Parameters used in the environmental pathways (DESCARTES) and radiological dose (CIDER) modules of the Hanford Environmental Dose Reconstruction Integrated Codes (HEDRIC) for the air pathway. Hanford Environmental Dose Reconstruction Project

Energy Technology Data Exchange (ETDEWEB)

Snyder, S.F.; Farris, W.T.; Napier, B.A.; Ikenberry, T.A.; Gilbert, R.O.

1992-09-01

This letter report is a description of work performed for the Hanford Environmental Dose Reconstruction (HEDR) Project. The HEDR Project was established to estimate the radiation doses to individuals resulting from releases of radionuclides from the Hanford Site since 1944. This work is being done by staff at Battelle, Pacific Northwest Laboratories (Battelle) under a contract with the Centers for Disease Control (CDC) with technical direction provided by an independent Technical Steering Panel (TSP). The objective of this report is to-document the environmental accumulation and dose-assessment parameters that will be used to estimate the impacts of past Hanford Site airborne releases. During 1993, dose estimates made by staff at Battelle will be used by the Fred Hutchinson Cancer Research Center as part of the Hanford Thyroid Disease Study (HTDS). This document contains information on parameters that are specific to the airborne release of the radionuclide iodine-131. Future versions of this document will include parameter information pertinent to other pathways and radionuclides.

Predictions of models for environmental radiological assessment

International Nuclear Information System (INIS)

Peres, Sueli da Silva; Lauria, Dejanira da Costa; Mahler, Claudio Fernando

2011-01-01

In the field of environmental impact assessment, models are used for estimating source term, environmental dispersion and transfer of radionuclides, exposure pathway, radiation dose and the risk for human beings Although it is recognized that the specific information of local data are important to improve the quality of the dose assessment results, in fact obtaining it can be very difficult and expensive. Sources of uncertainties are numerous, among which we can cite: the subjectivity of modelers, exposure scenarios and pathways, used codes and general parameters. The various models available utilize different mathematical approaches with different complexities that can result in different predictions. Thus, for the same inputs different models can produce very different outputs. This paper presents briefly the main advances in the field of environmental radiological assessment that aim to improve the reliability of the models used in the assessment of environmental radiological impact. The intercomparison exercise of model supplied incompatible results for 137 Cs and 60 Co, enhancing the need for developing reference methodologies for environmental radiological assessment that allow to confront dose estimations in a common comparison base. The results of the intercomparison exercise are present briefly. (author)

Environmental radiation exposure: Regulation, monitoring, and assessment

International Nuclear Information System (INIS)

Chen, S.Y.; Yu, C.; Hong, K.J.

1991-01-01

Radioactive releases to the environment from nuclear facilities constitute a public health concern. Protecting the public from such releases can be achieved through the establishment and enforcement of regulatory standards. In the United States, numerous standards have been promulgated to regulate release control at nuclear facilities. Most recent standards are more restrictive than those in the past and require that radioactivity levels be as low as reasonably achievable (ALARA). Environmental monitoring programs and radiological dose assessment are means of ensuring compliance with regulations. Environmental monitoring programs provide empirical information on releases, such as the concentrations of released radioactivity in environmental media, while radiological dose assessment provides the analytical means of quantifying dose exposures for demonstrating compliance

The embryogenesis of dose assessment at Hanford

International Nuclear Information System (INIS)

Foster, R.F.

1990-01-01

Several significant events occurred between 1955 and 1960 that resulted in major changes in environmental monitoring at Hanford and in the initiation of comprehensive dose assessments. These included: (1) specification of dose limits for nonoccupational exposure (including internal emitters); (2) a national and international awakening to the need for managing the disposal of radioactive wastes; (3) identification of the most important radionuclides and their sources of exposure; (4) data that quantified the transfer coefficients of nuclides along environmental pathways; and (5) development of greatly improved radiation detection instrumentation. In response to a growing need, the Hanford Laboratories formed the Environmental Studies and Evaluation component. This group revamped the monitoring and sampling programs so that analytical results contributed directly to dose estimation. Special studies were conducted to ascertain local dietary and recreational habits that affected dose calculations and to calibrate the models. These studies involved extensive contact with the public and governmental agencies, which elicited a positive reaction

Development of environmental dose assessment system (EDAS) code of PC version

Energy Technology Data Exchange (ETDEWEB)

Taki, Mitsumasa; Kikuchi, Masamitsu; Kobayashi, Hideo; Yamaguchi, Takenori [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

2003-05-01

A computer code (EDAS) was developed to assess the public dose for the safety assessment to get the license of nuclear reactor operation. This code system is used for the safety analysis of public around the nuclear reactor in normal operation and severe accident. This code was revised and composed for personal computer user according to the Nuclear Safety Guidelines reflected the ICRP1990 recommendation. These guidelines are revised by Nuclear Safety Commission on March, 2001, which are 'Weather analysis guideline for the safety assessment of nuclear power reactor', 'Public dose around the facility assessment guideline corresponding to the objective value for nuclear power light water reactor' and 'Public dose assessment guideline for safety review of nuclear power light water reactor'. This code has been already opened for public user by JAERI, and English version code and user manual are also prepared. This English version code is helpful for international cooperation concerning the nuclear safety assessment with JAERI. (author)

Development of environmental dose assessment system (EDAS) code of PC version

CERN Document Server

Taki, M; Kobayashi, H; Yamaguchi, T

2003-01-01

A computer code (EDAS) was developed to assess the public dose for the safety assessment to get the license of nuclear reactor operation. This code system is used for the safety analysis of public around the nuclear reactor in normal operation and severe accident. This code was revised and composed for personal computer user according to the Nuclear Safety Guidelines reflected the ICRP1990 recommendation. These guidelines are revised by Nuclear Safety Commission on March, 2001, which are 'Weather analysis guideline for the safety assessment of nuclear power reactor', 'Public dose around the facility assessment guideline corresponding to the objective value for nuclear power light water reactor' and 'Public dose assessment guideline for safety review of nuclear power light water reactor'. This code has been already opened for public user by JAERI, and English version code and user manual are also prepared. This English version code is helpful for international cooperation concerning the nuclear safety assessme...

Hanford Environmental Dose Reconstruction Project monthly report

International Nuclear Information System (INIS)

Finch, S.M.

1991-10-01

The objective of the Hanford Environmental Dose Reconstruction Project is to estimate the radiation doeses that individuals and populations could have received from nuclear operations at Hanford since 1944. The project is divided into the following technical tasks. These tasks correspond to the path radionuclides followed, from release to impact on humans (dose estimates): Source terms; environmental transport; environmental monitoring data; demographics, agriculture, food habits; environmental pathways and dose estimates

Design, implementation and verification of software code for radiation dose assessment based on simple generic environmental model

International Nuclear Information System (INIS)

I Putu Susila; Arif Yuniarto

2017-01-01

Radiation dose assessment to determine the potential of radiological impacts of various installations within nuclear facility complex is necessary to ensure environmental and public safety. A simple generic model-based method for calculating radiation doses caused by the release of radioactive substances into the environment has been published by the International Atomic Energy Agency (IAEA) as the Safety Report Series No. 19 (SRS-19). In order to assist the application of the assessment method and a basis for the development of more complex assessment methods, an open-source based software code has been designed and implemented. The software comes with maps and is very easy to be used because assessment scenarios can be done through diagrams. Software verification was performed by comparing its result to SRS-19 and CROM software calculation results. Dose estimated by SRS-19 are higher compared to the result of developed software. However, these are still acceptable since dose estimation in SRS-19 is based on conservative approach. On the other hand, compared to CROM software, the same results for three scenarios and a non-significant difference of 2.25 % in another scenario were obtained. These results indicate the correctness of our implementation and implies that the developed software is ready for use in real scenario. In the future, the addition of various features and development of new model need to be done to improve the capability of software that has been developed. (author)

Hanford Environmental Dose Reconstruction Project monthly report

International Nuclear Information System (INIS)

Finch, S.M.

1990-12-01

The objective of the Hanford Environmental Dose Reconstruction Project is to estimate the radiation doses that populations could have been have received from nuclear operations at Hanford since 1944. The project is being managed and conducted by the Pacific Northwest Laboratory (PNL) under the direction of an independent Technical Steering Panel (TSP). The project is divided into the following technical tasks. These tasks correspond to the path radionuclides followed, from release to impact on humans (dose estimates): source terms; environmental transport; environmental monitoring data; demographics, agriculture, food habits; and environmental pathways and dose estimates. 3 figs., 3 tabs

Sensitivity analysis of specific activity model parameters for environmental transport of 3H and dose assessment

International Nuclear Information System (INIS)

Rout, S.; Mishra, D.G.; Ravi, P.M.; Tripathi, R.M.

2016-01-01

Tritium is one of the radionuclides likely to get released to the environment from Pressurized Heavy Water Reactors. Environmental models are extensively used to quantify the complex environmental transport processes of radionuclides and also to assess the impact to the environment. Model parameters exerting the significant influence on model results are identified through a sensitivity analysis (SA). SA is the study of how the variation (uncertainty) in the output of a mathematical model can be apportioned, qualitatively or quantitatively, to different sources of variation in the input parameters. This study was designed to identify the sensitive model parameters of specific activity model (TRS 1616, IAEA) for environmental transfer of 3 H following release to air and then to vegetation and animal products. Model includes parameters such as air to soil transfer factor (CRs), Tissue Free Water 3 H to Organically Bound 3 H ratio (Rp), Relative humidity (RH), WCP (fractional water content) and WEQp (water equivalent factor) any change in these parameters leads to change in 3 H level in vegetation and animal products consequently change in dose due to ingestion. All these parameters are function of climate and/or plant which change with time, space and species. Estimation of these parameters at every time is a time consuming and also required sophisticated instrumentation. Therefore it is necessary to identify the sensitive parameters and freeze the values of least sensitive parameters at constant values for more accurate estimation of 3 H dose in short time for routine assessment

Environmental dose rate assessment of ITER using the Monte Carlo method

Directory of Open Access Journals (Sweden)

Karimian Alireza

2014-01-01

Full Text Available Exposure to radiation is one of the main sources of risk to staff employed in reactor facilities. The staff of a tokamak is exposed to a wide range of neutrons and photons around the tokamak hall. The International Thermonuclear Experimental Reactor (ITER is a nuclear fusion engineering project and the most advanced experimental tokamak in the world. From the radiobiological point of view, ITER dose rates assessment is particularly important. The aim of this study is the assessment of the amount of radiation in ITER during its normal operation in a radial direction from the plasma chamber to the tokamak hall. To achieve this goal, the ITER system and its components were simulated by the Monte Carlo method using the MCNPX 2.6.0 code. Furthermore, the equivalent dose rates of some radiosensitive organs of the human body were calculated by using the medical internal radiation dose phantom. Our study is based on the deuterium-tritium plasma burning by 14.1 MeV neutron production and also photon radiation due to neutron activation. As our results show, the total equivalent dose rate on the outside of the bioshield wall of the tokamak hall is about 1 mSv per year, which is less than the annual occupational dose rate limit during the normal operation of ITER. Also, equivalent dose rates of radiosensitive organs have shown that the maximum dose rate belongs to the kidney. The data may help calculate how long the staff can stay in such an environment, before the equivalent dose rates reach the whole-body dose limits.

EMP Attachment 3 DOE-SC PNNL Site Dose Assessment Guidance

Energy Technology Data Exchange (ETDEWEB)

Snyder, Sandra F.

2011-12-21

This Dose Assessment Guidance (DAG) describes methods to use to determine the Maximally-Exposed Individual (MEI) location and to estimate dose impact to that individual under the U.S. Department of Energy Office of Science (DOE-SC) Pacific Northwest National Laboratory (PNNL) Site Environmental Monitoring Plan (EMP). This guidance applies to public dose from radioactive material releases to the air from PNNL Site operations. This document is an attachment to the Pacific Northwest National Laboratory (PNNL) Environmental Monitoring Plan (EMP) and describes dose assessment guidance for radiological air emissions. The impact of radiological air emissions from the U.S. Department of Energy Office of Science (DOE-SC) PNNL Site is indicated by dose estimates to a maximally exposed member of the public, referred to as the maximally exposed individual (MEI). Reporting requirements associated with dose to members of the public from radiological air emissions are in 40 CFR Part 61.94, WAC 246-247-080, and DOE Order 458.1. The DOE Order and state standards for dose from radioactive air emissions are consistent with U.S. Environmental Protection Agency (EPA) dose standards in 40 CFR 61.92 (i.e., 10 mrem/yr to a MEI). Despite the fact that the current Contract Requirements Document (CRD) for the DOE-SC PNNL Site operations does not include the requirement to meet DOE CRD 458.1, paragraph 2.b, public dose limits, the DOE dose limits would be met when EPA limits are met.

Recommended environmental dose calculation methods and Hanford-specific parameters

International Nuclear Information System (INIS)

Schreckhise, R.G.; Rhoads, K.; Napier, B.A.; Ramsdell, J.V.; Davis, J.S.

1993-03-01

This document was developed to support the Hanford Environmental Dose overview Panel (HEDOP). The Panel is responsible for reviewing all assessments of potential doses received by humans and other biota resulting from the actual or possible environmental releases of radioactive and other hazardous materials from facilities and/or operations belonging to the US Department of Energy on the Hanford Site in south-central Washington. This document serves as a guide to be used for developing estimates of potential radiation doses, or other measures of risk or health impacts, to people and other biota in the environs on and around the Hanford Site. It provides information to develop technically sound estimates of exposure (i.e., potential or actual) to humans or other biotic receptors that could result from the environmental transport of potentially harmful materials that have been, or could be, released from Hanford operations or facilities. Parameter values and information that are specific to the Hanford environs as well as other supporting material are included in this document

Recommended environmental dose calculation methods and Hanford-specific parameters

Energy Technology Data Exchange (ETDEWEB)

Schreckhise, R.G.; Rhoads, K.; Napier, B.A.; Ramsdell, J.V. (Pacific Northwest Lab., Richland, WA (United States)); Davis, J.S. (Westinghouse Hanford Co., Richland, WA (United States))

1993-03-01

This document was developed to support the Hanford Environmental Dose overview Panel (HEDOP). The Panel is responsible for reviewing all assessments of potential doses received by humans and other biota resulting from the actual or possible environmental releases of radioactive and other hazardous materials from facilities and/or operations belonging to the US Department of Energy on the Hanford Site in south-central Washington. This document serves as a guide to be used for developing estimates of potential radiation doses, or other measures of risk or health impacts, to people and other biota in the environs on and around the Hanford Site. It provides information to develop technically sound estimates of exposure (i.e., potential or actual) to humans or other biotic receptors that could result from the environmental transport of potentially harmful materials that have been, or could be, released from Hanford operations or facilities. Parameter values and information that are specific to the Hanford environs as well as other supporting material are included in this document.

Hanford Environmental Dose Reconstruction Project monthly report

International Nuclear Information System (INIS)

McMakin, A.H., Cannon, S.D.; Finch, S.M.

1992-09-01

The objective of the Hanford Environmental Dose Reconstruction MDR) Project is to estimate the radiation doses that individuals and populations could have received from nuclear operations at Hanford since 1944. The TSP consists of experts in envirorunental pathways. epidemiology, surface-water transport, ground-water transport, statistics, demography, agriculture, meteorology, nuclear engineering. radiation dosimetry. and cultural anthropology. Included are appointed members representing the states of Oregon, Washington, and Idaho, a representative of Native American tribes, and an individual representing the public. The project is divided into the following technical tasks. These tasks correspond to the path radionuclides followed from release to impact on humans (dose estimates): Source Terms; Environmental Transport; Environmental Monitoring Data Demography, Food Consumption, and Agriculture; and Environmental Pathways and Dose Estimates

The Hanford Environmental Dose Reconstruction (HEDR) Project: Technical approach

International Nuclear Information System (INIS)

Napier, B.A.; Freshley, M.D.; Gilbert, R.O.; Haerer, H.A.; Morgan, L.G.; Rhoads, R.E.; Woodruff, R.K.

1990-01-01

Historical measurements and current assessment techniques are being combined to estimate potential radiation doses to people from radioactive releases to the air, the Columbia River, soils, and ground water at the Hanford Site since 1944. Environmental contamination from these releases has been monitored, at varying levels of detail, for 45 yr. Phase I of the Hanford Environmental Reconstruction Project will estimate the magnitude of potential doses, their areal extends, and their associated uncertainties. The Phase I study area comprises 10 counties in eastern Washington and northern Oregon, within a 100-mi radius of the site, including a stretch of the Columbia River that was most significantly affected. These counties contain a range of projected and measured contaminant levels, environmental exposure pathways, and population groups. Phase I dose estimates are being developed for the periods 1944 through 1947 for air pathways and 1964 through 1966 for river pathways. Important radionuclide/pathway combinations include fission products, such as 131 I, in milk for early atmospheric releases and activation products, such as 32 P and 65 Zn, in fish for releases to the river. Potential doses range over several orders of magnitude within the study area. We will expand the time periods and study are in three successive phases, as warranted by results of Phase I

Environmental gamma-ray dose measurements with thermoluminescence dosemeters (TLD) and environmental radiation characteristics

International Nuclear Information System (INIS)

Kanematsu, Seiko

1999-01-01

It is important to evaluate environmental gamma-ray exposure both at work and home in order to assess people's collective dosages. Environmental gamma radiation was measured for air-absorbed dose with a thermoluminescence dosemeter at various points in the workplace and Ningyotoge, and workplace radiation characteristics were analyzed. From the results, the public dose due to gamma rays generated artificially was assessed to be sufficiently lower than the annual limit. For indoor environments of the workplace, the maximum dosage rate among measured values was 97 nGy/h and the minimum value was 70 nGy/h, the average over one year was 83 nGy/h. The average annual outdoor dosage for a year was 82 nGy/ h. In Ningyotoge, the maximum was 103 nGy/h, minimum 60 nGy/h, and average 88 nGy/h. These values depend on the nature of the soil and weather factors, showing higher values in the summer than in the winter in the workplace. There was no significant difference in the dosage rate in houses and the workplace. (author)

Dose measurement, its distribution and individual external dose assessments of inhabitants on high background radiation area in China

Energy Technology Data Exchange (ETDEWEB)

Koga, Taeko; Morishima, Hiroshige [Kinki Univ., Atomic Energy Research Institute, Osaka (Japan); Tatsumi, Kusuo [Kinki Univ., Life Science Research Institute, Osaka (Japan); Nakai, Sayaka; Sugahara, Tsutomu [Health Research Foundation, Kyoto (Japan); Yuan Yongling [Labor Hygiene Institute of Hunan Prov. (China); Wei Luxin [Laboratory of Industorial Hygiene, Ministry of Health (China)

2001-01-01

As a part of the China-Japan cooperative research on the natural radiation epidemiology, we have carried out a dose-assessment study to evaluate the external to natural radiation in the high background radiation area (HBRA) of Yangjiang in Guangdong province and in the control area (CA) of Enping prefecture since 1991. Because of the difficulties in measuring the individual doses of all inhabitants directly by the personal dosimeters, an indirect method was applied to estimate the exposed dose rates from the environmental radiation dose rates measured by survey meters and the occupancy factors of each hamlet. An individual radiation dose roughly correlates with the environmental radiation dose and the life style of the inhabitant. We have analyzed the environmental radiation doses in the hamlets and the variation of the occupancy factors to obtain the parameters of dose estimation on the inhabitants in selected hamlets; Madi and the several hamlets of the different level doses in HBRA and Hampizai hamlet in CA. With these parameters, we made estimations of individual dose rates and compared them with those obtained from the direct measurement using dosimeters carried by selected individuals. The results obtained are as follows: (1) The environmental radiation dose rates are influenced by the natural radioactive nuclide concentrations in building materials, the age of the building and the arrangement of the houses in a hamlet. There existed a fairly large and heterogeneous distribution of indoor and outdoor environmental radiation. The indoor radiation dose rates were due to the exposure from the natural radioactive nuclides in the building materials and they were about twice higher than the outdoor radiation dose rates. This difference was not observed in CA. (2) The occupancy factor was affected by the age of individuals and the seasons of a year. Indoor occupancy factors were higher for infants and aged individuals than for other age groups. This lead to higher

Dose measurement, its distribution and individual external dose assessments of inhabitants on high background radiation area in China

International Nuclear Information System (INIS)

Koga, Taeko; Morishima, Hiroshige; Tatsumi, Kusuo; Nakai, Sayaka; Sugahara, Tsutomu; Yuan Yongling; Wei Luxin

2001-01-01

As a part of the China-Japan cooperative research on the natural radiation epidemiology, we have carried out a dose-assessment study to evaluate the external to natural radiation in the high background radiation area (HBRA) of Yangjiang in Guangdong province and in the control area (CA) of Enping prefecture since 1991. Because of the difficulties in measuring the individual doses of all inhabitants directly by the personal dosimeters, an indirect method was applied to estimate the exposed dose rates from the environmental radiation dose rates measured by survey meters and the occupancy factors of each hamlet. An individual radiation dose roughly correlates with the environmental radiation dose and the life style of the inhabitant. We have analyzed the environmental radiation doses in the hamlets and the variation of the occupancy factors to obtain the parameters of dose estimation on the inhabitants in selected hamlets; Madi and the several hamlets of the different level doses in HBRA and Hampizai hamlet in CA. With these parameters, we made estimations of individual dose rates and compared them with those obtained from the direct measurement using dosimeters carried by selected individuals. The results obtained are as follows: 1) The environmental radiation dose rates are influenced by the natural radioactive nuclide concentrations in building materials, the age of the building and the arrangement of the houses in a hamlet. There existed a fairly large and heterogeneous distribution of indoor and outdoor environmental radiation. The indoor radiation dose rates were due to the exposure from the natural radioactive nuclides in the building materials and they were about twice higher than the outdoor radiation dose rates. This difference was not observed in CA. 2) The occupancy factor was affected by the age of individuals and the seasons of a year. Indoor occupancy factors were higher for infants and aged individuals than for other age groups. This lead to higher

Dose assessment activities in the Republic of the Marshall Islands

International Nuclear Information System (INIS)

Simon, S.L.; Graham, J.C.

1996-01-01

Dose assessments, both retrospective and prospective, comprise one important function of a radiological study commissioned by the Republic of the Marshall Islands (RMI) government in late 1989. Estimating past or future exposure requires the synthesis of information from historical data, results from a recently completed field monitoring program, laboratory measurements, and some experimental studies. Most of the activities in the RMI to date have emphasized a pragmatic rather than theoretical approach. In particular, most of the recent effort has been expended on conducting an independent radiological monitoring program to determine the degree of deposition and the geographical extent of weapons test fallout over the nation. Contamination levels on 70% of the land mass of the Marshall Islands were unknown prior to 1994. The environmental radioactivity data play an integral role in both retrospective and prospective assessments. One recent use of dose assessment has been to interpret environmental measurements of radioactivity into annual doses that might be expected at every atoll. A second use for dose assessment has been to determine compliance with dose action level for the rehabitation of Rongelap Island. Careful examination of exposure pathways relevant to the island lifestyle has been necessary to accommodate these purposes. Finally, an examination is underway of gummed film, fixed-instrument, and aerial survey data accumulated during the 1950's by the Health and Safety Laboratory of the U.S. AEC. This article gives an overview of these many different activities and a summary of recent dose assessments

Meteorological monitoring for environmental/dose assessment and emergency response modeling: How much is enough?

International Nuclear Information System (INIS)

Glantz, C.S.

1989-01-01

In evaluation the effectiveness and appropriateness of meteorological monitoring programs, managers responsible for planning and operating emergency response or environmental/dose assessment systems must routinely question whether enough meteorological data are being obtained to adequately support system applications. There is no simple answer or cookbook procedure that can be followed in generating an appropriate answer to this question. The answer must be developed through detailed consideration of the intended applications for the data, the capabilities of the models that would use the data, pollutant release characteristics, terrain in the modeling region, the size of the modeling domain, and the distribution of human population in the modeling domain. It is recommended that manager consult meteorologists when assessing these factors; the meteorologist's detailed knowledge of, and experience in, studying atmospheric transport and diffusion should assist the manager in determining the appropriate level of meteorological monitoring. 1 ref

Discussion of some issues in assessing nuclear and radiation environmental impacts and in related assessment

International Nuclear Information System (INIS)

Pan Ziqiang

1998-01-01

The author discusses some noticeable issues in drafting assessment report of nuclear and radiation environmental impacts and relevant aspects needed to be considered from the point of view of comprehensive environmental assessment. The considerable issue are principles of radioactive waste management, optimization of radiation protection and collective dose, and uncertainty of the assessment. Implementing reporting system on assessment of nuclear and radiation environmental impacts would improve environmental protection for nuclear and radiation facilities. However, trade's, regional , country and global assessment of environmental impacts has to be enhanced. For this purpose, it is necessary to develop methodology of qualitative and quantitative comprehensive assessment

Hanford Environmental Dose Reconstruction Project monthly report, August 1992

International Nuclear Information System (INIS)

McMakin, A.H.; Cannon, S.D.; Finch, S.M.

1992-01-01

The objective of the Hanford Environmental Dose Reconstruction (HEDR) Project is to estimate the radiation doses that individuals and populations could have received from nuclear operations at Hanford since 1944. The project is divided into the following technical tasks. These tasks correspond to the path radionuclides followed from release to impact on humans (dose estimates): source terms; environmental transport; environmental monitoring data; demography; food consumption; and agriculture; and environmental pathway and dose estimates

Parameters used in the environmental pathways (DESCARTES) and radiological dose (CIDER) modules of the Hanford Environmental Dose Reconstruction Integrated Codes (HEDRIC) for the air pathway

Energy Technology Data Exchange (ETDEWEB)

Snyder, S.F.; Farris, W.T.; Napier, B.A.; Ikenberry, T.A.; Gilbert, R.O.

1992-09-01

This letter report is a description of work performed for the Hanford Environmental Dose Reconstruction (HEDR) Project. The HEDR Project was established to estimate the radiation doses to individuals resulting from releases of radionuclides from the Hanford Site since 1944. This work is being done by staff at Battelle, Pacific Northwest Laboratories (Battelle) under a contract with the Centers for Disease Control (CDC) with technical direction provided by an independent Technical Steering Panel (TSP). The objective of this report is to-document the environmental accumulation and dose-assessment parameters that will be used to estimate the impacts of past Hanford Site airborne releases. During 1993, dose estimates made by staff at Battelle will be used by the Fred Hutchinson Cancer Research Center as part of the Hanford Thyroid Disease Study (HTDS). This document contains information on parameters that are specific to the airborne release of the radionuclide iodine-131. Future versions of this document will include parameter information pertinent to other pathways and radionuclides.

Parameters used in the environmental pathways (DESCARTES) and radiological dose (CIDER) modules of the Hanford Environmental Dose Reconstruction Integrated Codes (HEDRIC) for the air pathway

International Nuclear Information System (INIS)

Snyder, S.F.; Farris, W.T.; Napier, B.A.; Ikenberry, T.A.; Gilbert, R.O.

1992-09-01

This letter report is a description of work performed for the Hanford Environmental Dose Reconstruction (HEDR) Project. The HEDR Project was established to estimate the radiation doses to individuals resulting from releases of radionuclides from the Hanford Site since 1944. This work is being done by staff at Battelle, Pacific Northwest Laboratories (Battelle) under a contract with the Centers for Disease Control (CDC) with technical direction provided by an independent Technical Steering Panel (TSP). The objective of this report is to-document the environmental accumulation and dose-assessment parameters that will be used to estimate the impacts of past Hanford Site airborne releases. During 1993, dose estimates made by staff at Battelle will be used by the Fred Hutchinson Cancer Research Center as part of the Hanford Thyroid Disease Study (HTDS). This document contains information on parameters that are specific to the airborne release of the radionuclide iodine-131. Future versions of this document will include parameter information pertinent to other pathways and radionuclides

Internal Dose Conversion Coefficients of Domestic Reference Animal and Plants for Dose Assessment of Non-human Species

International Nuclear Information System (INIS)

Keum, Dong Kwon; Jun, In; Lim, Kwang Muk; Choi, Yong Ho

2009-01-01

Traditionally, radiation protection has been focused on a radiation exposure of human beings. In the international radiation protection community, one of the recent key issues is to establish the methodology for assessing the radiological impact of an ionizing radiation on non-human species for an environmental protection. To assess the radiological impact to non-human species dose conversion coefficients are essential. This paper describes the methodology to calculate the internal dose conversion coefficient for non-human species and presents calculated internal dose conversion coefficients of 25 radionuclides for 8 domestic reference animal and plants

The Hanford Environmental Dose Reconstruction Project: Overview

International Nuclear Information System (INIS)

Haerer, H.A.; Freshley, M.D.; Gilbert, R.O.; Morgan, L.G.; Napier, B.A.; Rhoads, R.E.; Woodruff, R.K.

1990-01-01

In 1988, researchers began a multiyear effort to estimate radiation doses that people could have received since 1944 at the U.S. Department of Energy's Hanford Site. The study was prompted by increasing concern about potential health effects to the public from more than 40 yr of nuclear activities. We will provide an overview of the Hanford Environmental Dose Reconstruction Project and its technical approach. The work has required development of new methods and tools for dealing with unique technical and communication challenges. Scientists are using a probabilistic, rather than the more typical deterministic, approach to generate dose distributions rather than single-point estimates. Uncertainties in input parameters are reflected in dose results. Sensitivity analyses are used to optimize project resources and define the project's scope. An independent technical steering panel directs and approves the work in a public forum. Dose estimates are based on review and analysis of historical data related to operations, effluents, and monitoring; determination of important radionuclides; and reconstruction of source terms, environmental conditions that affected transport, concentrations in environmental media, and human elements, such as population distribution, agricultural practices, food consumption patterns, and lifestyles. A companion paper in this volume, The Hanford Environmental Dose Reconstruction Project: Technical Approach, describes the computational framework for the work

Environmental impact assessment around TRIGA research reactor

International Nuclear Information System (INIS)

Lee, Jeong Ho; Lee, Hyun Duk; Lee, Young Bok; Cheong, Kyu Hoi; Ahn, Jong Sung; Kim, Kug Chan; You, Byung Sun; Kim, Byung Woo; Kim, Sang Bok; Han Moon Hee

1985-01-01

Population distribution, atmospheric change, X/Q, characteristics of terrestrial ecosystem around Seoul site were surveyed. Environmental radiation and radioactivities such as grossα, grossβ, Cs-137, Sr-90 and H-3 of various environmental samples were analyzed. The values of environmental radiation dose tended to increase gradually in the light of the recent five years' results of environmental radiation monitoring around the nuclear power plants from 1980 to 1984, however, the changes were not significant. In addition, continuous assessment of environmental radiation monitoring on the roofs of main building and life science building at KAERI showed that the environmental radiation dose tended to increase a little during the night time. Judging from the above results, it is concluded that environmental contamination level by radioactive materials could be ignored in the case of radioisotope production or experiment using radioisotopes except the release of gaseous radioactive materials such as Ar-41 of short half life by the operation of nuclear reactor. (Author)

Characteristics of the graded wildlife dose assessment code K-BIOTA and its application

Energy Technology Data Exchange (ETDEWEB)

Keum, Dong Kwon; Jun, In; Lim, Kwang Muk; Kim, Byeong Ho; Choi, Yong Ho [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2015-12-15

This paper describes the technical background for the Korean wildlife radiation dose assessment code, K-BIOTA, and the summary of its application. The K-BIOTA applies the graded approaches of 3 levels including the screening assessment (Level 1 and 2), and the detailed assessment based on the site specific data (Level 3). The screening level assessment is a preliminary step to determine whether the detailed assessment is needed, and calculates the dose rate for the grouped organisms, rather than an individual biota. In the Level 1 assessment, the risk quotient (RQ) is calculated by comparing the actual media concentration with the environmental media concentration limit (EMCL) derived from a bench-mark screening reference dose rate. If RQ for the Level 1 assessment is less than 1, it can be determined that the ecosystem would maintain its integrity, and the assessment is terminated. If the RQ is greater than 1, the Level 2 assessment, which calculates RQ using the average value of the concentration ratio (CR) and equilibrium distribution coefficient (Kd) for the grouped organisms, is carried out for the more realistic assessment. Thus, the Level 2 assessment is less conservative than the Level 1 assessment. If RQ for the Level 2 assessment is less than 1, it can be determined that the ecosystem would maintain its integrity, and the assessment is terminated. If the RQ is greater than 1, the Level 3 assessment is performed for the detailed assessment. In the Level 3 assessment, the radiation dose for the representative organism of a site is calculated by using the site specific data of occupancy factor, CR and Kd. In addition, the K-BIOTA allows the uncertainty analysis of the dose rate on CR, Kd and environmental medium concentration among input parameters optionally in the Level 3 assessment. The four probability density functions of normal, lognormal, uniform and exponential distribution can be applied. The applicability of the code was tested through the

Characteristics of the graded wildlife dose assessment code K-BIOTA and its application

International Nuclear Information System (INIS)

Keum, Dong Kwon; Jun, In; Lim, Kwang Muk; Kim, Byeong Ho; Choi, Yong Ho

2015-01-01

This paper describes the technical background for the Korean wildlife radiation dose assessment code, K-BIOTA, and the summary of its application. The K-BIOTA applies the graded approaches of 3 levels including the screening assessment (Level 1 and 2), and the detailed assessment based on the site specific data (Level 3). The screening level assessment is a preliminary step to determine whether the detailed assessment is needed, and calculates the dose rate for the grouped organisms, rather than an individual biota. In the Level 1 assessment, the risk quotient (RQ) is calculated by comparing the actual media concentration with the environmental media concentration limit (EMCL) derived from a bench-mark screening reference dose rate. If RQ for the Level 1 assessment is less than 1, it can be determined that the ecosystem would maintain its integrity, and the assessment is terminated. If the RQ is greater than 1, the Level 2 assessment, which calculates RQ using the average value of the concentration ratio (CR) and equilibrium distribution coefficient (Kd) for the grouped organisms, is carried out for the more realistic assessment. Thus, the Level 2 assessment is less conservative than the Level 1 assessment. If RQ for the Level 2 assessment is less than 1, it can be determined that the ecosystem would maintain its integrity, and the assessment is terminated. If the RQ is greater than 1, the Level 3 assessment is performed for the detailed assessment. In the Level 3 assessment, the radiation dose for the representative organism of a site is calculated by using the site specific data of occupancy factor, CR and Kd. In addition, the K-BIOTA allows the uncertainty analysis of the dose rate on CR, Kd and environmental medium concentration among input parameters optionally in the Level 3 assessment. The four probability density functions of normal, lognormal, uniform and exponential distribution can be applied. The applicability of the code was tested through the

Modelling of Biota Dose Effects. Report of Working Group 6 Biota Dose Effects Modelling of EMRAS II Topical Heading Reference Approaches for Biota Dose Assessment. Environmental Modelling for RAdiation Safety (EMRAS II) Programme

International Nuclear Information System (INIS)

2014-07-01

Environmental assessment models are used for evaluating the radiological impact of actual and potential releases of radionuclides to the environment. They are essential tools for use in the regulatory control of routine discharges to the environment and in planning the measures to be taken in the event of accidental releases. They are also used for predicting the impact of releases which may occur far into the future, for example, from underground radioactive waste repositories. It is important to verify, to the extent possible, the reliability of the predictions of such models by a comparison with measured values in the environment or with the predictions of other models. The IAEA has been organizing programmes on international model testing since the 1980s. These programmes have contributed to a general improvement in models, in the transfer of data and in the capabilities of modellers in Member States. IAEA publications on this subject over the past three decades demonstrate the comprehensive nature of the programmes and record the associated advances which have been made. From 2009 to 2011, the IAEA organized a project entitled Environmental Modelling for RAdiation Safety (EMRAS II), which concentrated on the improvement of environmental transfer models and the development of reference approaches to estimate the radiological impacts on humans, as well as on flora and fauna, arising from radionuclides in the environment. Different aspects were addressed by nine working groups covering three themes: reference approaches for human dose assessment, reference approaches for biota dose assessment and approaches for addressing emergency situations. This publication describes the work of the Biota Effects Modelling Working Group

Modelling of Biota Dose Effects. Report of Working Group 6 Biota Dose Effects Modelling of EMRAS II Topical Heading Reference Approaches for Biota Dose Assessment. Environmental Modelling for RAdiation Safety (EMRAS II) Programme

Energy Technology Data Exchange (ETDEWEB)

NONE

2014-07-15

Environmental assessment models are used for evaluating the radiological impact of actual and potential releases of radionuclides to the environment. They are essential tools for use in the regulatory control of routine discharges to the environment and in planning the measures to be taken in the event of accidental releases. They are also used for predicting the impact of releases which may occur far into the future, for example, from underground radioactive waste repositories. It is important to verify, to the extent possible, the reliability of the predictions of such models by a comparison with measured values in the environment or with the predictions of other models. The IAEA has been organizing programmes on international model testing since the 1980s. These programmes have contributed to a general improvement in models, in the transfer of data and in the capabilities of modellers in Member States. IAEA publications on this subject over the past three decades demonstrate the comprehensive nature of the programmes and record the associated advances which have been made. From 2009 to 2011, the IAEA organized a project entitled Environmental Modelling for RAdiation Safety (EMRAS II), which concentrated on the improvement of environmental transfer models and the development of reference approaches to estimate the radiological impacts on humans, as well as on flora and fauna, arising from radionuclides in the environment. Different aspects were addressed by nine working groups covering three themes: reference approaches for human dose assessment, reference approaches for biota dose assessment and approaches for addressing emergency situations. This publication describes the work of the Biota Effects Modelling Working Group.

Hanford Environmental Dose Reconstruction Project, Quarterly report, September--November 1993

International Nuclear Information System (INIS)

Cannon, S.D.; Finch, S.M.

1993-01-01

The objective of the Hanford Environmental Dose Reconstruction (HEDR) Project is to estimate the radiation doses that individuals and populations could have received from nuclear operations at Hanford since 1944. The project is divided into the following technical tasks. These tasks correspond to the path radionuclides followed from release to impact on humans (dose estimates); Source Terms, Environmental Transport, Environmental Monitoring Data, Demography, Food Consumption, and Agriculture, and Environmental Pathways and Dose Estimates

Evaluation of the environmental dose commitment due to radium-contaminated soil

International Nuclear Information System (INIS)

Feldman, J.; Eng, J.; Giardina, P.A.

1979-01-01

The Middlesex Sampling Plant located in Middlesex, NJ was a uranium ore sampling plant operating during the 1940s and 1950s. A radiological problem was identified during a routine program to resurvey selected former MED/AEC sites which are no longer under government control. The survey, when conducted by the US Department of Energy (DOE), indicated that the Middlesex facility had a radium and radon problem on-site as well as off-site, where some of the contaminated soil was used as landfill. The old sampling plant is presently being used as a Marine Corps Reserve Training Center. Subsequent, more detailed studies have identified possible solutions to the contamination problem. The US Environmental Protection Agency (EPA) is examining cleanup options based on a cost/benefit analysis utilizing the environmental dose commitment concept rather than an annual dose calculation. The practice of using dose to local populations as a basis for impact assessment can lead to a large underestimate of the total potential impact from the continuous environmental release of radon

Recommended environmental dose calculation methods and Hanford-specific parameters. Revision 2

Energy Technology Data Exchange (ETDEWEB)

Schreckhise, R.G.; Rhoads, K.; Napier, B.A.; Ramsdell, J.V. [Pacific Northwest Lab., Richland, WA (United States); Davis, J.S. [Westinghouse Hanford Co., Richland, WA (United States)

1993-03-01

This document was developed to support the Hanford Environmental Dose overview Panel (HEDOP). The Panel is responsible for reviewing all assessments of potential doses received by humans and other biota resulting from the actual or possible environmental releases of radioactive and other hazardous materials from facilities and/or operations belonging to the US Department of Energy on the Hanford Site in south-central Washington. This document serves as a guide to be used for developing estimates of potential radiation doses, or other measures of risk or health impacts, to people and other biota in the environs on and around the Hanford Site. It provides information to develop technically sound estimates of exposure (i.e., potential or actual) to humans or other biotic receptors that could result from the environmental transport of potentially harmful materials that have been, or could be, released from Hanford operations or facilities. Parameter values and information that are specific to the Hanford environs as well as other supporting material are included in this document.

Risk and environmental impact assessment: nuclear and environmental licensing interface

International Nuclear Information System (INIS)

Costa, Eduardo M.; Monteiro, Iara A.

1997-01-01

The main aims of this paper are the identification and discussion of interfaces and application of common concepts in the existing nuclear and environmental licensing procedures. Risk and impact assessment of nuclear electricity generation are two of these concepts which are discussed detail. The risk concept, which had initially focused on engineering projects, has been extended to many other areas of human activity. Risk resulting from the use of ionization radiation has been associated to the dose for the critical members of the public. Therefore, radiation protection applies basic dose limits which are established in national and international recommendations. These recommendations are increasing the emphasis to keep all the exposures to ionizing radiation as low as reasonable achievable, economical and social factors being taken into account. On the other hand, environmental impact assessment has been used as a tool in planning and decision-making processes, thus including environmental concern in the discussion of social and economical development strategies. This paper aims to discuss the association of these two concepts by presenting the procedures of control of radiological impact during normal operation of a nuclear power plant and the various forms of risk communication to the public in the case of events occurrence. (author). 13 refs

Dose measurement, its distribution and individual external dose assessments of inhabitants in the high background radiation areas in China

International Nuclear Information System (INIS)

Morishima, Hiroshige; Koga, Taeko; Tatsumi, Kusuo; Nakai, Sayaka; Sugahara, Tsutomu; Yuan Yongling; Wei Luxin

2000-01-01

As a part of the China-Japan cooperative research on natural radiation epidemiology, we have carried out a dose-assessment study to evaluate the external exposure to natural radiation in the high background radiation areas (HBRA) of Yangjiang in Guangdong province and in the control areas (CA) of Enping prefecture since 1991. Because of the difficulties in measuring the individual doses of all inhabitants directly by personal dosimeters, an indirect method was applied in which the exposed individual doses were estimated from the environmental radiation doses measured by survey meters and the occupancy factors of each hamlet. We analyzed the dose in the hamlets and the variation in the occupancy factors to obtain the parameters of dose estimation on the inhabitants in selected hamlets; Madi and several hamlets of different dose levels in HBRA and Hampizai hamlet in CA. With these parameters, we estimated individual dose rates and compared them with those obtained from direct measurement using dosimeters carried by selected individuals. The results obtained are as follows. The environmental radiation doses are influenced by the natural radioactive nuclide concentrations in building materials, the age of the building and the arrangement of the houses in a hamlet. There existed a fairly large and heterogeneous distribution of indoor and outdoor environmental radiations. The indoor radiation doses were due to exposure from the natural radioactive nuclides in the building materials and were about two times as large as the outdoor radiation doses. The difference between indoor and outdoor doses was not observed in CA. The occupancy factor was influenced by the age of individuals and by the season of the year. The occupancy factor was higher for infants and aged individuals than for other age groups. This lead to higher dose rates of exposure to those age groups. A good correlation was observed between the dose assessed indirectly and that measured directly and the

Dose measurement, its distribution and individual external dose assessments of inhabitants in the high background radiation areas in China

Energy Technology Data Exchange (ETDEWEB)

Morishima, Hiroshige; Koga, Taeko [Kinki Univ., Higashi-Osaka, Osaka (Japan). Atomic Energy Research Inst.; Tatsumi, Kusuo; Nakai, Sayaka; Sugahara, Tsutomu; Yuan Yongling; Wei Luxin

2000-10-01

As a part of the China-Japan cooperative research on natural radiation epidemiology, we have carried out a dose-assessment study to evaluate the external exposure to natural radiation in the high background radiation areas (HBRA) of Yangjiang in Guangdong province and in the control areas (CA) of Enping prefecture since 1991. Because of the difficulties in measuring the individual doses of all inhabitants directly by personal dosimeters, an indirect method was applied in which the exposed individual doses were estimated from the environmental radiation doses measured by survey meters and the occupancy factors of each hamlet. We analyzed the dose in the hamlets and the variation in the occupancy factors to obtain the parameters of dose estimation on the inhabitants in selected hamlets; Madi and several hamlets of different dose levels in HBRA and Hampizai hamlet in CA. With these parameters, we estimated individual dose rates and compared them with those obtained from direct measurement using dosimeters carried by selected individuals. The results obtained are as follows. The environmental radiation doses are influenced by the natural radioactive nuclide concentrations in building materials, the age of the building and the arrangement of the houses in a hamlet. There existed a fairly large and heterogeneous distribution of indoor and outdoor environmental radiations. The indoor radiation doses were due to exposure from the natural radioactive nuclides in the building materials and were about two times as large as the outdoor radiation doses. The difference between indoor and outdoor doses was not observed in CA. The occupancy factor was influenced by the age of individuals and by the season of the year. The occupancy factor was higher for infants and aged individuals than for other age groups. This lead to higher dose rates of exposure to those age groups. A good correlation was observed between the dose assessed indirectly and that measured directly and the

Environmental radiation monitoring: mobile gamma dose rate measurements along Mumbai-Hyderabad rail route and Hyderabad city roads

International Nuclear Information System (INIS)

Divkar, J.K.; Padmanabhan, N.; Chaudhury, Probal; Pradeepkumar, K.S.; Pujari, R.N.; Dogra, Santosh; Sharma, D.N.; Rajagopalan, S.; Srivastava, G.K.

2005-01-01

Environmental Radiation monitoring based on gamma dose rate logging on a mobile platform integrated with real time position from a Global Positioning System is an effective tool to acquire dose rate profile and generate radiological map of any geographical region. The microcontroller based dose rate data acquisition system capable of storing the acquired data and transferring to an attached laptop/PC and providing a graphical illustration of relative variations in gamma background can also be used for quick assessment of environmental radiological impact assessment. This paper describes the methodology and results of the environmental gamma dose rate monitoring surveys carried out: (i) on Mumbai-Hyderabad rail route with the systems installed in the trains guard's room and (ii) Hyderabad city roads with systems installed in a monitoring van. The results indicate significant difference in the gamma background measured along the rail route between Mumbai-Hyderabad and in the radiological map generated after the Hyderabad city survey. (author)

Environmental impact statement analysis: dose methodology

International Nuclear Information System (INIS)

Mueller, M.A.; Strenge, D.L.; Napier, B.A.

1981-01-01

Standardized sections and methodologies are being developed for use in environmental impact statements (EIS) for activities to be conducted on the Hanford Reservation. Five areas for standardization have been identified: routine operations dose methodologies, accident dose methodology, Hanford Site description, health effects methodology, and socioeconomic environment for Hanford waste management activities

The system of radiation dose assessment and dose conversion coefficients in the ICRP and FGR

Energy Technology Data Exchange (ETDEWEB)

Kim, So Ra; Min, Byung Il; Park, Kihyun; Yang, Byung Mo; Suh, Kyung Suk [Nuclear Environmental Safety Research Division, Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2016-12-15

The International Commission on Radiological Protection (ICRP) recommendations and the Federal Guidance Report (FGR) published by the U.S. Environmental Protection Agency (EPA) have been widely applied worldwide in the fields of radiation protection and dose assessment. The dose conversion coefficients of the ICRP and FGR are widely used for assessing exposure doses. However, before the coefficients are used, the user must thoroughly understand the derivation process of the coefficients to ensure that they are used appropriately in the evaluation. The ICRP provides recommendations to regulatory and advisory agencies, mainly in the form of guidance on the fundamental principles on which appropriate radiological protection can be based. The FGR provides federal and state agencies with technical information to assist their implementation of radiation protection programs for the U.S. population. The system of radiation dose assessment and dose conversion coefficients in the ICRP and FGR is reviewed in this study. A thorough understanding of their background is essential for the proper use of dose conversion coefficients. The FGR dose assessment system was strongly influenced by the ICRP and the U.S. National Council on Radiation Protection and Measurements (NCRP), and is hence consistent with those recommendations. Moreover, the ICRP and FGR both used the scientific data reported by Biological Effects of Ionizing Radiation (BEIR) and United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR) as their primary source of information. The difference between the ICRP and FGR lies in the fact that the ICRP utilized information regarding a population of diverse races, whereas the FGR utilized data on the American population, as its goal was to provide guidelines for radiological protection in the US. The contents of this study are expected to be utilized as basic research material in the areas of radiation protection and dose assessment.

The system of radiation dose assessment and dose conversion coefficients in the ICRP and FGR

International Nuclear Information System (INIS)

Kim, So Ra; Min, Byung Il; Park, Kihyun; Yang, Byung Mo; Suh, Kyung Suk

2016-01-01

The International Commission on Radiological Protection (ICRP) recommendations and the Federal Guidance Report (FGR) published by the U.S. Environmental Protection Agency (EPA) have been widely applied worldwide in the fields of radiation protection and dose assessment. The dose conversion coefficients of the ICRP and FGR are widely used for assessing exposure doses. However, before the coefficients are used, the user must thoroughly understand the derivation process of the coefficients to ensure that they are used appropriately in the evaluation. The ICRP provides recommendations to regulatory and advisory agencies, mainly in the form of guidance on the fundamental principles on which appropriate radiological protection can be based. The FGR provides federal and state agencies with technical information to assist their implementation of radiation protection programs for the U.S. population. The system of radiation dose assessment and dose conversion coefficients in the ICRP and FGR is reviewed in this study. A thorough understanding of their background is essential for the proper use of dose conversion coefficients. The FGR dose assessment system was strongly influenced by the ICRP and the U.S. National Council on Radiation Protection and Measurements (NCRP), and is hence consistent with those recommendations. Moreover, the ICRP and FGR both used the scientific data reported by Biological Effects of Ionizing Radiation (BEIR) and United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR) as their primary source of information. The difference between the ICRP and FGR lies in the fact that the ICRP utilized information regarding a population of diverse races, whereas the FGR utilized data on the American population, as its goal was to provide guidelines for radiological protection in the US. The contents of this study are expected to be utilized as basic research material in the areas of radiation protection and dose assessment

Evaluation of effective dose equivalent from environmental gamma rays

International Nuclear Information System (INIS)

Saito, K.; Tsutsumi, M.; Moriuchi, S.; Petoussi, N.; Zankl, M.; Veit, R.; Jacob, P.; Drexler, G.

1991-01-01

Organ doses and effective dose equivalents for environmental gamma rays were calculated using human phantoms and Monte Carlo methods accounting rigorously the environmental gamma ray fields. It was suggested that body weight is the dominant factor to determine organ doses. The weight function expressing organ doses was introduced. Using this function, the variation in organ doses due to several physical factors were investigated. A detector having gamma-ray response similar to that of human bodies has been developed using a NaI(Tl) scintillator. (author)

Survey of environmental radiation dose rates in Tokushima prefecture

International Nuclear Information System (INIS)

Sakama, Minoru; Imura, Hiroyoshi; Akou, Natsuki; Takeuchi, Emi; Morihiro, Yukinori

2004-01-01

Survey of environmental radiation dose rates in Tokushima prefecture has been carried out using a portable NaI (Tl) scintillation survey meter and a CsI(Tl) pocket type one. To our knowledge, previous several surveys in Tokushima, for example by Abe et al. (1982) and Yoshino et al. (1991), have remained to report the environmental radiation dose rates merely about the major cities, that is Tokushima City and others along the Pacific. Up to now, there have been few efforts to survey the environmental radiation dose rates about mountain valleys in Tokushima. In this work, it is remarkable that we have for the first time made surveys of environmental radiation dose rates on the 6 routes across the Sanuki mountains and inside the pier of Onaruto Bridge, 'Naruto Uzu-no-michi', in the northern area of Tokushima. In the course of present surveys, the maximum value of the environmental radiation dose rates was 0.117±0.020 μGy/h at Higetouge in Sanuki City, and then it was found that the radiation dose rates across the Sanuki mountains tend to increase slightly with approaching Kagawa area from Tokushima one. Considering geological formation around the northern side of Sanuki mountains, there are mainly geological layers of granodiorite containing in the substantial amount of naturally occurring radionuclides, 40 K, U-series, and Th-series, than other geological rocks and it was found that the terrestrial gamma-rays have effect on the environmental radiation dose rates according to the geological formation. (author)

A comparison of dose versus risk at environmental restoration sites

International Nuclear Information System (INIS)

Holm-Hansen, T.; Pastor, R.S.

1996-01-01

This paper compares current US Environmental Protection Agency methods for completing risk assessments at radionuclide-contaminated sites with the International Council for Radiation Protection dose-based method. The two methods produce inconsistent results that could complicate cleanup decisions. Important issues include uncertainties associated with the use of carcinogenic slope factors and methods to account for institutional controls and decay of the source term for decision-making purposes. Overall, risk management at sites contaminated with radionuclides should be driven by a dose-based approach through adoption of the proposed 15 millirem cleanup standard found in Title 40 Code of Federal Regulations, Part 191

Dose assessment activities in the Republic of the Marshall Islands.

Science.gov (United States)

Simon, S L; Graham, J C

1996-10-01

Dose assessments, both retrospective and prospective, comprise one important function of a radiological study commissioned by the Republic of the Marshall Islands (RMI) government in late 1989. Estimating past or future exposure requires the synthesis of information from historical data, results from a recently completed field monitoring program, laboratory measurements, and some experimental studies. Most of the activities in the RMI to date have emphasized a pragmatic rather than theoretical approach. In particular, most of the recent effort has been expended on conducting an independent radiological monitoring program to determine the degree of deposition and the geographical extent of weapons test fallout over the nation. Contamination levels on 70% of the land mass of the Marshall Islands were unknown prior to 1994. The environmental radioactivity data play an integral role in both retrospective and prospective assessments. One recent use of dose assessment has been to interpret environmental measurements of radioactivity into annual doses that might be expected at every atoll. A second use for dose assessment has been to determine compliance with a dose action level for the rehabilitation of Rongelap Island. Careful examination of exposure pathways relevant to the island lifestyle has been necessary to accommodate these purposes. Examples of specific issues studied include defining traditional island diets as well as current day variations, sources of drinking water, uses of tropical plants including those consumed for food and for medicinal purposes, the nature and microvariability of plutonium particles in the soil and unusual pathways of exposure, e.g., that which might be associated with cooking and washing outdoors and inadvertent soil ingestion. A study on the prevalence of thyroid disease is also being conducted and the geographic pattern of disease may be useful as a bioindicator of the geographic pattern of exposure to radioiodine. Finally, an

Dose-response relationships for environmentally mediated infectious disease transmission models.

Directory of Open Access Journals (Sweden)

Andrew F Brouwer

2017-04-01

Full Text Available Environmentally mediated infectious disease transmission models provide a mechanistic approach to examining environmental interventions for outbreaks, such as water treatment or surface decontamination. The shift from the classical SIR framework to one incorporating the environment requires codifying the relationship between exposure to environmental pathogens and infection, i.e. the dose-response relationship. Much of the work characterizing the functional forms of dose-response relationships has used statistical fit to experimental data. However, there has been little research examining the consequences of the choice of functional form in the context of transmission dynamics. To this end, we identify four properties of dose-response functions that should be considered when selecting a functional form: low-dose linearity, scalability, concavity, and whether it is a single-hit model. We find that i middle- and high-dose data do not constrain the low-dose response, and different dose-response forms that are equally plausible given the data can lead to significant differences in simulated outbreak dynamics; ii the choice of how to aggregate continuous exposure into discrete doses can impact the modeled force of infection; iii low-dose linear, concave functions allow the basic reproduction number to control global dynamics; and iv identifiability analysis offers a way to manage multiple sources of uncertainty and leverage environmental monitoring to make inference about infectivity. By applying an environmentally mediated infectious disease model to the 1993 Milwaukee Cryptosporidium outbreak, we demonstrate that environmental monitoring allows for inference regarding the infectivity of the pathogen and thus improves our ability to identify outbreak characteristics such as pathogen strain.

Radiological dose assessment from the operation of Daeduk nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

Hwang, Won Tae; Kim, Eun Han; Suh, Kyung Suk; Choi, Young Gil [Korea Atomic Energy Research Institute, Taejon (Korea)

2000-02-01

The objective of this project is to assure the public acceptance for nuclear facilities, and the environmental safety from the operation of Daeduk nuclear facilities, such as HANARO research reactor, nuclear fuel processing facilities and others. For identifying the integrity of their facilities, the maximum individual doses at the site boundary and on the areas with high population density were assessed. Also, the collective doses within radius 80 km from the site were assessed. The radiation impacts for residents around the site from the operation of Daeduk nuclear facilities in 1999 were neglectable. 8 refs., 10 figs., 27 tabs. (Author)

Discussion on the method of environmental radiological impact assessment for the highway construction project

International Nuclear Information System (INIS)

Qiu Guohua

2008-01-01

Based on the characteristics and environmental radiological impact of the highway construction project, the basic procedure of environmental radiological impact assessment for the highway construction project is put forward, including analysis and determination of contamination sources, selection of evaluation factors, determination of assessment range and dose limit, environmental investigation, environmental impact prediction and assessment. The working method of each procedure is analyzed. (authors)

Researches and Applications of ESR Dosimetry for Radiation Accident Dose Assessment

International Nuclear Information System (INIS)

Wu, K.; Guo, L.; Cong, J.B.; Sun, C.P.; Hu, J.M.; Zhou, Z.S.; Wang, S.; Zhang, Y.; Zhang, X.; Shi, Y.M.

1998-01-01

The aim of this work was to establish methods suitable for practical dose assessment of people involved in ionising radiation accidents. Some biological materials of the human body and materials possibly carried or worn by people were taken as detection samples. By using electron spin resonance (ESR) techniques, the basic dosimetric properties of selected materials were investigated in the range above the threshold dose of human acute haemopoietic radiation syndrome. The dosimetric properties involved included dose response properties of ESR signals, signal stabilities, distribution of background signals, the lowest detectable dose value, radiation conditions, environmental effects on the detecting process, etc. Several practical dose analytical indexes and detecting methods were set up. Some of them (bone, watch glass and tooth enamel) had also been successfully used in the dose assessment of people involved in three radiation accidents, including the Chernobyl reactor accident. This work further proves the important role of ESR techniques in radiation accident dose estimation. (author)

Hanford environmental dose reconstruction project - an overview

International Nuclear Information System (INIS)

Shipler, D.B.; Napier, B.A.; Farris, W.T.

1996-01-01

The Hanford Environmental Dose Reconstruction Project was initiated because of public interest in the historical releases of radioactive materials from the Hanford Site, located in southcentral Washington State. By 1986, over 38,000 pages of environmental monitoring documentation from the early years of Hanford operations had been released. Special committees reviewing the documents recommended initiation of the Hanford Environmental Dose Reconstruction Project, which began in October 1987, and is conducted by Battelle, Pacific Northwest Laboratories. The technical approach taken was to reconstruct releases of radioactive materials based on facility operating information; develop and/or adapt transport, pathway, and dose models and computer codes; reconstruct environmental, meterological, and hydrological monitoring information; reconstruct demographic, agricultural, and lifestyle characteristics; apply statistical methods to all forms of uncertainty in the information, parameters, and models; and perform scientific investigation that were technically defensible. The geographic area for the study includes ∼2 x 10 5 km 2 (75,000 mi 2 ) in eastern Washington, western Idaho, and northeastern Oregon (essentially the Mid-columbia Basin of the Pacific Northwest). Three exposure pathways were considered: the atmosphere, the Columbia River, and ground water

Procedures for operational monitoring of the environmental equivalent doses in cobalt therapy

International Nuclear Information System (INIS)

Perez Velasquez, Reytel; Gonzalez Lopez, Nadia; Perez Tamayo, Luis

2009-01-01

It took as its object of study environmental equivalent dose rates of field radiation they face radiophysicists technicians and medical physicists in the irradiation site of the radiation department of Lenin Hospital in Holguin, and the public that travels or remains in premises and areas surrounding the campus. It A review of national and international publications as well as technical documents to study the state of the art of the methodological existing monitoring of those dose rates and the valuation of impact in the context of an environmental management system. Since no detailed instructions and to perform the above-mentioned monitoring was proposed structure should contain a procedure to regulate the steps for this monitoring in the radiotherapy department of the Lenin Hospital Holguin, for which we studied the guidelines of NC ISO 14000 , and was conducted wide experiment whose led to: illustrate the level of doses required workers exposed occupationally exposed to radiation and the public compare these levels with natural radiation sources, assess the effectiveness of shielding the site of irradiation and the points of greatest risk within and outside the enclosure irradiation.Also assessed the impact it can have on the health of people exposed to such doses. Finally, we proposed a procedure for conducting subsequent monitoring and made recommendations to reduce levels radiation determined the lowest level reasonably achievable. (author)

AGING FACILITY WORKER DOSE ASSESSMENT

International Nuclear Information System (INIS)

R.L. Thacker

2005-01-01

The purpose of this calculation is to estimate radiation doses received by personnel working in the Aging Facility performing operations to transfer aging casks to the aging pads for thermal and logistical management, stage empty aging casks, and retrieve aging casks from the aging pads for further processing in other site facilities. Doses received by workers due to aging cask surveillance and maintenance operations are also included. The specific scope of work contained in this calculation covers both collective doses and individual worker group doses on an annual basis, and includes the contributions due to external and internal radiation from normal operation. There are no Category 1 event sequences associated with the Aging Facility (BSC 2004 [DIRS 167268], Section 7.2.1). The results of this calculation will be used to support the design of the Aging Facility and to provide occupational dose estimates for the License Application. The calculations contained in this document were developed by Environmental and Nuclear Engineering of the Design and Engineering Organization and are intended solely for the use of the Design and Engineering Organization in its work regarding facility operation. Yucca Mountain Project personnel from the Environmental and Nuclear Engineering should be consulted before use of the calculations for purposes other than those stated herein or use by individuals other than authorized personnel in Environmental and Nuclear Engineering

Enjebi Island dose assessment

International Nuclear Information System (INIS)

Robison, W.L.; Conrado, C.L.; Phillips, W.A.

1987-07-01

We have updeated the radiological dose assessment for Enjebi Island at Enewetak Atoll using data derived from analysis of food crops grown on Enjebi. This is a much more precise assessment of potential doses to people resettling Enjebi Island than the 1980 assessment in which there were no data available from food crops on Enjebi. Details of the methods and data used to evaluate each exposure pathway are presented. The terrestrial food chain is the most significant potential exposure pathway and 137 Cs is the radionuclide responsible for most of the estimated dose over the next 50 y. The doses are calculated assuming a resettlement date of 1990. The average wholebody maximum annual estimated dose equivalent derived using our diet model is 166 mremy;the effective dose equivalent is 169 mremy. The estimated 30-, 50-, and 70-y integral whole-body dose equivalents are 3.5 rem, 5.1 rem, and 6.2 rem, respectively. Bone-marrow dose equivalents are only slightly higher than the whole-body estimates in each case. The bone-surface cells (endosteal cells) receive the highest dose, but they are a less sensitive cell population and are less sensitive to fatal cancer induction than whole body and bone marrow. The effective dose equivalents for 30, 50, and 70 y are 3.6 rem, 5.3 rem, and 6.6 rem, respectively. 79 refs., 17 figs., 24 tabs

Overview of the Hanford Environmental Dose Reconstruction Project

International Nuclear Information System (INIS)

Shipler, D.B.; Napier, B.A.; Ikenberry, T.A.

1992-04-01

The objective of the Hanford Environmental Dose Reconstruction (HEDR) Project is to estimate the radiation doses that specific and representative individuals and populations may have received as a result of releases of radioactive materials from historical operations at the Hanford Site. These dose estimates would account for the uncertainties of information regarding facilities operations, environmental monitoring, demography, food consumption and lifestyles, and the variability of natural phenomena. Other objectives of the HEDR Project include: supporting the Hanford Thyroid Disease Study (HTDS), declassifying Hanford-generated information and making it available to the public, performing high-quality, credible science, and conducting the project in an open, public forum. The project is briefly described

Evaluation and distribution of doses received by Cuban population due to environmental sources of radioactivity

International Nuclear Information System (INIS)

Zerquera, Juan T.; Prendes Alonso, Miguel; Fernandez Gomez, Isis M.; Lopez Bejerano, Gladys

2008-01-01

Full text: In the frame of a national research project supported by the Nuclear Energy Agency of the Ministry of Science, Technology and Environment of the Republic of Cuba doses received by Cuban population due to the exposure to existing in the environment sources of radiation were assessed. Direct measurements of sources representing 90% of average total doses to world population according to UNSCEAR data were made and estimations of doses were obtained for the different components of the total dose: doses due to the exposure to cosmic radiation, external terrestrial radiation, potassium contained in human body and inhalation and ingestion of radionuclides present in the environment. Using the obtained results it was made an estimation of total doses to Cuban population due to environmental radiation sources and the contributions of different dose components were assessed. This was carried out through a Monte Carlo simulation of the total doses using the parameter of dose distributions obtained for the different contributors (components) to total dose. On the basis of the estimations the average total effective dose to Cuban population due to the exposure to environmental sources was estimated as 1.1 ± 0.3 mSv per year. This low dose value is in the range of doses estimated by UNSCEAR for world population due to natural background and can be explained by the specific of Cuban environment: a majority of the population living at the sea level or at low altitudes, relative low content of primordial radionuclides in soils and high ventilation rates in dwellings. All the instructions specified in the Call for Abstracts should be taken into account. e/ 41 and 457. (author)

Environmental carcinogenic agents and cancer prevention. Risk assessment and management

International Nuclear Information System (INIS)

Tsugane, Shoichiro

2013-01-01

Many agents in our environment have been established as being carcinogenic, and in most cases, the carcinogenic properties of these agents were identified because of high-dose occupational or accidental exposure. Risk characterization, taking into account the dose-response relationship, and exposure assessment are essential for risk assessment and subsequent cancer prevention. Based on scientific risk assessment, risk management should be conducted practically by considering the economic, social, political, and other technical issues and by balancing the risks and benefits. Asbestos and environmental tobacco smoke are typical examples of established carcinogenic agents in the general environment, contributing to low-dose exposure. Further epidemiological studies are required to investigate the carcinogenicity of low-dose exposure to known carcinogenic agents such as arsenic and cadmium through dietary intake, radiation via medical and natural exposure, and air pollution due to diesel exhaust. In contrast, occupational chemical exposure to 1,2-dichloropropane and/or dichloromethane, whose carcinogenicity had not been established, was suggested to cause cholangiocarcinoma among workers involved in offset color proof-printing only after a rare situation of high-dose exposure was unveiled. Continuous monitoring of unusual cancer occurrences in target populations such as workers in occupational and regional settings as well as exposure reduction to suspected carcinogenic agents to levels as low as reasonably achievable is essential for reducing the risk of cancer due to environmental carcinogens. (author)

Real-time assessment of exposure dose to workers in radiological environments during decommissioning of nuclear facilities

International Nuclear Information System (INIS)

Jeong, KwanSeong; Choi, ByungSeon; Moon, JeiKwon; Hyun, Dongjun; Lee, Jonghwan; Kim, IkJune; Kim, GeunHo; Seo, JaeSeok; Jeong, SeongYoung; Lee, JungJun; Song, HaeSang; Lee, SangWha; Son, BongKi

2014-01-01

Highlights: • The method of exposure dose assessment to workers during decommissioning of nuclear facilities. • The environments of simulation were designed under a virtual reality. • To assess exposure dose to workers, human model was developed within a virtual reality. - Abstract: This objective of this paper is to develop a method to simulate and assess the exposure dose to workers during decommissioning of nuclear facilities. To simulate several scenarios, decommissioning environments were designed using virtual reality. To assess exposure dose to workers, a human model was also developed using virtual reality. The exposure dose was measured and assessed under the principle of ALARA in accordance with radiological environmental change. This method will make it possible to plan for the exposure dose to workers during decommissioning of nuclear facilities

Significance of BETA and GAMMA dose on environmental qualification of components

International Nuclear Information System (INIS)

Aydogdu, K.M.; Tsang, K.T.

1999-01-01

Safety-related systems and components that are required to perform safety functions during accident conditions must be designed to withstand the harsh environmental conditions that occur as a consequence of the accident. Where these conditions are 'harsh', and equipment operability can potentially be affected by the post-accident environment environmental qualification of the equipment must be conducted to demonstrate that the required safety function can be maintained. It is also understood that non-safety related equipment that affects, or prevents, the satisfactory operation of a safety-related system should also withstand the 'harsh' environmental conditions caused by an appropriate design-basis accident. There are essentially two types of requirements that must be satisfied to qualify equipment or components to withstand radiation damage, namely economic requirements and safety requirements. The general objective of the economic requirement is to reduce maintenance cost and to maximize component life during reactor operation. The general objective of the safety requirement is that the equipment should be qualified to withstand the harsh post-accident environmental conditions and should function properly for the appropriate length of time after a design-basis accident has occurred. To address the economic factors - i.e., to reduce maintenance costs and to maximize component life - the radiation dose rates to equipment are calculated throughout the reactor building and the service building during reactor operation. These are also used for the safety requirement purpose, to assess radiation ageing of safety-related components caused by degradation of material properties with time at radiation exposure. To address the safety requirement, the dose-rate estimates and accumulated doses after a LOCA coincident with loss-of-emergency-core cooling (LOECC) are provided. The harsh post-accident environmental conditions defined for environmental qualification of components

Radioactive environmental impact assessment for a production project of titanium dioxide by chlorination process

International Nuclear Information System (INIS)

Qiu Guohua

2010-01-01

Based on the analysis of shifting direction of radionuclide in production process and the environmental investigation and monitoring, the radioactive environmental impact from a production project of titanium dioxide by chlorination process has been analyzed and assessed. The result of radioactive environmental investigation shows that values of assessment factors are in the range of environmental radioactive background. The radioactive environmental sensitive spot has been delineated. The results of radioactive environmental prediction show that the additional doses to workers and residents are 0.59 mSv/a and 9.28 × 10-4 mSv/a respectively which are less than the annual dose limits of administration. The radioactive environmental impact of the production project of the titanium dioxide by chlorination process will meet the needs of national regulations and standards if radiation protection and environmental protection measures are implemented and radioactive environmental monitoring are strengthened. (author)

Environmental Change in Post-closure Safety Assessment of Solid Radioactive Waste Repositories. Report of Working Group 3 Reference Models for Waste Disposal of EMRAS II Topical Heading Reference Approaches for Human Dose Assessment. Environmental Modelling for Radiation Safety (EMRAS II) Programme

International Nuclear Information System (INIS)

2016-08-01

Environmental assessment models are used for evaluating the radiological impact of actual and potential releases of radionuclides to the environment. They are essential tools for use in the regulatory control of routine discharges to the environment and also in planning measures to be taken in the event of accidental releases. They are also used for predicting the impact of releases which may occur far into the future, for example, from underground radioactive waste repositories. It is important to verify, to the extent possible, the reliability of the predictions of such models by a comparison with measured values in the environment or with predictions of other models. The IAEA has been organizing programmes of international model testing since the 1980s. These programmes have contributed to a general improvement in models, in the transfer of data and in the capabilities of modellers in Member States. IAEA publications on this subject over the past three decades demonstrate the comprehensive nature of the programmes and record the associated advances which have been made. From 2009 to 2011, the IAEA organized a programme entitled Environmental Modelling for Radiation Safety (EMRAS II), which concentrated on the improvement of environmental transfer models and the development of reference approaches to estimate the radiological impacts on humans, as well as on flora and fauna, arising from radionuclides in the environment. Different aspects were addressed by nine working groups covering three themes: reference approaches for human dose assessment, reference approaches for biota dose assessment and approaches for assessing emergency situations. This publication describes the work of the Reference Models for Waste Disposal Working Group

Review of Cl-36 behaviour in the biosphere and implications for long-term dose assessment

International Nuclear Information System (INIS)

Leclerc, E.; Smith, G.; Lloyd, P.

2009-01-01

Cl-36 is an important contributor to potential radiation doses in the long term, arising from release into the biosphere from radioactive waste disposal facilities. Its special attributes include its long half-life, high mobility in many environmental conditions, and potentially high uptake into plants and hence accumulation in the food-chain. Review has shown very wide ranges of Cl-36 values of parameters commonly employed in models used for long term doses. Accordingly, a workshop was held recently within the aegis of the international collaboration project BIOPROTA, to consider the causes of such variation, and in particular: to provide an open forum for presentation and discussion of environmental processes involved in Cl-36 migration and accumulation, and on how to model them, and to develop recommendations for the direction of continuing research as input to long-term radiological assessment. Participation in the workshop included specialists and contributions from North America, Europe and Japan in environmental behaviour of chlorine, radioecology of Cl-36 and long term dose assessment. This paper will present the output from that workshop in the context of the wider aspects of performance assessment, taking into account information about: waste types for which Cl-36 is a significant component of the total Cl-36 inventory; data requirements for the dose assessment models, notably concerning uptake from soils into food crops which may lead to higher doses than direct consumption of contaminated drinking water; critical data weaknesses which may lead to overly pessimistic dose estimates; time dependent factors within a single growing season which can affect final concentrations in food crops for animals and humans; alternative conceptual models for the behaviour of Cl-36 in the environment, notably models structured as other trace radionuclide dose assessment models as opposed to models which are based specifically on chlorine behaviour which should take

Occupational dose assessment and national dose registry system in Iran

International Nuclear Information System (INIS)

Jafari-Zadeh, M.; Nazeri, F.; Hosseini-Pooya, S. M.; Taheri, M.; Gheshlaghi, F.; Kardan, M. R.; Babakhani, A.; Rastkhah, N.; Yousefi-Nejad, F.; Darabi, M.; Oruji, T.; Gholamali-Zadeh, Z.; Karimi-Diba, J.; Kazemi-Movahed, A. A.; Dashti-Pour, M. R.; Enferadi, A.; Jahanbakhshian, M. H.; Sadegh-Khani, M. R.

2011-01-01

This report presents status of external and internal dose assessment of workers and introducing the structure of National Dose Registry System of Iran (NDRSI). As well as types of individual dosemeters in use, techniques for internal dose assessment are presented. Results obtained from the International Atomic Energy Agency intercomparison programme on measurement of personal dose equivalent H p (10) and consistency of the measured doses with the delivered doses are shown. Also, implementation of dosimetry standards, establishment of quality management system, authorisation and approval procedure of dosimetry service providers are discussed. (authors)

Phase 1 of the Hanford Environmental Dose Reconstruction Project

International Nuclear Information System (INIS)

1991-08-01

The work described in this report was prompted by the public's concern about potential effect from the radioactive materials released from the Hanford Site. The Hanford Environmental Dose Reconstruction (HEDR) Project was established to estimate radiation dose the public might have received from the Hanford Site since 1944, when facilities began operating. Phase 1 of the HEDR Project is a ''pilot'' or ''demonstration'' phase. The objectives of this initial phase were to determine whether enough historical information could be found or reconstructed to be used for dose estimation and develop and test conceptual and computational models for calculating credible dose estimates. Preliminary estimates of radiation doses were produced in Phase 1 because they are needed to achieve these objectives. The reader is cautioned that the dose estimates provided in this and other Phase 1 HEDR reports are preliminary. As the HEDR Project continues, the dose estimates will change for at least three reasons: more complete input information for models will be developed; the models themselves will be refined; and the size and shape of the geographic study area will change. This is one of three draft reports that summarize the first phase of the four-phased HEDR Project. This, the Summary Report, is directed to readers who want a general understanding of the Phase 1 work and preliminary dose estimates. The two other reports -- the Air Pathway Report and the Columbia River Pathway Report -- are for readers who understand the radiation dose assessment process and want to see more technical detail. Detailed descriptions of the dose reconstruction process are available in more than 20 supporting reports listed in Appendix A. 32 refs., 46 figs

ANDROS: A code for Assessment of Nuclide Doses and Risks with Option Selection

International Nuclear Information System (INIS)

Begovich, C.L.; Sjoreen, A.L.; Ohr, S.Y.; Chester, R.O.

1986-11-01

ANDROS (Assessment of Nuclide Doses and Risks with Option Selection) is a computer code written to compute doses and health effects from atmospheric releases of radionuclides. ANDROS has been designed as an integral part of the CRRIS (Computerized Radiological Risk Investigation System). ANDROS reads air concentrations and environmental concentrations of radionuclides to produce tables of specified doses and health effects to selected organs via selected pathways (e.g., ingestion or air immersion). The calculation may be done for an individual at a specific location or for the population of the whole assessment grid. The user may request tables of specific effects for every assessment grid location. Along with the radionuclide concentrations, the code requires radionuclide decay data, dose and risk factors, and location-specific data, all of which are available within the CRRIS. This document is a user manual for ANDROS and presents the methodology used in this code

Developing RESRAD-BASELINE for environmental baseline risk assessment

International Nuclear Information System (INIS)

Cheng, Jing-Jy.

1995-01-01

RESRAD-BASELINE is a computer code developed at Argonne developed at Argonne National Laboratory for the US Department of Energy (DOE) to perform both radiological and chemical risk assessments. The code implements the baseline risk assessment guidance of the US Environmental Protection Agency (EPA 1989). The computer code calculates (1) radiation doses and cancer risks from exposure to radioactive materials, and (2) hazard indexes and cancer risks from exposure to noncarcinogenic and carcinogenic chemicals, respectively. The user can enter measured or predicted environmental media concentrations from the graphic interface and can simulate different exposure scenarios by selecting the appropriate pathways and modifying the exposure parameters. The database used by PESRAD-BASELINE includes dose conversion factors and slope factors for radionuclides and toxicity information and properties for chemicals. The user can modify the database for use in the calculation. Sensitivity analysis can be performed while running the computer code to examine the influence of the input parameters. Use of RESRAD-BASELINE for risk analysis is easy, fast, and cost-saving. Furthermore, it ensures in consistency in methodology for both radiological and chemical risk analyses

Concepts, methods and models to assess environmental impact

International Nuclear Information System (INIS)

Pentreath, R.J.

2002-01-01

The environmental impact of chemicals generally in the environment is a subject that has been approached in recent years in ways that are different in concept and practice. They range from chemical 'toxicity' and 'residual' risk assessments based on individuals, to broader based, ecological risk assessments. At the same time, approaches to considering what in the environment should be protected, and how, has also changed. Approaches to this subject vary from strict conservation of identified species and areas, to the more general concepts of wishing to maintain the biological diversity within and amongst all species and habitats, and of protecting large habitat areas against irreversible human damage. Against this background, approaches to the issue of the possible impact of radionuclides in the environment over the last decade or so have centred around the various statements made by the ICRP; either attempting to support them, or seeking to compensate for their perceived deficiencies. There have been arguments that, because man is an integral part of 'the environment', and is afforded such a high level of protection, then all other components of it would be axiomatically protected. There have also been calculations to demonstrate that, in hypothetical situations, if radionuclide concentrations in the environment were such that the 1 mSv a -1 dose limit to man was not exceeded, then the concentrations of radionuclides in the animals and plants in their food chain would therefore receive dose-rates less than those likely to cause them 'harm' at the population level. Some countries have been more direct. In the USA, dose 'standards' for the protection of populations of all aquatic animals have been introduced, and consideration is being given to the introduction of dose 'standards' for populations of all terrestrial plants and animals. The introduction of a set of 'no effects' dose-rate screening reference levels for different types of fauna, to be applied to

Integrated technique for assessing environmental dose of radioactive waste storage installation

Energy Technology Data Exchange (ETDEWEB)

Bor-Jing Chang; Chien-Liang Shih; Ing-Jane Chen [Institute of Nuclear Energy Research, Lungtan, Taiwan (China); Ren-Dih Sheu; Shiang-Huei Jiang [National Tsing Hua University, Hsinchu, Taiwan (China); Shu-Jun Chang [Nuclear Science and Technology Association, Taiwan (China); Ruei-Ying Liao; Pei Yu; Chin-Yi Huang [Taiwan Power Company, Taipei, Taiwan (China)

2000-05-01

The ability to accurately predict exposure rates at large distances from a gamma radiation source is becoming increasingly important. This is because that the related regulation for the control of radiation levels in and around nuclear facilities becomes more stringent. Since the continuous increase of the radwaste storage capacity requirement on site, the requirement of a more realistic evaluation is very necessary. Those doses are usually at past time evaluated by QADCG/INER-2 code for direct dose and by SKYSHINE-III code for skyshine dose in which evaluation were over conservatively considered. This study is to update the evaluation code package accompanied with adequate methodology and to establish integrated analysis procedure. Thereafter, radiation doses can be accurately calculated in a reasonably conservative way. The purpose of the investigation is divided into three categories. First, SPECTRUM-506 is used instead of SPECTUM. Nuclide databases are enlarged from 100 up to 506. And the operation is ported to personal computer. Secondly, the QADCG/INER-3 code is developed to enhance the original QADCG/INER-2 code. The most important difference is the use of the geometric progression (GP) fitting function for the gamma-ray buildup factor. SKYSHINE-III code is replaced by McSKY and SKYDOSE codes. They are well benchmarked by using the Monte Carlo code MCNP and sensitive parameters are detailed investigated. Thirdly, the well developed analysis procedure is applicable for nuclear utility radwaste storage sites. Finally, the case studies were performed by using those packages to assess the radiological impact of utility radwaste storage site. The results are verified in detail by using Monte Carlo code MCNP and the results seems pretty consistent from both method. (author)

Population dose assessment: characteristics of PC CREAM

International Nuclear Information System (INIS)

Alonso, Maria T.; Curti, Adriana R.

2000-01-01

This paper presents the main features of the PC CREAM, a program for performing radiological impact assessments due to radioactive discharges into the environment during the operation of radioactive and nuclear facilities. PC CREAM is a suite of six programs that can be used to estimate individual and collective radiation doses. The methodology of PC CREAM is based on updated environmental and dosimetric models, including ICRP 60 recommendations. The models include several exposure pathways and the input files are easy to access. The ergonomics of the program improves the user interaction and makes easier the input of local data. This program is useful for performing sensitivity analysis, siting studies and validation of model comparing the activity concentration output data with environmental monitoring data. The methodology of each module is described as well as the output data. (author)

Development of a site specific environmental radiation assessment model for Youngkwang NPPs

Energy Technology Data Exchange (ETDEWEB)

Chung, Yang Geun; Song, Myung Jae; Shon, Soon Hwan; Shin, Sang Woon; Lee, Gap Bock; Yang, Kyung Hwa [Korea Electric Power Research Institute, Taejon (Korea, Republic of); Kim, Seong Pyung; Kim, Jeong Kyu; Shin, Dae Yoon; Kim, Hyun Ku; Lee, Kyung Jin [Chosun University, Kwangju (Korea, Republic of)

1996-12-31

During the normal operation of nuclear power plants, a very small amount of radionuclide materials is released to the environment. The radionuclide releases to the environment may give rise to some additional radiation dose through a number of pathways. With a few exception, radionuclide transports are highly dependent on the environmental conditions such as topological features, atmospheric and oceanic conditions and socio-environmental characteristics, etc. The dose calculation in Korea are presently being performed using the models in US NRC Reg. Guide. However, these models which were originally released by the US NRC in 1977 are inadequate to deal with environmental movement of radionuclides in consideration of complex terrain, tidal condition of the Yellow Sea, and Youngkwang site specific conditions. KEPRI has developed the models to consider the site specific characteristics around Youngkwang NPPs, to give the realistic dose assessment, and to improve assurance and reliability in public dose calculation. (author). 41 figs., 70 refs.

Ecological aspects of environmental assessment of contaminated areas

International Nuclear Information System (INIS)

Templeton, W.L.

1990-04-01

When large landscapes are contaminated by radionuclides released from nuclear activities, physical processes, such as atmospheric and hydrological transport may move the radioactive materials over large distances resulting in direct external exposure of man and organisms. This paper provides an overview of the modeling of radionuclide movement through defined ecological pathways, describes some ecological problems at remediated sites, and briefly reviews effects of environmental radiation on terrestrial and aquatic biota. This paper describes pathways that should be considered when conducting environmental dose assessments for radionuclides released to the environment. 4 refs

Statistical analysis of environmental dose data for Trombay environment

International Nuclear Information System (INIS)

Kale, M.S.; Padmanabhan, N.; Rekha Kutty, R.; Sharma, D.N.; Iyengar, T.S.; Iyer, M.R.

1993-01-01

The microprocessor based environmental dose logging system is functioning at six stations at Trombay for the past couple of years. The site emergency control centre (SECC) at modular laboratory receives telemetered data every five minutes from main guard house (South Site), Bhabha point (top of the hill), Cirus reactor, Mod Lab terrace, Hall No. 7 and Training School Hostel. The data collected are being stored in dbase III + format for easy processing in a PC. Various statistical parameters and distributions of environmental gamma dose are determined from the hourly dose data. On the basis of the reactor operation status an attempt has been made to separate the natural background and the gamma dose contribution due to the operating research reactors in each one of these monitoring stations. Similar investigations are being carried out for Tarapur environment. (author). 2 refs., 3 tabs., 2 figs

Assessing radiological impacts (exposures and doses) associated with the mining and milling of radioactive ores

International Nuclear Information System (INIS)

Williams, G.A.

1990-01-01

The basic units and concepts applicable to radiological assessment are presented. Data relevant to the assessment of radiological exposures from the mining and milling phases of uranium and thorium ores are discussed. As a guide to the assessment of environmental exposures to members of the public, concepts such as the critical group are defined. Environmental transport and exposure pathways are presented in general terms, together with a discussion of the use of mathematical models. The dose assessment procedures defined in the 1987 Code of Practice are described. 13 refs., 2 tabs., 1 fig

ENVIRONMENTAL ASSESSMENT METHODOLOGY FOR THE NUCLEAR FUEL CYCLE

Energy Technology Data Exchange (ETDEWEB)

Brenchley, D. L.; Soldat, J. K.; McNeese, J. A.; Watson, E. C.

1977-07-01

This report describes the methodology for determining where environmental control technology is required for the nuclear fuel cycle. The methodology addresses routine emission of chemical and radioactive effluents, and applies to mining, milling, conversion, enrichment, fuel fabrication, reactors (LWR and BWR) and fuel reprocessing. Chemical and radioactive effluents are evaluated independently. Radioactive effluents are evaluated on the basis of maximum exposed individual dose and population dose calculations for a 1-year emission period and a 50-year commitment. Sources of radionuclides for each facility are then listed according to their relative contribution to the total calculated dose. Effluent, ambient and toxicology standards are used to evaluate the effect of chemical effluents. First, each chemical and source configuration is determined. Sources are tagged if they exceed existirrg standards. The combined effect of all chemicals is assessed for each facility. If the additive effects are unacceptable, then additional control technology is recommended. Finally, sources and their chemicals at each facility are ranked according to their relative contribution to the ambient pollution level. This ranking identifies those sources most in need of environmental control.

Source term assessment using inverse modeling of radiation dose measured with environmental radiation monitors located at different positions

International Nuclear Information System (INIS)

Srinivas, C.V.; Rakesh, P.T.; Baskaran, R.; Venkatraman, B.

2018-01-01

Source term is an important input for consequence analysis using Decision Support Systems (DSS) to project radiological impact in the event of nuclear emergencies. A source term model called 'ASTER' is incorporated in the Online Nuclear Emergency Response System (ONERS) operational at Kalpakkam site for decision making during nuclear emergencies. This computes release rates using inverse method by employing an atmospheric dispersion model and gamma dose rates measured by environmental radiation monitors (ERM) deployed around the nuclear plant. The estimates may depend on the distribution of ERMs around the release location. In this work, data from various gamma monitors located at different radii 0.75 km and 1.5 km is used to assess the accuracy in the source term estimation for stack releases of MAPS-PHWR at Kalpakkam

L-Reactor operation, Savannah River Plant: environmental assessment

International Nuclear Information System (INIS)

1982-08-01

The purpose of this document is to assess the significance of the effects on the human environment of the proposed resumption of L-reactor operation at the Savannah River Plant, scheduled for October 1983. The discussion is presented under the following section headings: need for resumption of L-Reactor operations and purpose of this environmental assessment; proposed action and alternative; affected environment (including, site location and description, land use, historic and archeological resources, socioeconomic and community characteristics, geology and seismology, hydrology, meteorology and climatology, ecology, and radiation environment); environmental consequences; summary of projected L-Reactor releases and impacts; and Federal and State permits and approval. The three appendices are entitled: radiation dose calculation methods and assumptions; floodplain/wetlands assessment - L-Reactor operations; and, conversion table. A list of references is included at the end of each chapter

Cosmic-ray contribution in measurement of environmental gamma-ray dose

International Nuclear Information System (INIS)

Nagaoka, Kazunori; Honda, Kouichirou; Miyano, Keiji

1996-01-01

Nowadays several kinds of dosimeters are being used for environmental gamma-ray monitoring. However the results measured by those instruments are not always in good agreement. It may be caused from the different characteristics of dosimeters. In particular the different responses of the instruments to cosmic-rays give significant influence on the results. Environmental radiation measurements at various altitudes on Mt. Fuji were carried out using a scintillation spectrometer with 3''φ spherical NaI(Tl), a pressurized ionization chamber (PIC), an air-equivalent ionization chamber (IC), thermoluminescence dosimeters (TLD), radiophotoluminescence glass dosimeters (RPLD) and NaI(Tl) scintillation survey meters so that the response characteristics of these instruments to cosmic-rays could be clarified. Cosmic-ray contributions for all instruments were correlated with counting rate over 3 MeV by the spectrometer. Each contribution can be estimated by measurement of the counting rate. Conversion factors (nGy/h/cpm) for IC, PIC, TLD, RPLD and NaI survey meters (TCS166 and TCS121C) were 0.33, 0.32, 0.25, 0.24, 0.06 and -0.01, respectively. Self-doses of these instruments were estimated by measurements at Nokogiriyama facilities of the Institute for Cosmic Ray Research, University of Tokyo. Self-doses for TLD and RPLD were approximately 6 nGy/h. The self dose effect should be taken into consideration in environmental dose measurements. These data are expected to be useful in estimating the cosmic-ray contribution and self-dose in the measurement of environmental gamma-ray dose. (author)

Advances in environmental radiation protection: re-thinking animal-environment interaction modelling for wildlife dose assessment

Energy Technology Data Exchange (ETDEWEB)

Wood, Michael D. [School of Environment and Life Sciences, University of Salford, Manchester, M4 4WT (United Kingdom); Beresford, Nicholas A. [School of Environment and Life Sciences, University of Salford, Manchester, M4 4WT (United Kingdom); Centre for Ecology and Hydrology, Bailrigg, Lancaster, LA1 4AP (United Kingdom); Bradshaw, Clare [Department of Ecology, Environment and Plant Sciences, Stockholm University, 10691 Stockholm (Sweden); Gashchak, Sergey [Chornobyl Centre for Nuclear Safety, Radioactive Waste and Radioecology, 07100 Slavutych (Ukraine); Hinton, Thomas G. [Institut de Radioprotection et de Surete Nucleaire (IRSN), Centre de Cadarache, 13115 Saint Paul-lez-Durance (France)

2014-07-01

Current wildlife dose assessment models adopt simplistic approaches to the representation of animal-environment interaction. The simplest approaches are to assume either that environmental media (e.g. soil, sediment or water) are uniformly contaminated or relating organism exposure to activity concentrations in media collected at the point of sampling of the animal. The external exposure of a reference organism is then estimated by defining the geometric relationship between the organism and the medium. For example, a reference organism within the soil would have a 4p exposure geometry and a reference organism on the soil would have a 2p exposure geometry. At best, the current modelling approaches recognise differences in media activity concentrations by calculating exposure for different areas of contamination and then estimating the fraction of time that an organism spends in each area. In other fields of pollution ecology, for example wildlife risk assessment for chemical pollution, more advanced approaches are being implemented to model animal-environment interaction and estimate exposure. These approaches include individual-based movement modelling and random walk modelling and a variety of software tools have been developed to facilitate the implementation of these models. Although there are more advanced animal-environment interaction modelling approaches that are available, it is questionable whether these should be adopted for use in environmental radiation protection. Would their adoption significantly reduce uncertainty within the assessment process and, if so, by how much? These questions are being addressed within the new TREE (TRansfer - Exposure - Effects) research programme funded by the United Kingdom Natural Environment Research Council (NERC) and within Working Group (WG) 8 of the International Atomic Energy Agency's MODARIA programme. MODARIA WG8 is reviewing some of the alternative approaches that have been developed for animal

Offsite radiation doses summarized from Hanford environmental monitoring reports for the years 1957-1984

International Nuclear Information System (INIS)

Soldat, J.K.; Price, K.R.; McCormack, W.D.

1986-02-01

Since 1957, evaluations of offsite impacts from each year of operation have been summarized in publicly available, annual environmental reports. These evaluations included estimates of potential radiation exposure to members of the public, either in terms of percentages of the then permissible limits or in terms of radiation dose. The estimated potential radiation doses to maximally exposed individuals from each year of Hanford operations are summarized in a series of tables and figures. The applicable standard for radiation dose to an individual for whom the maximum exposure was estimated is also shown. Although the estimates address potential radiation doses to the public from each year of operations at Hanford between 1957 and 1984, their sum will not produce an accurate estimate of doses accumulated over this time period. The estimates were the best evaluations available at the time to assess potential dose from the current year of operation as well as from any radionuclides still present in the environment from previous years of operation. There was a constant striving for improved evaluation of the potential radiation doses received by members of the public, and as a result the methods and assumptions used to estimate doses were periodically modified to add new pathways of exposure and to increase the accuracy of the dose calculations. Three conclusions were reached from this review: radiation doses reported for the years 1957 through 1984 for the maximum individual did not exceed the applicable dose standards; radiation doses reported over the past 27 years are not additive because of the changing and inconsistent methods used; and results from environmental monitoring and the associated dose calculations reported over the 27 years from 1957 through 1984 do not suggest a significant dose contribution from the buildup in the environment of radioactive materials associated with Hanford operations

Human health risk assessment (HHRA) for environmental development and transfer of antibiotic resistance

DEFF Research Database (Denmark)

Ashbolt, Nicholas J.; Amézquita, Alejandro; Backhaus, Thomas

2013-01-01

to enable human health risk assessments (HHRA) that focus on the role of the environment in the failure of antibiotic treatment caused by antibiotic-resistant pathogens. Methods: The authors participated in a workshop held 4-8 March 2012 in Québec, Canada, to define the scope and objectives...... of an environmental assessment of antibiotic-resistance risks to human health. We focused on key elements of environmental-resistance-development "hot spots," exposure assessment (unrelated to food), and dose response to characterize risks that may improve antibiotic-resistance management options. Discussion: Various...... novel aspects to traditional risk assessments were identified to enable an assessment of environmental antibiotic resistance. These include a) accounting for an added selective pressure on the environmental resistome that, over time, allows for development of antibiotic-resistant bacteria (ARB); b...

Consultative exercise on dose assessments.

Science.gov (United States)

Bridges, B A; Parker, T; Simmonds, J R; Sumner, D

2001-06-01

A summary is given of a meeting held at Sussex University, UK, in October 2000, which allowed the exchange of ideas on methods of assessment of dose to the public arising from potential authorised radioactive discharges from nuclear sites in the UK. Representatives of groups with an interest in dose assessments were invited, and hence the meeting was called the Consultative Exercise on Dose Assessments (CEDA). Although initiated and funded by the Food Standards Agency, its organisation, and the writing of the report, were overseen by an independent Chairman and Steering Group. The report contains recommendations for improvement in co-ordination between different agencies involved in assessments, on method development and on the presentation of data on assessments. These have been prepared by the Steering Group, and will be taken forward by the Food Standards Agency and other agencies in the UK. The recommendations are included in this memorandum.

A new approach for environmental justice impact assessment

International Nuclear Information System (INIS)

Wilkinson, C.H.; Brumburgh, G.P.; Edmunds, T.A.; Kay, D.

1996-03-01

President Clinton's Executive Order 12898 calls for examination of disproportionately high and adverse impacts to minority and low-income communities. In addition to demographic mapping, environmental justice analyses should also include quantitative impact assessment to show presence or absence of disproportionate impacts. This study demonstrates use of a geographic information system (GIS) and a computer model. For this demonstration, a safety analysis report and a computer code were used to develop impact assessment data from a hypothetical facility accident producing a radiological airborne plume. The computer code modeled the plume, plotted dose contours, and provided latitude and longitude coordinates for transfer to the GIS. The GIS integrated and mapped the impact and demographic data toprovide a graphical representation of the plume with respect to the population. Impacts were then analyzed. The GIS was used to estimate the total dose to the exposed population under the plume, the dose to the low-income population under the plume, and the dose to the minority population under the plume. Impacts among the population groups were compared to determine whether a dispropotionate share of the impacts were borne by minority or low-income populations

Biosphere model for assessing doses from nuclear waste disposal

International Nuclear Information System (INIS)

Zach, R.; Amiro, B.D.; Davis, P.A.; Sheppard, S.C.; Szekeley, J.G.

1994-01-01

The biosphere model, BIOTRAC, for predicting long term nuclide concentrations and radiological doses from Canada's nuclear fuel waste disposal concept of a vault deep in plutonic rock of the Canadian Shield is presented. This generic, boreal zone biosphere model is based on scenario analysis and systems variability analysis using Monte Carlo simulation techniques. Conservatism is used to bridge uncertainties, even though this creates a small amount of extra nuclide mass. Environmental change over the very long assessment period is mainly handled through distributed parameter values. The dose receptors are a critical group of humans and four generic non-human target organisms. BIOTRAC includes six integrated submodels and it interfaces smoothly with a geosphere model. This interface includes a bedrock well. The geosphere model defines the discharge zones of deep groundwater where nuclides released from the vault enter the biosphere occupied by the dose receptors. The size of one of these zones is reduced when water is withdrawn from the bedrock well. Sensitivity analysis indicates 129 I is by far the most important radionuclide. Results also show bedrock-well water leads to higher doses to man than lake water, but the former doses decrease with the size of the critical group. Under comparable circumstances, doses to the non-human biota are greater than those for man

Survey of environmental radiation dose rates in Kyoto and Shiga prefectures, Japan

International Nuclear Information System (INIS)

Minamia, Kazuyuki; Shimo, Michikuni; Oka, Mitsuaki; Ejiri, Kazutaka; Sugino, Masato; Minato, Susumu; Hosoda, Masahiro; Yamada, Junya; Fukushi, Masahiro

2008-01-01

We have measured environmental radiation dose rates in several Prefectures, such as Ai chi Prefecture, Gifu Prefecture, and Mie Prefecture, in central Japan. Recently, we measured the environmental radiation dose rates in Kyoto and Shiga Prefectures that are also located in central Japan with a car-borne survey system. At the time of measurement, Kyoto Prefecture (area: 4,613 km 2 ) had a total of 36 districts, and Shiga Prefecture (area: 3,387 km 2 ) a total of 26. Terrestrial gamma ray dose rates and secondary cosmic ray dose rates were measured by a 2 inches ψ x 2 inches NaI(Tl) scintillation counter and a handy-type altimeter (GPS eTrex Legend by Gamin), respectively. The following factors were taken into consideration the shielding effect of the car body, the effect of the road pavement, radon progeny borne by precipitation, and increases in tunnels and near the walls. Terrestrial gamma ray dose rates in Kyoto and Shiga Prefectures were estimated to be 51.7 ± 6.0 n Gy/h (district average: 52.4 ± 4.7 n Gy/h), 52.2 ± 10.5 n Gy/h (district average: 51.9 ± 8.1 n Gy/h), respectively. Secondary cosmic ray dose rates in Kyoto and Shiga Prefectures were 30.0 ± 0.6 n Gy/h (district average: 29.9 ±0.3 n Gy/h), 30.1 ± 0.3 n Gy/h (district average: 30.0 ± 0.2 n Gy/h), respectively. The environmental radiation dose rates due to the sum dose rates of terrestrial gamma ray and secondary cosmic ray in Kyoto and Shiga Prefectures were 81.7 ± 6.2 n Gy/h (district average: 82.3 ± 4.8 n Gy/h), 82.3 ± 10.6 n Gy/h (district average: 82.0 ± 8.1 n Gy/h), respectively. We confirmed that the environmental radiation dose rates in Kyoto and Shiga Prefectures mainly depended on the change of the terrestrial gamma ray dose rates, since the secondary cosmic ray dose rates had little change. Therefore, radiation dose-rate maps of the terrestrial gamma rays as well as maps of the environmental radiation dose-rate were drawn. (author)

Internal dose assessment due to large area contamination: Main lessons drawn from the Chernobyl accident

Energy Technology Data Exchange (ETDEWEB)

Andrasi, A [KFKI Atomic Energy Research Inst., Budapest (Hungary)

1997-03-01

The reactor accident at Chernobyl in 1986 beside its serious and tragic consequences provided also an excellent opportunity to check, test and validate all kind of environmental models and calculation tools which were available in the emergency preparedness systems of different countries. Assessment of internal and external doses due to the accident has been carried out for the population all over Europe using different methods. Dose predictions based on environmental model calculation considering various pathways have been compared with those obtained by more direct monitoring methods. One study from Hungary and one from the TAEA is presented shortly. (orig./DG)

Internal dose assessment due to large area contamination: Main lessons drawn from the Chernobyl accident

International Nuclear Information System (INIS)

Andrasi, A.

1997-01-01

The reactor accident at Chernobyl in 1986 beside its serious and tragic consequences provided also an excellent opportunity to check, test and validate all kind of environmental models and calculation tools which were available in the emergency preparedness systems of different countries. Assessment of internal and external doses due to the accident has been carried out for the population all over Europe using different methods. Dose predictions based on environmental model calculation considering various pathways have been compared with those obtained by more direct monitoring methods. One study from Hungary and one from the TAEA is presented shortly. (orig./DG)

Occupational dose assessment in interventional cardiology in Serbia

International Nuclear Information System (INIS)

Kaljevic, J.; Ciraj-Bjelac, O.; Stankovic, J.; Arandjic, D.; Bozovic, P.; Antic, V.

2016-01-01

The objective of this work is to assess the occupational dose in interventional cardiology in a large hospital in Belgrade, Serbia. A double-dosimetry method was applied for the estimation of whole-body dose, using thermoluminescent dosemeters, calibrated in terms of the personal dose equivalent H p (10). Besides the double-dosimetry method, eye dose was also estimated by means of measuring ambient dose equivalent, H*(10), and doses per procedure were reported. Doses were assessed for 13 physicians, 6 nurses and 10 radiographers, for 2 consequent years. The maximum annual effective dose assessed was 4.3, 2.1 and 1.3 mSv for physicians, nurses and radiographers, respectively. The maximum doses recorded by the dosemeter worn at the collar level (over the apron) were 16.8, 11.9 and 4.5 mSv, respectively. This value was used for the eye lens dose assessment. Estimated doses are in accordance with or higher than annual dose limits for the occupational exposure. (authors)

Long-term environmental assessment of waste from PyroGreen system

International Nuclear Information System (INIS)

Ju, Heejae; Hahm, Inhye; Sohn, Sungjune; Hwang, Il-Soon

2016-01-01

We have conducted a long-term environmental assessment of a geological repository for Intermediate Level Wastes (ILW) arising from PyroGreen processes that has been developed to decontaminate all HLW from the pyrochemical partitioning of spent nuclear fuels (SNF). PyroGreen process has been designed so that final ILW can meet conservative acceptance criteria such as one established for the Waste Isolation Pilot Plant (WIPP) in U.S.A. The nuclide inventory of final vitrified PyroGreen waste is calculated using ORIGEN 2.1 based on the design decontamination factor of PyroGreen processes applied to 18,171 metric tons of PWR SNF with 45 GWD/MTU burnup. Using GoldSim model, the environmental impact of ILW upon geological disposal at an intermediate depth. Among radioactive nuclides, Ra 226 , Rn 222 and Sn 126 are identified as key contributors to radiological dose for general public. The environmental impact of PyroGreen wastes satisfies the Korean dose limit of 0.1 mSv/year with sufficiently high margin. Sensitivity studies have shown that the predicted dose can vary significantly by distribution coefficient of Ra 226 and Rn 222 , solubility limit of Se 79 . (authors)

Long-term environmental assessment of waste from PyroGreen system

Energy Technology Data Exchange (ETDEWEB)

Ju, Heejae; Hahm, Inhye; Sohn, Sungjune; Hwang, Il-Soon [Seoul National University, Gwanak-ro, Gwanak-gu, Seoul, 151-742 (Korea, Republic of)

2016-07-01

We have conducted a long-term environmental assessment of a geological repository for Intermediate Level Wastes (ILW) arising from PyroGreen processes that has been developed to decontaminate all HLW from the pyrochemical partitioning of spent nuclear fuels (SNF). PyroGreen process has been designed so that final ILW can meet conservative acceptance criteria such as one established for the Waste Isolation Pilot Plant (WIPP) in U.S.A. The nuclide inventory of final vitrified PyroGreen waste is calculated using ORIGEN 2.1 based on the design decontamination factor of PyroGreen processes applied to 18,171 metric tons of PWR SNF with 45 GWD/MTU burnup. Using GoldSim model, the environmental impact of ILW upon geological disposal at an intermediate depth. Among radioactive nuclides, Ra{sup 226}, Rn{sup 222} and Sn{sup 126} are identified as key contributors to radiological dose for general public. The environmental impact of PyroGreen wastes satisfies the Korean dose limit of 0.1 mSv/year with sufficiently high margin. Sensitivity studies have shown that the predicted dose can vary significantly by distribution coefficient of Ra{sup 226} and Rn{sup 222}, solubility limit of Se{sup 79}. (authors)

Human Health Risk Assessment (HHRA) for Environmental Development and Transfer of Antibiotic Resistance

Science.gov (United States)

Amézquita, Alejandro; Backhaus, Thomas; Borriello, Peter; Brandt, Kristian K.; Collignon, Peter; Coors, Anja; Finley, Rita; Gaze, William H.; Heberer, Thomas; Lawrence, John R.; Larsson, D.G. Joakim; McEwen, Scott A.; Ryan, James J.; Schönfeld, Jens; Silley, Peter; Snape, Jason R.; Van den Eede, Christel; Topp, Edward

2013-01-01

Background: Only recently has the environment been clearly implicated in the risk of antibiotic resistance to clinical outcome, but to date there have been few documented approaches to formally assess these risks. Objective: We examined possible approaches and sought to identify research needs to enable human health risk assessments (HHRA) that focus on the role of the environment in the failure of antibiotic treatment caused by antibiotic-resistant pathogens. Methods: The authors participated in a workshop held 4–8 March 2012 in Québec, Canada, to define the scope and objectives of an environmental assessment of antibiotic-resistance risks to human health. We focused on key elements of environmental-resistance-development “hot spots,” exposure assessment (unrelated to food), and dose response to characterize risks that may improve antibiotic-resistance management options. Discussion: Various novel aspects to traditional risk assessments were identified to enable an assessment of environmental antibiotic resistance. These include a) accounting for an added selective pressure on the environmental resistome that, over time, allows for development of antibiotic-resistant bacteria (ARB); b) identifying and describing rates of horizontal gene transfer (HGT) in the relevant environmental “hot spot” compartments; and c) modifying traditional dose–response approaches to address doses of ARB for various health outcomes and pathways. Conclusions: We propose that environmental aspects of antibiotic-resistance development be included in the processes of any HHRA addressing ARB. Because of limited available data, a multicriteria decision analysis approach would be a useful way to undertake an HHRA of environmental antibiotic resistance that informs risk managers. Citation: Ashbolt NJ, Amézquita A, Backhaus T, Borriello P, Brandt KK, Collignon P, Coors A, Finley R, Gaze WH, Heberer T, Lawrence JR, Larsson DG, McEwen SA, Ryan JJ, Schönfeld J, Silley P, Snape JR

Organ doses as a function of body weight for environmental gamma rays

International Nuclear Information System (INIS)

Saito, Kimiaki; Petoussi, N.; Zankl, M.; Veit, R.; Jacob, P.; Drexler, G.

1991-01-01

The organ doses for γ rays from typical environmental sources were determined with Monte Carlo calculations using anthropomorphic phantoms having different body sizes. It has been suggested that body weight is the predominant factor influencing organ doses for environmental γ rays, regardless of sex and age. A weight function expressing organ doses for environmental γ rays was introduced. This function fitted well with the organ doses calculated using the different phantoms. The function coefficients were determined mathematically with the least squares method. On the assumption that this function was applicable to organ doses for human bodies with diverse characteristics, the variances in organ doses due to race, sex, age and difference in body weight of adults were investigated. The variations of organ doses due to race and sex were not significant. Differences in body weight were found to alter organ doses by a maximum of 10% for γ rays over 100 keV, and 20% for low-energy γ rays. The doses for organs located deep inside a body, such as ovaries, differed between a newborn baby and an adult by a maximum factor of 2 to 3. For γ rays over 100 keV, the variation was within a factor of 2 for all organs. The organ doses for adolescents more than 12 years agreed within 15% with those of the average adult. (author)

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

CERN Document Server

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

2002-01-01

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

Dose Rate of Environmental Gamma Radiation in Java Island

International Nuclear Information System (INIS)

Gatot Suhariyono; Buchori; Dadong Iskandar

2007-01-01

The dose rate Monitoring of environmental gamma radiation at some locations in Java Island in the year 2005 / 2006 has been carried out. The dose rate measurement of gamma radiation is carried out by using the peripheral of Portable Gamma of Ray Spectrometer with detector of NaI(Tl), Merck Exploranium, Model GR-130- MINISPEC, while to determine its geographic position is used by the GPS (Global Positioning System), made in German corporation of GPS III Plus type. The division of measurement region was conducted by dividing Java Island become 66 parts with same distance, except in Jepara area that will built PLTN (Nuclear Energy Power), distance between measurement points is more closed. The results of dose rate measurement are in 66 locations in Java Island the range of (19.24 ± 4.05) nSv/hour until (150.78 ± 12.26) nSv/hour with mean (51.93 ± 36.53) nSv/h. The lowest dose rate was in location of Garut, while highest dose rate was in Ujung Lemah Abang, Jepara location. The data can be used for base line data of dose rate of environmental gamma radiation in Indonesia, specially in Java Island. The mean level of gamma radiation in Java monitoring area (0.46 mSv / year) was still lower than worldwide average effective dose rate of terrestrial gamma rays 0.5 mSv / year (report of UNSCEAR, 2000). (author)

Environmental Hazards Assessment Program. Volume 4: Annual report, July 1, 1993--June 30, 1994

International Nuclear Information System (INIS)

1994-01-01

The Medical University of South Carolina's (MUSC) vision is to become the premier national resource for medical information and for environmental/health risk assessment. A key component to the success of the many missions of the Environmental Hazards Assessment Program (EHAP) is timely access to large volumes of data. The significant growth in the number of environmental/health information systems that has occurred over the past few years has made data access challenging. This study documents the results of the needs assessment effort conducted to determine the information access and processing requirements of EHAP. The following topics are addressed in this report: immunological consequences of beryllium exposure; assessment of genetic risks to environmental diseases; low dose-rate radiation health effects; environmental risk perception in defined populations; information support and access systems; and environmental medicine and risk communication: curriculum and a professional support network-Department of Family Medicine

Environmental Hazards Assessment Program. Volume 4: Annual report, July 1, 1993--June 30, 1994

Energy Technology Data Exchange (ETDEWEB)

1994-09-01

The Medical University of South Carolina`s (MUSC) vision is to become the premier national resource for medical information and for environmental/health risk assessment. A key component to the success of the many missions of the Environmental Hazards Assessment Program (EHAP) is timely access to large volumes of data. The significant growth in the number of environmental/health information systems that has occurred over the past few years has made data access challenging. This study documents the results of the needs assessment effort conducted to determine the information access and processing requirements of EHAP. The following topics are addressed in this report: immunological consequences of beryllium exposure; assessment of genetic risks to environmental diseases; low dose-rate radiation health effects; environmental risk perception in defined populations; information support and access systems; and environmental medicine and risk communication: curriculum and a professional support network-Department of Family Medicine.

Negotiating NORM cleanup and land use limits: Practical use of dose assessment and cost benefit analysis

International Nuclear Information System (INIS)

Blanchard, A.D.H.

1997-01-01

Oil companies are presently faced with complex and costly environmental decisions, especially concerning NORM cleanup and disposal. Strict cleanup limits and disposal restrictions are established, in theory, to protect public health and environment. While public health is directly measured in terms of dose (mrem/yr), most NORM regulations adopt soil concentration limits to ensure future public health is maintained. These derived soil limits create the potential for unnecessary burden to operators without additional health benefit to society. Operators may use a dose assessment to show direct compliance with dose limits, negotiating less restrictive cleanup levels and land use limits. This paper discusses why a dose assessment is useful to Oilfield operators, NORM exposure scenarios and pathways, assessment advantages, variables and recommendations and one recent dose assessment application. Finally, a cost benefit analysis tool for regulatory negotiations will be presented allowing comparison of Oilfield NORM health benefit costs to that of other industries. One use for this tool--resulting in the savings of approximately $100,000--will be discussed

Discussion of environmental impact assessment for the nuclear technology application in hospital

International Nuclear Information System (INIS)

Li Shaoting; Xu Zhongyang

2010-01-01

Medical use of ionizing radiation has become the greatest artificial radiation in the world. Based on the characteristics of the nuclear technology application in hospital the content of the environmental impact assessment has been stated, including identification of the environmental impact factor, the standard, the environmental impact, control of the pollution as well. The dose of the medical staff which engaged in interventional operation and the accompanies of the patients which received nuclear medicine treatment should be focused on. (authors)

Investigation of natural radiation background and assessment of its population dose in China

International Nuclear Information System (INIS)

1989-01-01

This paper presents the nationwide survey in 1984-1988 of environmental external radiation by integrating measurements, and the assessment of population doses from obtained data. Thermoluminescent dosimeters (TLD) model ETLD-80 with CaSO 4 : Dy were used. The survey was conducted in two different scales. In general survey, TLDs were distributed in whole area of every investigated provinces; and in local survey, one city and one village within each province were selected and investigated for the purpose of comparison of the natural radiation levels between the rural and urban areas. A marked characteristics was noted that the level of natural environmental radiation in south China seems to be higher than that in north China. It may be attributed to the geological difference in both parts. The annual individual average and collective effective dose equivalents to population of China from natural environmental radiation were estimated to be 780 μSv and 8.1 x 10 5 man. Sv, based on the model recommended by UNSCEAR 1988 Report

Assessment of internal doses

CERN Document Server

Rahola, T; Falk, R; Isaksson, M; Skuterud, L

2002-01-01

There is a definite need for training in dose calculation. Our first course was successful and was followed by a second, both courses were fully booked. An example of new tools for software products for bioassay analysis and internal dose assessment is the Integrated Modules for Bioassay Analysis (IMBA) were demonstrated at the second course. This suite of quality assured code modules have been adopted in the UK as the standard for regulatory assessment purposes. The intercomparison measurements are an important part of the Quality Assurance work. In what is known as the sup O utside workers ' directive it is stated that the internal dose measurements shall be included in the European Unions supervision system for radiation protection. The emergency preparedness regarding internal contamination was much improved by the training with and calibration of handheld instruments from participants' laboratories. More improvement will be gained with the handbook giving practical instructions on what to do in case of e...

Radionuclide transport and dose assessment modelling in biosphere assessment 2009

International Nuclear Information System (INIS)

Hjerpe, T.; Broed, R.

2010-11-01

Following the guidelines set forth by the Ministry of Trade and Industry (now Ministry of Employment and Economy), Posiva is preparing to submit a construction license application for the final disposal spent nuclear fuel at the Olkiluoto site, Finland, by the end of the year 2012. Disposal will take place in a geological repository implemented according to the KBS-3 method. The long-term safety section supporting the license application will be based on a safety case that, according to the internationally adopted definition, will be a compilation of the evidence, analyses and arguments that quantify and substantiate the safety and the level of expert confidence in the safety of the planned repository. This report documents in detail the conceptual and mathematical models and key data used in the landscape model set-up, radionuclide transport modelling, and radiological consequences analysis applied in the 2009 biosphere assessment. Resulting environmental activity concentrations in landscape model due to constant unit geosphere release rates, and the corresponding annual doses, are also calculated and presented in this report. This provides the basis for understanding the behaviour of the applied landscape model and subsequent dose calculations. (orig.)

An updated dose assessment for Rongelap Island

Energy Technology Data Exchange (ETDEWEB)

Robison, W.L.; Conrado, C.L.; Bogen, K.T.

1994-07-01

We have updated the radiological dose assessment for Rongelap Island at Rongelap Atoll using data generated from field trips to the atoll during 1986 through 1993. The data base used for this dose assessment is ten fold greater than that available for the 1982 assessment. Details of each data base are presented along with details about the methods used to calculate the dose from each exposure pathway. The doses are calculated for a resettlement date of January 1, 1995. The maximum annual effective dose is 0.26 mSv y{sup {minus}1} (26 mrem y{sup {minus}1}). The estimated 30-, 50-, and 70-y integral effective doses are 0.0059 Sv (0.59 rem), 0.0082 Sv (0.82 rem), and 0.0097 Sv (0.97 rem), respectively. More than 95% of these estimated doses are due to 137-Cesium ({sup 137}Cs). About 1.5% of the estimated dose is contributed by 90-Strontium ({sup 90}Sr), and about the same amount each by 239+240-Plutonium ({sup 239+240}PU), and 241-Americium ({sup 241}Am).

A real-time internal dose assessment exercise

International Nuclear Information System (INIS)

Bingham, D.; Bull, R. K.

2013-01-01

A real-time internal dose assessment exercise has been conducted in which participants were required to make decisions about sampling requirements, seek relevant information about the 'incident' and make various interim dose assessments. At the end of the exercise, each participant was requested to make a formal assessment, providing statements of the methods, models and assumptions used in that assessment. In this paper we describe how the hypothetical assessment case was set up and the exercise was conducted, the responses of the participants and the assessments of dose that they made. Finally we discuss the lessons learnt from the exercise and suggest how the exercise may be adapted to a wider range of participants. (authors)

Monitoring and Analysis of Environmental Gamma Dose Rate around Serpong Nuclear Complex

Directory of Open Access Journals (Sweden)

I.P. Susila

2017-08-01

Full Text Available An environmental radiation monitoring system that continuously measures gamma dose rate around nuclear facilities is an important tool to present dose rate information to the public or authorities for radiological protection during both normal operation and radiological accidents. We have developed such a system that consists of six GM-based device for monitoring the environmental dose rate around Serpong Nuclear Complex. It has operated since 2010. In this study, a description of the system and analysis of measured data are presented. Analysis of the data for the last five years shows that the average dose rate levels were between 84-99 nSv/h which are still lower than terrestrial gamma radiation levels at several other locations in Indonesia. Time series analysis of the monitoring data demonstrates a good agreement between an increase in environmental gamma dose rate and the presence of iodine and argon in the air by in situ measurement. This result indicates that system is also effective for an early warning system in the case of radiological emergency.

System for prediction of environmental emergency dose information

International Nuclear Information System (INIS)

Moriuchi, Shigeru

1989-01-01

According to the national research program revised by the Japan Nuclear Safety Commission after the TMI-2 reactor accident JAERI started the development of a computer code system for the real-time prediction of environmental consequences following a nuclear reactor accident, and in 1985 the basic development of the System for Prediction of Environmental Emergency Dose Information SPEEDI was completed. The system consists of three-dimensional models of wind field calculation (WIND04), dispersion calculation (PRWDA) and internal and external dose calculation (CIDE), and is designed to speedily predict radioactive concentration in the air, the ground deposition and radiation doses of upto 100 km range by simulation calculation when the radioactive materials are accidentally released from a reactor. At Chernobyl accident the calculational domain of SPEEDI were extended tentatively upto 2000 km, and simulation calculations of the movement of radioactive cloud were executed, and the estimation of the amounts of released radioactivities were made using calculated results and observed data. The calculated distribution and the movement of plume well agreed with the distribution patterns evaluated from observation data, and the estimated source term agreed approximately with data reported from USSR and other countries. (author)

SPEEDI: system for prediction of environmental emergency dose information

International Nuclear Information System (INIS)

Chino, Masamichi; Ishikawa, Hirohiko; Kai, Michiaki

1984-03-01

In this report a computer code system for prediction of environmental emergency dose information , i.e., SPEEDI for short, is presented. In case of an accidental release of radioactive materials from a nuclear plant, it is very important for an emergency planning to predict the concentration and dose caused by the materials. The SPEEDI code system has been developed for this purpose and it has features to predict by calculation the released nuclides, wind fields, concentrations and dose based on release information, actual weather and topographical data. (author)

Evaluation of environmental radiation dose in Ibaraki Prefecture

International Nuclear Information System (INIS)

Koike, Ryoji

1977-01-01

In Ibaraki Prefecture, there is Environmental Radioactivity Surveillance Committee in order to ensure the safety around nuclear power facilities. Environmental radioactivity data are collected every three months, and the grasp of the present situation, the clarification of causes, the evaluation of dose and the publication of results are made. Two instances in particular are described: of contamination paddies due to 14 C contained in drainage; contamination of rivers due to U contained in drainage. (Mori, K.)

Environmental impact assessment report

Energy Technology Data Exchange (ETDEWEB)

Jung, K. J.; Paik, S. T.; Chung, U. S.; Jung, K. H.; Park, S. K.; Lee, D. G.; Kim, H. R.; Kim, J. K.; Yang, S. H.; Lee, B. J.; Kim, E. H.; Choi, K. S

2000-10-01

This report is the revised Environmental Impact Assessment Report which was made and submitted as one of the license documents for TRIGA Research Reactor D and D Project. The Environmental Impact Assessment Report includes introduction of decommissioning plan, status of reactors and environmental impact of surroundings. Also it was assessed and analyzed on radioactivity for environment, and the plan was established to minimize radioactive material release. Finally environmental monitoring plan was established to confirm whether contaminated or not from radioactivity during decommissioning period. According to the assessment results, the risk of excess exposure will be not on environment and public. The first Environmental Impact Assessment Report was submitted to the government for the license and reviewed by Korea Institute of Nuclear Safety. The first Report was revised including answers for the questions arising from review process.

Environmental monitoring, restoration and assessment: What have we learned

Energy Technology Data Exchange (ETDEWEB)

Gray, R.H. (ed.)

1990-01-01

The Twenty-Eighth Hanford Symposium on Health and the Environment was held in Richland, Washington, October 16--19, 1989. The symposium was sponsored by the US Department of Energy and the Pacific Northwest Laboratory, operated by Battelle Memorial Institute. The symposium was organized to review and evaluate some of the monitoring and assessment programs that have been conducted or are currently in place. Potential health and environmental effects of energy-related and other industrial activities have been monitored and assessed at various government and private facilities for over three decades. Most monitoring is required under government regulations; some monitoring is implemented because facility operators consider it prudent practice. As a result of these activities, there is now a substantial radiological, physical, and chemical data base for various environmental components, both in the United States and abroad. Symposium participants, both platform and poster presenters, were asked to consider, among other topics, the following: Has the expenditure of millions of dollars for radiological monitoring and assessment activities been worth the effort How do we decide when enough monitoring is enough Can we adequately assess the impacts of nonradiological components -- both inorganic and organic -- of wastes Are current regulatory requirements too restrictive or too lenient Can monitoring and assessment be made more cost effective Papers were solicited in the areas of environmental monitoring; environmental regulations; remediation, restoration, and decommissioning; modeling and dose assessment; uncertainty, design, and data analysis; and data management and quality assurance. Individual reports are processed separately for the databases.

Environmental monitoring, restoration and assessment: What have we learned?

International Nuclear Information System (INIS)

Gray, R.H.

1990-01-01

The Twenty-Eighth Hanford Symposium on Health and the Environment was held in Richland, Washington, October 16--19, 1989. The symposium was sponsored by the US Department of Energy and the Pacific Northwest Laboratory, operated by Battelle Memorial Institute. The symposium was organized to review and evaluate some of the monitoring and assessment programs that have been conducted or are currently in place. Potential health and environmental effects of energy-related and other industrial activities have been monitored and assessed at various government and private facilities for over three decades. Most monitoring is required under government regulations; some monitoring is implemented because facility operators consider it prudent practice. As a result of these activities, there is now a substantial radiological, physical, and chemical data base for various environmental components, both in the United States and abroad. Symposium participants, both platform and poster presenters, were asked to consider, among other topics, the following: Has the expenditure of millions of dollars for radiological monitoring and assessment activities been worth the effort? How do we decide when enough monitoring is enough? Can we adequately assess the impacts of nonradiological components -- both inorganic and organic -- of wastes? Are current regulatory requirements too restrictive or too lenient? Can monitoring and assessment be made more cost effective? Papers were solicited in the areas of environmental monitoring; environmental regulations; remediation, restoration, and decommissioning; modeling and dose assessment; uncertainty, design, and data analysis; and data management and quality assurance. Individual reports are processed separately for the databases

Internal dose assessment in a case of continuous intake of Cs 137

International Nuclear Information System (INIS)

Gomez Parada, I.; Rojo, A.M.

2000-01-01

In 1997 the Argentine Nuclear Regulatory Authority (ARN) was invited to participate in the '3rd. European Intercomparison Exercise on Internal Dose Assessment'. This paper presents the solution submitted by the ARN to one of the cases proposed in the exercise. This is a real case of continuous ingestion of cesium 137 due to the environmental contamination arising from the Chernobyl accident. The subject was member of the public and the results of whole body counter measurements were provided. The monitoring period spanned from the first month after the accident to approximately 880 days later. The solution implied to estimate the total intake for the accident until the end of the monitoring period, the effective dose received by the subject in 1986 and 1987 respectively and the committed effective dose due to the total intake. For the intake assessment the code Cindy v 1.4 was used, assuming a constant rate of intake during the whole period of intake. The systemic retention model for caesium was that of the ICRP 30, with a modified biological half-life of the long-term retention. The dates of the beginning and end of the period of intake were chosen, using the same software, looking for the ones that fits better to the measurements data. This rate of intake and the same metabolic models used for the intake assessment were the input to the CINDY code to find the dose received by the subject in 1986 and 1987 respectively, as well as the committed effective dose. An alternative dose assessment was made, directly from body burden measurements, in order to compare the obtained values. In this approach, the software Origin 4.0 was used to graph the whole body activity measurements and the integrate it for the desired time intervals. Applying the corresponding Specific Effective Energy value obtained from LUPED 2.06 for the reference man, the effective doses were obtained directly from body burden. It was found that the values for the effective doses were almost the same

A package for environmental impact assessment of nuclear installations (NGLAR)

International Nuclear Information System (INIS)

Yang Yin; Chen Xiaoqiu; Ding Jinhou; Zhao Hui; Xi Xiaojun; Li Hongsheng

1996-09-01

The main contents, designing strategies and properties of the microcomputer-based software package NGLAR are described for environmental impact assessment of nuclear installations. The package consists of the following components: NGAS and NACC, the codes for routine and accidental airborne releases respectively; NLIQ, the code for both routine and accidental liquid releases; and NRED, environmental database system of nuclear installations. NGAS and NACC are used for evaluating atmosphere dispersion and doses to public of radioactive materials released from nuclear facilities, giving the concentrations around the facilities of radionuclides in air, on ground surface, and in varieties of animal foods and farm produces, and further estimating collective doses and doses to critical group around the facilities. NLIQ is suitable for liquid effluence released to non-tide rivers, and is modelled to calculate firstly the concentration of radionuclides concerned in the polluted rivers, and then to estimate the resulting doses to public. Under routine releases, the doses obtained from NGAS and NLIQ can be appropriately categorized and summed up together. NRED can be run independently, also used to provide some input data for above programs and save data permanently for them. Having both English and Chinese versions, the package, which was fabricated of multiple functions can be run on IBM 386 or higher and its compatible microcomputers. (3 figs., 1 tabs)

Overview of the Multimedia Environmental Pollutant Assessment System (MEPAS)

International Nuclear Information System (INIS)

Whelan, G.; Buck, J.W.; Strenge, D.L.; Droppo, J.G.; Hoopes, B.L.; Aiken, R.J.

1992-01-01

The Multimedia Environmental Pollutant Assessment System (MEPAS) is a physics-based risk computation code that integrates source-term, transport, and exposure models. Developed by Pacific Northwest Laboratory for screening and ranking of environmental problems, MEPAS is designed for site-specific assessments using readily available information to estimate potential health impacts. Risk values are computed for chemical and radioactive carcinogens; while hazard quotients, based on reference doses, are computed for noncarcinogens. This system has wide applicability to a range of environmental problems using air, groundwater, surface-water, overland, and exposure models. Whenever available and appropriate, EPA guidance and models were used to facilitate compatibility and acceptance. Although based on relatively standard transport and exposure computation approaches, the unique feature of MEPAS is that these approaches are integrated into a single system. The use of a single system provides a consistent basis for evaluating health impacts for a large number of problems and sites. Implemented on a desktop computer, a user-friendly shell allows the user to define the problem, input the required data, and execute the appropriate models. The MEPAS guidance documents include sources of information. MEPAS can be used for both screening and assessment applications for the remedial investigation/risk assessment/feasibility study and environment restoration processes

A review of occupational dose assessment uncertainties and approaches

International Nuclear Information System (INIS)

Anderson, R. W.

2004-01-01

The Radiological Protection Practitioner (RPP) will spend a considerable proportion of his time predicting or assessing retrospective radiation exposures to occupational personnel for different purposes. The assessments can be for a variety of purposes, such as to predict doses for occupational dose control, or project design purposes or to make retrospective estimates for the dose record, or account for dosemeters which have been lost or damaged. There are other less frequent occasions when dose assessment will be required such as to support legal cases and compensation claims and to provide the detailed dose information for epidemiological studies. It is important that the level of detail, justification and supporting evidence in the dose assessment is suitable for the requirements. So for instance, day to day operational dose assessments often rely mainly on the knowledge of the RPP in discussion with operators whilst at the other end of the spectrum a historical dose assessment for a legal case will require substantial research and supporting evidence for the estimate to withstand forensic challenge. The robustness of the assessment will depend on many factors including a knowledge of the work activities, the radiation dose uptake and field characteristics; all of which are affected by factors such as the time elapsed, the memory of operators and the dosemeters employed. This paper reviews the various options and uncertainties in dose assessments ranging from use of personal dosimetry results to the development of upper bound assessments. The level of assessment, the extent of research and the evidence adduced should then be appropriate to the end use of the estimate. (Author)

Development of environmental risk assessment framework using index method

International Nuclear Information System (INIS)

Ali, M.W.; Wu, Y.

2000-01-01

This paper presents a newly developed framework for assessing the risk from events which are considered to be major accidents to the environment according to the classifications by the United Kingdom Department of Environment (DoE). The application of an environmental risk assessment framework using the newly developed index method is demonstrated by means of a case study. The framework makes use of Environmental Hazard Index (EHI) method by the United Kingdom AEA Technology for releases to river, but improves it by taking account to toxic dose rather than concentration; taking account of long-term effects including persistence and bio accumulation, not just short term effects; extending the method to all aspects of environment, not just rivers; and allowing account to be taken of design changes to mitigate the risk. The development of the framework has also led to a revision of the tolerability criteria to be used with the framework proposed earlier by weakness and recommend further work to improve this newly proposed environmental risk assessment framework. From the study, it is recommended that the environmental risk assessment framework be applied to a wide range of other case studies in order to further improve it. The framework should be modified to maintain consistency when the DoE revises its definitions of major accidents to the environment. Ease-of-use of the framework (and any other environmental framework) would be aided by the compilation of databases for environmental toxicity, river data and available consequence models. Further work could also be done to suggest methods of mitigating the risk and including them as numerical factors within method. (author)

Dose assessments for SFR 1

International Nuclear Information System (INIS)

Bergstroem, Ulla; Avila, Rodolfo; Ekstroem, Per-Anders; Cruz, Idalmis de la

2008-05-01

Following a review by the Swedish regulatory authorities of the safety analysis of the SFR 1 disposal facility for low and intermediate level waste, SKB has prepared an updated safety analysis, SAR-08. This report presents estimations of annual doses to the most exposed groups from potential radionuclide releases from the SFR 1 repository for a number of calculation cases, selected using a systematic approach for identifying relevant scenarios for the safety analysis. The dose estimates can be used for demonstrating that the long term safety of the repository is in compliance with the regulatory requirements. In particular, the mean values of the annual doses can be used to estimate the expected risks to the most exposed individuals, which can then be compared with the regulatory risk criteria for human health. The conversion from doses to risks is performed in the main report. For one scenario however, where the effects of an earthquake taking place close to the repository are analysed, risk calculations are presented in this report. In addition, prediction of concentrations of radionuclides in environmental media, such as water and soil, are compared with concentration limits suggested by the Erica-project as a base for estimating potential effects on the environment. The assessment of the impact on non-human biota showed that the potential impact is negligible. Committed collective dose for an integration period of 10,000 years for releases occurring during the first thousand years after closure are also calculated. The collective dose commitment was estimated to be 8 manSv. The dose calculations were carried out for a period of 100,000 years, which was sufficient to observe peak doses in all scenarios considered. Releases to the landscape and to a well were considered. The peaks of the mean annual doses from releases to the landscape are associated with C-14 releases to a future lake around year 5,000 AD. In the case of releases to a well, the peak annual doses

Dose assessments for SFR 1

Energy Technology Data Exchange (ETDEWEB)

Bergstroem, Ulla (Swedish Nuclear Fuel and Waste Management Co., Stockholm (Sweden)); Avila, Rodolfo; Ekstroem, Per-Anders; Cruz, Idalmis de la (Facilia AB, Bromma (Sweden))

2008-06-15

Following a review by the Swedish regulatory authorities of the safety analysis of the SFR 1 disposal facility for low and intermediate level waste, SKB has prepared an updated safety analysis, SAR-08. This report presents estimations of annual doses to the most exposed groups from potential radionuclide releases from the SFR 1 repository for a number of calculation cases, selected using a systematic approach for identifying relevant scenarios for the safety analysis. The dose estimates can be used for demonstrating that the long term safety of the repository is in compliance with the regulatory requirements. In particular, the mean values of the annual doses can be used to estimate the expected risks to the most exposed individuals, which can then be compared with the regulatory risk criteria for human health. The conversion from doses to risks is performed in the main report. For one scenario however, where the effects of an earthquake taking place close to the repository are analysed, risk calculations are presented in this report. In addition, prediction of concentrations of radionuclides in environmental media, such as water and soil, are compared with concentration limits suggested by the Erica-project as a base for estimating potential effects on the environment. The assessment of the impact on non-human biota showed that the potential impact is negligible. Committed collective dose for an integration period of 10,000 years for releases occurring during the first thousand years after closure are also calculated. The collective dose commitment was estimated to be 8 manSv. The dose calculations were carried out for a period of 100,000 years, which was sufficient to observe peak doses in all scenarios considered. Releases to the landscape and to a well were considered. The peaks of the mean annual doses from releases to the landscape are associated with C-14 releases to a future lake around year 5,000 AD. In the case of releases to a well, the peak annual doses

Occupational exposure of phosphate mine workers: airborne radioactivity measurements and dose assessment

International Nuclear Information System (INIS)

Khater, Ashraf E.; Hussein, M.A.; Hussein, Mohamed I.

2004-01-01

Under the Egyptian program for radiation safety and control, airborne radioactivity measurements and radiological dose assessment were conducted in some phosphate and uranium mines. Abu-Tartor mine is one of the biggest underground phosphate mines in Egypt. Airborne radioactivity, radon ( 222 Rn) and its short-lived decay products (progenies) and thoron ( 220 Rn), were measured in selected locations along the mine. The environmental gamma and workers dose equivalent rate (mSv/y) were measured inside and outside the mine using thermo-luminescence dosimeters (TLD). The results were presented and discussed. The calculated annual effective dose due to airborne radioactivity is the main source of occupational exposure and exceeding the maximum recommended level by ICRP-60 inside the mine tunnels. A number of recommendations are suggested to control the occupational exposures

Cumulative Impact Assessment: Approaching Environmental Capacity in Development Area Using Environmental Impact Assessment Information

Science.gov (United States)

Cho, N.; Lee, M. J.; Maeng, J. H.

2017-12-01

Environmental impact assessment estimates the impact of development as a business unit and establishes mitigation plan. If the development is done, its economic effects can spread to the nearby areas. So that various developments can be distributed at different time intervals. The impact of the new developments can be combined with existing environmental impacts and can have a larger impact. That is, Cumulative impact assessment is needed to consider the environmental capacity of the Nearby area. Cumulative impact assessments require policy tools such as environmental impact assessment information and cumulative impact estimation models. In Korea, environmental information (water quality, air quality, etc.) of the development site is measured for environmental impact assessment and monitored for a certain period (generally 5 years) after the project. In addition, by constructing the environmental information as a spatial database, it is possible to express the environmental impact on a regional basis spatially and to intuitively use it for development site selection. Utilizing a composite model of environmental impact assessment information and Remote Sensing data for cumulative impact estimation, That can be used as a policy decision support tool that provides quantitative information for development area management, such as time series effect and sprawl phenomenon.

Estimation of 1945 to 1957 food consumption. Hanford Environmental Dose Reconstruction Project

Energy Technology Data Exchange (ETDEWEB)

Anderson, D.M.; Bates, D.J.; Marsh, T.L.

1993-07-01

This report details the methods used and the results of the study on the estimated historic levels of food consumption by individuals in the Hanford Environmental Dose Reconstruction (HEDR) study area from 1945--1957. This period includes the time of highest releases from Hanford and is the period for which data are being collected in the Hanford Thyroid Disease Study. These estimates provide the food-consumption inputs for the HEDR database of individual diets. This database will be an input file in the Hanford Environmental Dose Reconstruction Integrated Code (HEDRIC) computer model that will be used to calculate the radiation dose. The report focuses on fresh milk, eggs, lettuce, and spinach. These foods were chosen because they have been found to be significant contributors to radiation dose based on the Technical Steering Panel dose decision level.

An environmental assessment system for environmental technologies

DEFF Research Database (Denmark)

Clavreul, Julie; Baumeister, Hubert; Christensen, Thomas Højlund

2014-01-01

A new model for the environmental assessment of environmental technologies, EASETECH, has been developed. The primary aim of EASETECH is to perform life-cycle assessment (LCA) of complex systems handling heterogeneous material flows. The objectives of this paper are to describe the EASETECH...

Energy and environmental assessment

DEFF Research Database (Denmark)

Lund, Henrik; Sukkumnoed, Decharut

2004-01-01

The paper introduce and discuss strategic environmental assessment (SEA) and economic assessment for energy innovation and suggests approach to influence support for sustainable energy development in Thailand.......The paper introduce and discuss strategic environmental assessment (SEA) and economic assessment for energy innovation and suggests approach to influence support for sustainable energy development in Thailand....

Integrating environmental and socioeconomic assessment

International Nuclear Information System (INIS)

Branch, K.M.; Cluett, C.; Page, T.L.

1987-01-01

Since the passage of the National Environmental Policy Act (NEPA) in 1969, considerable scientific and regulatory attention has been given to the preparation of environmental impact assessments. Part of this attention has been directed to definition of the proper scope of an environmental assessment and to debate about how the ''human environment'' should be addressed. This debate continues, and is reflected in the ongoing evolution of the definition of and relationship between the ''environmental'' and ''socioeconomic'' components of an integrated environmental impact assessment. This paper discusses the need for close integration between the environmental and socioeconomic assessment efforts and examines some of the benefits and difficulties of achieving this integration

An Internal Dose Assessment Associated with Personal Food Intake

Energy Technology Data Exchange (ETDEWEB)

Lee, Joeun; Jae, Moosung [Hanyang University, Seoul (Korea, Republic of); Hwang, Wontae [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2015-10-15

ICRP (International Commission on Radiological Protection), Therefore, had recommended the concept of 'Critical Group'. Recently the ICRP has recommended the use of 'Representative Person' on the new basic recommendation 103. On the other hand the U.S. NRC (Nuclear Regulatory Commission) has adopted more conservative concept, 'Maximum Exposed Individuals (MEI)' of critical Group. The dose assessment in Korea is based on MEI. Although dose assessment based on MEI is easy to receive the permission of the regulatory authority, it is not efficient. Meanwhile, the internal dose by food consumption takes an important part. Therefore, in this study, the internal dose assessment was performed in accordance with ICRP's new recommendations. The internal dose assessment was performed in accordance with ICRP's new recommendations. It showed 13.2% decreased of the annual internal dose due to gaseous effluents by replacing MEI to the concept of representative person. Also, this calculation based on new ICRP's recommendation has to be extended to all areas of individual dose assessment. Then, more accurate and efficient values might be obtained for dose assessment.

Analysis of environmental impact assessment for large-scale X-ray medical equipments

International Nuclear Information System (INIS)

Fu Jin; Pei Chengkai

2011-01-01

Based on an Environmental Impact Assessment (EIA) project, this paper elaborates the basic analysis essentials of EIA for the sales project of large-scale X-ray medical equipment, and provides the analysis procedure of environmental impact and dose estimation method under normal and accident conditions. The key points of EIA for the sales project of large-scale X-ray medical equipment include the determination of pollution factor and management limit value according to the project's actual situation, the utilization of various methods of assessment and prediction such as analogy, actual measurement and calculation to analyze, monitor, calculate and predict the pollution during normal and accident condition. (authors)

Importance and variability in processes relevant to environmental tritium ingestion dose models

International Nuclear Information System (INIS)

Raskob, W.; Barry, P.

1997-01-01

The Aiken List was devised in 1990 to help decide which transport processes should be investigated experimentally so as to derive the greatest improvement in performance of environmental tritium assessment models. Each process was rated high, medium and low on each of two criteria. These were ''Importance'', which rated processes by how much each contributed to ingestion doses, and ''State of Modelling'', which rated the adequacy of the knowledge base on which models were built. Ratings, though unanimous, were, nevertheless, qualitative and subjective opinions. This paper describes how we have tried to quantify the ratings. To do this, we use, as measures of ''Importance'', sensitivities of predicted ingestion doses to changes in values of parameters in mathematical descriptions of individual processes. Measures of ''ModellinStatus'' were taken from a recently completed BIOMOVS study of HTO transport model performance and based either on by how much predicted transport by individual processes differed amongst participating modellers or by the variety of different ways that modellers chose to describe individual processes. The tritium transport model UFOTRI was used, and because environmental transport of HTO varies according to the weather at and after release time, sensitivities were measured in a sample of all conditions likely to arise in central Europe. (Author)

IAEA/IDEAS intercomparison exercise on internal dose assessment

International Nuclear Information System (INIS)

Doerfel, H.; Andrasi, A.; Cruz-Suarez, R.; Castellani, C. M.; Hurtgen, C.; Marsh, J.; Zeger, J.

2007-01-01

An Internet based intercomparison exercise on assessment of occupational exposure due to intakes of radionuclides has been performed to check the applicability of the 'General Guidelines for the Assessment of Internal Dose from Monitoring Data' developed by the IDEAS group. There were six intake cases presented on the Internet and 81 participants worldwide reported solutions to these cases. Results of the exercise indicate that the guidelines have a positive influence on the methodologies applied for dose assessments and, if correctly applied, improve the harmonisation of assessed doses. (authors)

Dose assessment models. Annex A

International Nuclear Information System (INIS)

1982-01-01

The models presented in this chapter have been separated into 2 general categories: environmental transport models which describe the movement of radioactive materials through all sectors of the environment after their release, and dosimetric models to calculate the absorbed dose following an intake of radioactive materials or exposure to external irradiation. Various sections of this chapter also deal with atmospheric transport models, terrestrial models, and aquatic models.

The assessment of collective dose for travellers travelling by water

International Nuclear Information System (INIS)

Yue Qingyu; Jiang Ping; Jin Hua

1992-06-01

The major contribution to the various radiation exposure received by mankind comes from natural radiation. Some environmental change caused by human beings and some activities of mankind may decrease or increase the radiation exposure level from natural radiation. People travelling by air will receive more exposure dose and by water will receive less. China has about 18000 km coast line and the inland water transportation is very flourishing. According to statistic data from Ministry of Transportation in 1988, the turnover in that year was about 2 x 10 10 man.km. The total number of fisherman for inshore fishing was nearly two million reported by Ministry of Farming, Animal Husbandry and Fishery. We measured 212 points in six typical shipping lines of inshore lines and inland rivers, and the distance was 5625 km. The average natural radiation exposure dose rate received by travellers in each shipping line was calculated. From that the assessment of collective dose equivalent for passengers by water and fishermen was derived. The value is 32.7 man.Sv for passengers and 265.3 man.Sv for fishermen

The assessment of collective dose for travellers travelling by water

International Nuclear Information System (INIS)

Yue Qingyu; Jian Ping; Jin Hua

1994-01-01

The major contribution to various radiation exposure received by mankind comes from natural radiation. Some environmental change caused by human beings and some activities of mankind may decrease or increase the radiation exposure level from natural radiation. China has about 18000 km coast line and the inland water transportation is very flourishing. According to statistic data from Ministry of Transportation in 1988, the turnover in that year was about 2 x 10 10 man·km. The total number of fisherman for inshore fishing was nearly two millions reported by Ministry of Farming, Animal Husbandry and Fishery. We measured exposure dose rates over 212 points in six typical shipping lines of inshore lines and inland rivers, and the distance was 5625 km. The average natural radiation exposure dose rate received by travellers in each shipping line was calculated. From that the assessment of collective dose equivalent for passengers by water and fishermen was derived. The value is 32.7 man·Sv for passengers and 265.3 man·Sv for fishermen

Work plan for the Hanford Environmental Dose Reconstruction Project

Energy Technology Data Exchange (ETDEWEB)

1989-12-01

The primary objective of the Hanford Environmental Dose Reconstruction (HEDR) Project is to estimate the radiation doses that populations could have received from nuclear operations at the Hanford Site since 1944, with descriptions of uncertainties inherent in such estimates. The secondary objective is to make project records--information that HEDR staff members used to estimate radiation doses--available to the public. Preliminary dose estimates for a limited geographic area and time period, certain radionuclides, and certain populations are planned to be available in 1990; complete results are planned to be reported in 1993. Project reports and references used in the reports are available to the public in the DOE Public Reading Room in Richland, Washington. Project progress is documented in monthly reports, which are also available to the public in the DOE Public Reading Room.

Program for rapid dose assessment in criticality accident, RADAPAS

International Nuclear Information System (INIS)

Takahashi, Fumiaki

2006-09-01

In a criticality accident, a person near fissile material can receive extremely high dose which can cause acute health effect. For such a case, medical treatment should be carried out for the exposed person, according to severity of the exposure. Then, radiation dose should be rapidly assessed soon after an outbreak of an accident. Dose assessment based upon the quantity of induced 24 Na in human body through neutron exposure is expected as one of useful dosimetry techniques in a criticality accident. A dose assessment program, called RADAPAS (RApid Dose Assessment Program from Activated Sodium in Criticality Accidents), was therefore developed to assess rapidly radiation dose to exposed persons from activity of induced 24 Na. RADAPAS consists of two parts; one is a database part and the other is a part for execution of dose calculation. The database contains data compendiums of energy spectra and dose conversion coefficients from specific activity of 24 Na induced in human body, which had been derived in a previous analysis using Monte Carlo calculation code. Information for criticality configuration or characteristics of radiation in the accident field is to be interactively given with interface displays in the dose calculation. RADAPAS can rapidly derive radiation dose to the exposed person from the given information and measured 24 Na specific activity by using the conversion coefficient in database. This report describes data for dose conversions and dose calculation in RADAPAS and explains how to use the program. (author)

Environmental dose measurement with microprocessor based portable TLD reader

International Nuclear Information System (INIS)

Deme, S.; Apathy, I.; Feher, I.

1996-01-01

Application of TL method for environmental gamma-radiation dosimetry involves uncertainty caused by the dose collected during the transport from the point of annealing to the place of exposure and back to the place of evaluation. Should an accident occur read out is delayed due to the need to transport to a laboratory equipped with a TLD reader. A portable reader capable of reading out the TL dosemeter at the place of exposure ('in situ TLD reader') eliminates the above mentioned disadvantages. We have developed a microprocessor based portable TLD reader for monitoring environmental gamma-radiation doses and for on board reading out of doses on space stations. The first version of our portable, battery operated reader (named Pille - 'butterfly') was made at the beginning of the 80s. These devices used CaSO 4 bulb dosemeters and the evaluation technique was based on analogue timing circuits and analogue to digital conversion of the photomultiplier current with a read out precision of 1 μGy and a measuring range up to 10 Gy. The measured values were displayed and manually recorded. The version with an external power supply was used for space dosimetry as an onboard TLD reader

Environmental impact assessment: Classification of ecosystems with respect to vulnerability for radioactive contamination

International Nuclear Information System (INIS)

Blytt, Line Diana

1999-01-01

This presentation recommends that an environmental impact assessment should be made ahead of any major action plan in the environment. The final document should point out to the authorities and public that expertise has been systematised in order to predict the effects of an action plan on the environment. This should be done for different scenarios and time scales. A useful tool for an environmental impact assessment is GIS, Geographic Information Systems. It can be used to identify areas and ecosystems that are vulnerable to radioactive contamination. To predict the radiation dose to humans and biota, a vulnerability assessment considers population density, land use, economic resources and the chemical and biological pathways of radionuclides in different ecosystems. Supplemented with knowledge of consumption and dietary habits a vulnerability assessment can be used to identify critical groups and to calculate doses to these groups. For ecosystems, vulnerability can be quantified by using critical loads for radioactive contamination or flux of radionuclides from an area. One criterion for critical load can be that intervention limits for food products should not be exceeded. If the critical load is low, this indicates a high vulnerability. The flux from an area can also identify vulnerability and it can be used to calculate collective dose. The vulnerability approach is a methodology that can be used to select areas that are suitable for treatment, transport and disposal of radioactive waste

Dose and risk assessment approach for the Fernald CERCLA D ampersand D Project

International Nuclear Information System (INIS)

Throckmorton, J.D.; Clark, T.R.; Waligora, S.J. Jr.; Haaker, R.F.

1994-01-01

At the Fernald Environmental Management Project (FEMP) the uranium processing facilities used from the 1952 through 1989 are near or beyond their intended design life. These current conditions present an increasing probability for future releases of hazardous substances to the environment. To support a decision by the U.S. Department of Energy (DOE) and the Environmental Protection Agency (EPA) to remediate the buildings, a dose and risk assessment was performed to determine the extent of exposure that would be associated with the controlled decontamination and dismantlement (D ampersand D) of the Fernald facilities. A conceptual risk assessment model was developed, with exposure mechanisms and associated pathways for each potential receptor. The three receptor groups were defined as: the remediation workers, other on-site workers (those not performing D ampersand D), and off-site residents. For use in the conceptual model, an airborne source term was developed through process knowledge, other historical information and data, and air sample data from within the facilities. Individual and collective doses and risks were developed for each receptor and for each population group. The risk assessment demonstrated that all exposures resulting from the action would be within the acceptable DOE administrative control level of 2.0 rem per year for occupational workers and the acceptable EPA risk range from 10 -6 to 10 -4 for the general public

A radiological dose assessment for the Port Hope conversion facility

International Nuclear Information System (INIS)

Garisto, N.C.; Cooper, F.; Janes, A.; Stager, R.; Peters, R.

2011-01-01

The Port Hope Conversion Facility (PHCF) receives uranium trioxide for conversion to uranium hexafluoride (UF 6 ) or uranium dioxide (UO 2 ). The PHCF Site has a long history of industrial use. A Radiological Dose Assessment was undertaken as part of a Site Wide Risk Assessment. This assessment took into account all possible human receptors, both workers and members of the public. This paper focuses on a radiological assessment of dose to members of the public. The doses to members of the public from terrestrial pathways were added to the doses from aquatic pathways to obtain overall dose to receptors. The benchmark used in the assessment is 1 mSv/y. The estimated doses related to PHCF operations are much lower than the dose limit. (author)

Dose assessment for Greifswald and Cadarache

International Nuclear Information System (INIS)

Raskob, W.

1996-07-01

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

Final report on the Project Research 'Assessment of Human Exposure to Environmental Radiation'

International Nuclear Information System (INIS)

1989-03-01

This is the final report of the Project Research, 'Assessment of Human Exposure to Environmental Radiation', which has been conducted during the period 1983-1988. With the objective of assessing risk of environmental radioactivity to the population, the Project was divided into the following five research groups: (1) research for establishing calculation models and parameters in transfer of radionuclides from crop species through the human body; (2) research for analyzing transfer of radionuclides in the ocean and their contributions to exposure doses in the human body; (3) research for surveying accuracy of exposure models for the external body and respiratory organ and the influential factors; (4) research for determining uptake and biokinetics of radionuclides in the body; and (5) research for estimating and evaluating physical and physiological characteristics of reference Japanese man and the populaltion doses. Effluents from nuclear power plants and reprocessing plants were regarded as radionuclide sources in the water and atmosphere. (N.K.)

Development of a methodology for assessing the environmental impact of radioactivity in Northern Marine environments

International Nuclear Information System (INIS)

Brown, J.E.; Hosseini, A.; Borretzen, P.; Thorring, H. . E-mail havard.thorring@nrpa.no

2006-01-01

The requirement to assess the impacts of radioactivity in the environment explicitly and transparently is now generally accepted by the scientific community. A recently developed methodology for achieving this end for marine ecosystems is presented within this paper. With its clear relationship to an overarching system, the marine impact assessment is built around components of environmental transfer, ecodosimetry and radiobiological effects appraisal relying on the use of 'reference organisms'. Concentration factors (CFs), dynamic models and, in cases where parameters are missing, allometry have been employed in the consideration of radionuclide transfer. Dose conversion coefficients (DCCs) have been derived for selected flora and fauna using, inter alia, dose attenuation and chord distribution functions. The calculated dose-rates can be contextualised through comparison with dose-rates arising from natural background and chronic dose-rates at which biological effects have been observed in selected 'umbrella' endpoints

Environmental Impact Assessment: A Procedure.

Science.gov (United States)

Stover, Lloyd V.

Prepared by a firm of consulting engineers, this booklet outlines the procedural "whys and hows" of assessing environmental impact, particularly for the construction industry. Section I explores the need for environmental assessment and evaluation to determine environmental impact. It utilizes a review of the National Environmental Policy Act and…

Radiological risk assessment of environmental radon

Energy Technology Data Exchange (ETDEWEB)

Khalid, Norafatin; Majid, Amran Ab; Yahaya, Redzuwan; Yasir, Muhammad Samudi [Nuclear Science Programme, School of Applied Physics, Faculty of Science and Technology, Universiti Kebangsaan Malaysia, 43600 Bangi, Selangor Darul Ehsan (Malaysia)

2013-11-27

Measurements of radon gas ({sup 222}Rn) in the environmental are important to assess indoor air quality and to study the potential risk to human health. Generally known that exposure to radon is considered the second leading cause of lung cancer after smoking. The environmental radon concentration depends on the {sup 226}Ra concentration, indoor atmosphere, cracking on rocks and building materials. This study was carried out to determine the indoor radon concentration from selected samples of tin tailings (amang) and building materials in an airtight sealed homemade radon chamber. The radiological risk assessment for radon gas was also calculated based on the annual exposure dose, effective dose equivalent, radon exhalation rates and fatal cancer risk. The continuous radon monitor Sun Nuclear model 1029 was used to measure the radon concentration emanates from selected samples for 96 hours. Five types of tin tailings collected from Kampar, Perak and four samples of building materials commonly used in Malaysia dwellings or building constructions were analysed for radon concentration. The indoor radon concentration determined in ilmenite, monazite, struverite, xenotime and zircon samples varies from 219.6 ± 76.8 Bq m{sup −3} to 571.1 ± 251.4 Bq m{sup −3}, 101.0 ± 41.0 Bq m{sup −3} to 245.3 ± 100.2 Bq m{sup −3}, 53.1 ± 7.5 Bq m{sup −3} to 181.8 ± 9.7 Bq m{sup −3}, 256.1 ± 59.3 Bq m{sup −3} to 652.2 ± 222.2 Bq m{sup −3} and 164.5 ± 75.9 Bq m{sup −3} to 653.3 ± 240.0 Bq m{sup −3}, respectively. Whereas, in the building materials, the radon concentration from cement brick, red-clay brick, gravel aggregate and cement showed 396.3 ± 194.3 Bq m{sup −3}, 192.1 ± 75.4 Bq m{sup −3}, 176.1 ± 85.9 Bq m{sup −3} and 28.4 ± 5.7 Bq m{sup −3}, respectively. The radon concentration in tin tailings and building materials were found to be much higher in xenotime and cement brick samples than others. All samples in tin tailings were exceeded the

Environmental impact assessment on the radioactive of a REE separation project

International Nuclear Information System (INIS)

Li Nana; Zhu Yucheng; Cai Minqi

2011-01-01

Based on the investigation of field actual environment and analysis of radioactive sources, and industrial process techniques, environmental impact of the radioactive from a REE separation project has been analyzed, assessed and forecasted. The investigation and monitoring of actual radioactive in the environment indicated that value of assessment factors remained within the range of natural background level as a whole. The maximum annual individual effective dose for occupational worker and the public were forecasted and were found to be 1.622 mSv/a and 0.029 mSv/a respectively. Both of the values are lower than annual dose limit respectively. The radioactive impact of this project on the environment will comply with the standard limit of law and requirements after the reservation measures are carried out to REE. (authors)

Dose assessment in radiological accidents

International Nuclear Information System (INIS)

Donkor, S.

2013-04-01

The applications of ionizing radiation bring many benefits to humankind, ranging from power generation to uses in medicine, industry and agriculture. Facilities that use radiation source require special care in the design and operation of equipment to prevent radiation injury to workers or to the public. Despite considerable development of radiation safety, radiation accidents do happen. The purpose of this study is therefore to discuss how to assess doses to people who will be exposed to a range of internal and external radiation sources in the event of radiological accidents. This will go a long way to complement their medical assessment thereby helping to plan their treatment. Three radiological accidents were reviewed to learn about the causes of those accidents and the recommendations that were put in place to prevent recurrence of such accidents. Various types of dose assessment methods were discussed.(au)

Assessment of radiation doses to the public in areas contaminated by the Fukushima Daiichi Nuclear Power Station accident

International Nuclear Information System (INIS)

Takahara, Shogo; Iijima, Masashi; Shimada, Kazumasa; Kimura, Masanori; Homma, Toshimitsu

2013-01-01

In the areas contaminated by radioactive materials due to the Fukushima Daiichi Nuclear Power Station accident, many residents are exposed to radiation through various exposure pathways. Dose assessment is important for providing appropriate protection to the people and clarifying the impact of the accident. The aim of this study is to provide preliminary results of the assessment of radiation doses received by the inhabitants of Fukushima Prefecture. To assess the doses realistically and comprehensively, a probabilistic approach was adopted using data that reflected realistic environmental trends and lifestyle habits in Fukushima Prefecture. In the first year after the contamination, the 95th percentile of the annual effective dose received by the inhabitants evacuated from the evacuation areas and the deliberate evacuation areas was mainly in the 1-10 mSv dose band. However, the 95th percentile of the dose received by some outdoor workers and inhabitants evacuated from highly contaminated areas was in the 10-50 mSv dose band. The doses due to external exposure to deposited radionuclides were the dominant exposure pathway, and their contributions were about 90% under prevailing contamination conditions in Fukushima Prefecture. In addition, 20%-30% of the lifetime effective dose was delivered during the first year after the contamination. (author)

Non-human biota dose assessment. Sensitivity analysis and knowledge quality assessment

International Nuclear Information System (INIS)

Smith, K.; Robinson, C.; Jackson, D.; La Cruz, I. de; Zinger, I.; Avila, R.

2010-10-01

This report provides a summary of a programme of work, commissioned within the BIOPROTA collaborative forum, to assess the quantitative and qualitative elements of uncertainty associated with biota dose assessment of potential impacts of long-term releases from geological disposal facilities (GDF). Quantitative and qualitative aspects of uncertainty were determined through sensitivity and knowledge quality assessments, respectively. Both assessments focused on default assessment parameters within the ERICA assessment approach. The sensitivity analysis was conducted within the EIKOS sensitivity analysis software tool and was run in both generic and test case modes. The knowledge quality assessment involved development of a questionnaire around the ERICA assessment approach, which was distributed to a range of experts in the fields of non-human biota dose assessment and radioactive waste disposal assessments. Combined, these assessments enabled critical model features and parameters that are both sensitive (i.e. have a large influence on model output) and of low knowledge quality to be identified for each of the three test cases. The output of this project is intended to provide information on those parameters that may need to be considered in more detail for prospective site-specific biota dose assessments for GDFs. Such information should help users to enhance the quality of their assessments and build greater confidence in the results. (orig.)

Estimation of 1945 to 1957 food consumption. Hanford Environmental Dose Reconstruction Project: Draft

Energy Technology Data Exchange (ETDEWEB)

Anderson, D.M.; Bates, D.J.; Marsh, T.L.

1993-03-01

This report details the methods used and the results of the study on the estimated historic levels of food consumption by individuals in the Hanford Environmental Dose Reconstruction (HEDR) study area from 1945--1957. This period includes the time of highest releases from Hanford and is the period for which data are being collected in the Hanford Thyroid Disease Study. These estimates provide the food-consumption inputs for the HEDR database of individual diets. This database will be an input file in the Hanford Environmental Dose Reconstruction Integrated Code (HEDRIC) computer model that will be used to calculate the radiation dose. The report focuses on fresh milk, eggs, lettuce, and spinach. These foods were chosen because they have been found to be significant contributors to radiation dose based on the Technical Steering Panel dose decision level.

Perinatal exposure to low-dose BDE-47, an emergent environmental contaminant, causes hyperactivity in rat offspring.

Science.gov (United States)

Suvorov, Alexander; Girard, Sylvie; Lachapelle, Sophie; Abdelouahab, Nadia; Sebire, Guillaume; Takser, Larissa

2009-01-01

Polybrominated diphenyl ethers (PBDE) are a group of environmental contaminants increasing in North America. Few data are available on neurobehavioral effects at low-dose exposure. Our goal in the present study was to evaluate whether low-dose BDE-47, which is the most abundant PBDE in human samples, affects the neurobehavioral development of rats. Dams were exposed to vehicle or low-dose BDE-47 (0.002, 0.02 and 0.2 mg/kg body weight) each 5 days from gestational day 15 to postnatal day (PND) 20 by intravenous injections. Spontaneous locomotor activity of pups was assessed using the open field test on PND 15, 20 and 25. Sensorimotor coordination was assessed using a RotaRod on PND 30. Exposure to BDE-47 increased locomotor activity of pups. Developmental landmarks and sensorimotor coordination were not influenced by exposure to BDE-47. BDE-47 content in adipose tissue of exposed rats was similar to that known for human populations. These results indicate neurodevelopmental disruption induced in rats by BDE-47 at levels found in the human population.

Parameters used in the environmental pathways and radiological dose modules (DESCARTES, CIDER, and CRD codes) of the Hanford Environmental Dose Reconstruction Integrated Codes (HEDRIC)

International Nuclear Information System (INIS)

Snyder, S.F.; Farris, W.T.; Napier, B.A.; Ikenberry, T.A.; Gilbert, R.O.

1994-05-01

This letter report is a description of work performed for the Hanford Environmental Dose Reconstruction (HEDR) Project. The HEDR Project was established to estimate the radiation doses to individuals resulting from releases of radionuclides from the Hanford Site during the period of 1944 to 1992. This work is being done by staff at Battelle, Pacific Northwest Laboratories under a contract with the Centers for Disease Control and Prevention with technical direction provided by an independent Technical Steering Panel (TSP)

Parameters used in the environmental pathways and radiological dose modules (DESCARTES, CIDER, and CRD codes) of the Hanford Environmental Dose Reconstruction Integrated Codes (HEDRIC)

Energy Technology Data Exchange (ETDEWEB)

Snyder, S.F.; Farris, W.T.; Napier, B.A.; Ikenberry, T.A.; Gilbert, R.O.

1994-05-01

This letter report is a description of work performed for the Hanford Environmental Dose Reconstruction (HEDR) Project. The HEDR Project was established to estimate the radiation doses to individuals resulting from releases of radionuclides from the Hanford Site during the period of 1944 to 1992. This work is being done by staff at Battelle, Pacific Northwest Laboratories under a contract with the Centers for Disease Control and Prevention with technical direction provided by an independent Technical Steering Panel (TSP).

Gonad, bone marrow and effective dose to the population of more than 90 towns and cities of Iran, arising from environmental gamma radiation

International Nuclear Information System (INIS)

Bahreyni Toossi, M. T.; Bayani, Sh.; Yarahmadi, M.; Aghamir, A.; Jomehzadeh, A.; Hagh Parast, M.; Tamjidi, A.

2009-01-01

Since 1996 the assessment of environmental gamma radiation dose in residential areas of Iranian towns and cities has been accomplished for 10 counties. As a practical method and based on the results of a pilot study, in order to attribute the final results to the whole residential area of a town five stations were selected for every town. The location of individual station was studied closely to comply with recommended conditions in the literature. Materials and Methods: RDS-110 was employed to measure gamma dose rate for one hour. Average annual dose rates plus conversion coefficients were employed to estimate gonad, bone marrow, equivalent and effective dose. Result: Minimum and maximum annual bone marrow and gonad dose equivalent attributed to environmental gamma are 0.24 mSvy -1 (for both tissues) and 1.44 and 1.46 mSvy -l , respectively. Conclusion: Average gonad and bone marrow doses for North Khorasan, Boshehr and Hormozgan provinces were less than the corresponding values for normal area.

Howard Hughes Medical Institute dose assessment survey

International Nuclear Information System (INIS)

O'Brien, S.L.; McDougall, M.M.; Barkley, W.E.

1996-01-01

Biomedical science researchers often express frustration that health physics practices vary widely between individual institutions. A survey examining both internal and external dose assessment practices was devised and mailed to fifty institutions supporting biomedical science research. The results indicate that health physics dose assessment practices and policies are highly variable. Factors which may contribute to the degree of variation are discussed. 2 tabs

On - Site Assessment Methods For Environmental Radioactivity

International Nuclear Information System (INIS)

Petrinec, B.; Babic, D.; Bituh, T.

2015-01-01

A method for the rapid determination of radioactivity in cases of release into the environment as well as in cases of nuclear/radiological accidents is described. These measurements would enable a direct risk assessment for humans and biota, without any sampling and at a considerably larger number of locations than in previous studies. Thus obtained, the substantially expanded dataset is expected to shed more light on the properties of environmental radioactivity both in the region studied and in other similar areas. Field measurements will be performed and samples of soil and biota will be collected in order to compare field results with laboratory measurements. Once the method has been validated, previously unexplored locations will be included in the study. Our measurements at numerous locations will also provide control values for comparison in cases of any unplanned or accidental radiological event. An assessment of the possible effects of radionuclide concentrations on the human food chain and biota will be performed within the appropriate models used worldwide exactly for this purpose. In this way, the project should contribute to regional, European, and global efforts towards understanding the radiological impact on ecosystems. Field measurements will also address certain issues in the environmental metrology of radioactive substances, e.g., simultaneous determination of activity concentrations and related dose rates. This will serve as a tool for rapid risk assessment in emergency situations. (author).

Dose assessment in the Marshall Islands

International Nuclear Information System (INIS)

Robison, William L.

1978-01-01

Bikini Atoll and Enewetak Atoll in the Marshall Islands were the sites of major U.S. weapons testing from 1948 through 1958. Both the Bikini and Knewetak people have expressed a desire to return to their native Atolls. In 1968 clean-up and resettlement of Bikini was begun. In 1972-73 the initial survey of Enewetak Atoll was conducted and clean-up began in 1977. Surveys have been conducted at both Atolls to establish the concentrations of radionuclides in the biota and to determine the external exposure rates. Subsequent to the surveys dose assessments have been made to determine the potential dose to returning (100) populations at both Atolls. This talk will include discussions of the relative importance of the critical exposure pathways (i.e., external exposure, inhalation, marine, terrestrial and drinking water), the predominant radionuclides contributing to the predicted doses for each pathway, the doses predicted for alternate living patterns, comparison to Federal Guidelines, the comparison between Atolls, some of the social problems created by adherence to Federal Guidelines and the follow-up research identified and initiated to help refine the dose assessments and better predict the long term use of the Atolls (86). (author)

Inhalation dose assessment for Maralinga and Emu

International Nuclear Information System (INIS)

Johnston, P.N.; Lokan, K.H.; Williams, G.A.

1990-01-01

Dose assessments for the inhalation of artificial radionuclides are presented for all types of contaminated areas at Maralinga and Emu. These enable Committed Effective Dose Equivalent (CEDE), to be estimated by scaling at any area of interest where activity concentrations are known. In the case of Aborigines, these dose are estimated assuming respirable dust loadings of 1 mg/m 3 for adults and 1.5 mg/m 3 for children and infants. Details of the calculations are presented in the appendix. The model of the respiratory system used in this assessment is that described in Interantional Commission on Radiological Protection (ICRP) Publication 30 (ICRP, 1979a). With the exception of Kuli, which is contaminated with uranium, at all other sites it is only the inhalation of plutonium and americium that contributes significantly to the dose, and of these 239 Pu is the largest contributor. Therefore, considering the long half lives of the radionuclides concerned, it appears that the inhalation problems highlighted by this dose assessment will not diminish significantly within any reasonable period of time and hence management strategies must be developed to deal with such problems. 32 refs., 5 tabs., 1 fig

Fuels and Materials Examination Facility: Environmental assessment, Hanford site, Richland, Washington: Environmental assessment

International Nuclear Information System (INIS)

1980-07-01

The Fuels and Materials Examination Facility (FMEF) and the High Performance Fuel Laboratory (HPFL) were originally proposed to be constructed as separate facilities in the 400 Area of the Hanford Site near Richland, Washington. The environmental effects of these two facilities were described and evaluated in the FMEF Environmental Assessment and the HPFL Final Environmental Impact Statement, ERDA-1550. For economic reasons, the two facilities will no longer be built as separate facilities. The FMEF facility plans have been modified to incorporate some of the features of the proposed HPFL facility while retaining essentially all of the capabilities of the original FMEF proposal. The purpose of this document is to update the FMEF Environmental Assessment to appropriately reflect addition of certain HPFL features into the FMEF facility and to assess the environmental affects of the facility which resulted from inclusion of HPFL features into the FMEF facility

Effective dose due to environmental γ-ray for the people of Akita prefecture

International Nuclear Information System (INIS)

Yamashita, Junsuke; Watarai, Jiro; Hisamatsu, Shun'ichi

2001-01-01

Environmental γ-ray doses were measured in Akita prefecture by a NaI(Tl) scintillation surveymeter. The numbers of measurement site were 207 on pavement, 45 on unpaved ground, nine in concrete buildings and nine in wooden houses. The results of measurements, which were subtracted for background (cosmic ray and self-irradiation of the surveymeter), were 31 nSv/h (effective dose rate) on pavement, 27 nSv/h on unpaved ground, 65 nSv/h in the concrete buildings and 34 nSv/h in the wooden houses. The effective dose rate due to environmental γ-ray for the people of Akita prefecture was estimated taking into account of seasonal change of the dose rate at one site and occupancy factor in the prefecture. The outdoor and indoor dose rates were estimated to be 0.03 mSv/y and 0.33 mSv/y, respectively. (author)

Food-chain and dose model, CALDOS, for assessing Canada's Nuclear Fuel Waste Management concept

International Nuclear Information System (INIS)

Zach, R.; Sheppard, S.C.

1991-01-01

The food-chain and dose model, CALculation of DOSe (CALDOS), was developed for assessing Canada's concept for nuclear fuel waste disposal in a vault deep in crystalline rock of the Canadian Shield. The model is very general and based on the Shield as a whole. The critical group is totally self-sufficient and represented by ICRP (1975) Reference Man for dose prediction. CALDOS assumes steady-state conditions and deals with variation and uncertainty through Monte Carlo simulation techniques. Ingrowth of some radioactive daughters is considered during food-chain transfer. A limit is set on root uptake to avoid unrealistic plant concentrations. Integrated ingestion and inhalation rates of man are calculated in a unique way, based on energy needs. Soil ingestion by man and external exposure from building material are unique pathways considered. Tritium, 129 I, and 222 Rn are treated through special models, and 14 C and 129 I involve unique geosphere dose limits. All transfer coefficients are lognormally distributed, and the plant/soil concentration ratio is correlated with the soil partition coefficient. Animals' ingestion rates are normally distributed and correlated with each other. Comprehensive sets of internal and external dose conversion factors were calculated for CALDOS. Sample calculations show that dose distributions tend to be strongly right-skewed. Many features of CALDOS are relevant for environmental assessment in general

Integration of models for the Hanford Environmental Dose Reconstruction Project

International Nuclear Information System (INIS)

Napier, B.A.

1991-01-01

The objective of the Hanford Environmental Dose Reconstruction Project is to estimate the radiation dose that individuals could have received as a result of emissions from nuclear operations at Hanford since 1944. The objective of phase 1 of the project was to demonstrate through calculations that adequate models and support data exist or could be developed to allow realistic estimations of doses to individuals from releases of radionuclides to the environment that occurred as long as 45 years ago. Much of the data used in phase 1 was preliminary; therefore, the doses calculated must be considered preliminary approximations. This paper describes the integration of various models that was implemented for initial computer calculations. Models were required for estimating the quantity of radioactive material released, for evaluating its transport through the environment, for estimating human exposure, and for evaluating resultant doses

Environmental Management Assessment of the Fernald Environmental Management Project (FEMP)

Energy Technology Data Exchange (ETDEWEB)

1993-04-01

This report documents the results of the Environmental Management Assessment performed at the Fernald Environmental Management Project (FEMP) in Fernald, Ohio. During this assessment, the activities conducted by the assessment team included review of internal documents and reports from previous audits and assessments; interviews with US Department of Energy (DOE) and FEMP contractor personnel; and inspection and observation of selected facilities and operations. The onsite portion of the assessment was conducted from March 15 through April 1, 1993, by DOE`s Office of Environmental Audit (EH-24) located within the Office of the Assistant Secretary for Environment, Safety, and Health (EH-1). EH-24 carries out independent assessments of DOE facilities and activities as part of the EH-1 Environment, Safety, and Health (ES&H) Oversight Audit Program. The EH-24 program is designed to evaluate the status of DOE facilities and activities with respect to compliance with Federal, state, and local environmental laws and regulations; compliance with DOE Orders, Guidance and Directives; conformance with accepted industry practices and standards of performance; and the status and adequacy of management systems developed to address environmental requirements. The Environmental Management Assessment of FEMP focused on the adequacy of environmental management systems. Further, in response to requests by the Office of Environmental Restoration and Waste Management (EM) and Fernald Field Office (FN), Quality Assurance and Environmental Radiation activities at FEMP were evaluated from a programmatic standpoint. The results of the evaluation of these areas are contained in the Environmental Protection Programs section in this report.

Environmental Management Assessment of the Fernald Environmental Management Project (FEMP)

International Nuclear Information System (INIS)

1993-04-01

This report documents the results of the Environmental Management Assessment performed at the Fernald Environmental Management Project (FEMP) in Fernald, Ohio. During this assessment, the activities conducted by the assessment team included review of internal documents and reports from previous audits and assessments; interviews with US Department of Energy (DOE) and FEMP contractor personnel; and inspection and observation of selected facilities and operations. The onsite portion of the assessment was conducted from March 15 through April 1, 1993, by DOE's Office of Environmental Audit (EH-24) located within the Office of the Assistant Secretary for Environment, Safety, and Health (EH-1). EH-24 carries out independent assessments of DOE facilities and activities as part of the EH-1 Environment, Safety, and Health (ES ampersand H) Oversight Audit Program. The EH-24 program is designed to evaluate the status of DOE facilities and activities with respect to compliance with Federal, state, and local environmental laws and regulations; compliance with DOE Orders, Guidance and Directives; conformance with accepted industry practices and standards of performance; and the status and adequacy of management systems developed to address environmental requirements. The Environmental Management Assessment of FEMP focused on the adequacy of environmental management systems. Further, in response to requests by the Office of Environmental Restoration and Waste Management (EM) and Fernald Field Office (FN), Quality Assurance and Environmental Radiation activities at FEMP were evaluated from a programmatic standpoint. The results of the evaluation of these areas are contained in the Environmental Protection Programs section in this report

ASSESSING CHILDREN'S EXPOSURES TO PESTICIDES: AN IMPORTANT APPLICATION OF THE STOCHASTIC HUMAN EXPOSURE AND DOSE SIMULATION MODEL (SHEDS)

Science.gov (United States)

Accurately quantifying human exposures and doses of various populations to environmental pollutants is critical for the Agency to assess and manage human health risks. For example, the Food Quality Protection Act of 1996 (FQPA) requires EPA to consider aggregate human exposure ...

The methodology of environmental impacts assessment of environmentally hazardous facilities

OpenAIRE

Adamenko, Yaroslav

2017-01-01

The article deals with the methodology of environmental impacts assessment of environmentally hazardous facilities and activities. The stages of evaluation of environmental impacts are proved. The algorithm and technology of decision-making in the system of environmental impact assessments based on a multi-criteria utility theory are proposed.

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

Energy Technology Data Exchange (ETDEWEB)

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

2002-11-01

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

Bio-indicators for radiation dose assessment

International Nuclear Information System (INIS)

Trivedi, A.

1990-12-01

In nuclear facilities, such as Chalk River Laboratories, dose to the atomic radiation workers (ARWs) is assessed routinely by using physical dosimeters and bioassay procedures in accordance with regulatory recommendations. However, these procedures may be insufficient in some circumstances, e.g., in cases where the reading of the physical dosimeters is questioned, in cases of radiation accidents where the person(s) in question was not wearing a dosimeter, or in the event of a radiation emergency when an exposure above the dose limits is possible. The desirability of being able to assess radiation dose on the basis of radio-biological effects has prompted the Dosimetric Research Branch to investigate the suitability of biological devices and techniques that could be used for this purpose. Current biological dosimetry concepts suggest that there does not appear to be any bio-indicator that could reliably measure the very low doses that are routinely measured by the physical devices presently in use. Nonetheless, bio-indicators may be useful in providing valuable supplementary information in cases of unusual radiation exposures, such as when the estimated body doses are doubtful because of lack of proper physical measurements, or in cases where available results need to be confirmed for medical treatment plannings. This report evaluates the present state of biological dosimetry and, in particular, assesses the efficiency and limits of individual indicators. This has led to the recommendation of a few promising research areas that may result in the development of appropriate biological dosimeters for operational and emergency needs at Chalk River

Assessment of the environmental impact of plutonium transport within the European Community

International Nuclear Information System (INIS)

1978-11-01

Assessment is given of the environmental impact of plutonium transport within the European Community in the 1990's. This includes shipments of plutonium, raw materials, fresh and spent mixed oxide fuel assemblies and plutonium contaminated solid wastes. The consequences on general traffic, the radiation doses to transport workers and the general public and the heat release during transport are presented

An updated dose assessment for a U.S. Nuclear Test Site - Bikini Atoll

International Nuclear Information System (INIS)

Robison, W.L.; Bogen, K.T.; Conrado, C.L.

1995-10-01

On March 1, 1954, a nuclear weapon test, code-named BRAVO, conducted at Bikini Atoll in the northern Marshall Islands contaminated the major residence island. There has been a continuing effort since 1977 to refine dose assessments for resettlement options at Bikini Atoll. Here we provide a radiological dose assessment for the main residence island, Bikini, using extensive radionuclide concentration data derived from analysis of food crops, ground water, cistern water, fish and other marine species, animals, air, and soil collected at Bikini Island as part of our continuing research and monitoring program that began in 1975. The unique composition of coral soil greatly alters the relative contribution of cesium-137 ( 137 Cs) and strontium-90 ( 90 Sr) to the total estimated dose relative to expectations based on North American and European soils. Without counter measures, cesium-137 produces 96% of the estimated dose for returning residents, mostly through uptake from the soil to terrestrial food crops but also from external gamma exposure. The doses are calculated assuming a resettlement date of 1999. The estimated maximum annual effective dose for current island conditions is 4.0 mSv when imported foods, which are now an established part of the diet, are available. The corresponding 30-, 50-, and 70-y integral effective doses are 9.1 cSv, 13 cSv, and 15 cSv, respectively. A corresponding uncertainty analysis showed that after about 5 y of residence, the 95% confidence limits on population-average dose would be ±35% of its expected value. We have evaluated various countermeasures to reduce 137 Cs in food crops. Treatment with potassium reduces the uptake of 137 Cs into food crops, and therefore the ingestion dose, to about 5% of pretreatment levels and has essentially no negative environmental consequences

Spherical ionization chamber of 14 liter for precise measurement of environmental radiation dose rate

International Nuclear Information System (INIS)

Nagaoka, Toshi; Saito, Kimiaki; Moriuchi, Shigeru

1991-05-01

A spherical ionization chamber of 14 liter filled with 1 atm. nitrogen gas was arranged aiming at precise measurement of dose rate due to environmental gamma rays and cosmic rays. Ionization current-dose rate conversion factor for this ionization chamber was derived from careful consideration taking into account the attenuation by chamber wall, ionization current due to alpha particles and so on. Experiments at calibrated gamma ray fields and intercomparison with NaI(Tl) scintillation detector were also performed, which confirmed this ionization chamber using the conversion factor can measure the dose rate with an error of only a few percent. This ionization chamber will be used for measurement of environmental gamma ray and cosmic ray dose rate. (author)

Outdoor and indoor dose assessment using environmental thermoluminescence dosimeters (TLDs) in Costa Rica

International Nuclear Information System (INIS)

Mora, Patricia

2003-01-01

Costa Rica lies at the intersection of the Cocos and Caribbean plates in Central America. It has mountain ranges with many active volcanoes along its territory. Its soils are predominantly of volcanic origin. Natural radiation measurements utilising environmental CaF 2 :Dy thermoluminescence dosimeters were used for the first time in Costa Rica by the Dosimetry Section of the Atomic, Nuclear and Molecular Sciences Research Center of the University of Costa Rica. Seven hundred outdoor measurements were obtained in a 3.5-year period at eight different sites throughout the country. One hundred and seventy-four indoor readings were also collected at four sites for a 2-year period. Population-weighted averages give 82 nGy h -1 for outdoors and 130 nGy h -1 for indoors. The values lie on the upper range of worldwide reported values due to reported soil characteristics rich in uranium and potassium. A preliminary population-weighted value of 0.74 mSv/year for the effective dose is calculated for natural terrestrial gamma radiation in Costa Rica

In situ assessment of genotoxic hazards of environmental pollution.

Science.gov (United States)

Sandhu, S S; Lower, W R

1989-01-01

mutagenic and neoplastic effects on aquatic animals from coastal areas and continental rivers, lakes, and ponds. The limitations of in situ environmental assessment are lack of control over the physical environmental components, inherent variability and interactions of test organisms, lack of control of exposure doses, and difficulty of finding concurrent experimental controls. Nevertheless, flowering plants, terrestrial, and aquatic animals may serve as useful sentinels and biomarkers of environmental pollution.

Environmental impacts assessment: Instruments for environmental policy making and resource management

International Nuclear Information System (INIS)

Cavelli, C.M.; Sartori, S.

1993-06-01

This review of evaluation criteria for environmental impacts assessments in Italy covers the following aspects: the efficacy of current Italian normatives governing assessment methods, the current approach of regional public administrations, the necessity for the creation of a national regulating board, environmental impacts assessment for complex environmental systems, the application of impacts assessment recommendations to resource development modelling in the planning of integrated environmental-economic systems, the involvement of the general public in decision making, techniques to determine the monetary worth of environmental resources, the use of multi-criteria analysis techniques

Long-term intercomparison of Spanish environmental dosimetry services. Study of transit dose estimations

International Nuclear Information System (INIS)

Duch, Ma Amor; Carlos Saez-Vergara, Jose; Ginjaume, Merce; Gomez, Candelas; Maria Gonzalez-Leiton, Ana; Herrero, Javier; Jose de Lucas, Ma; Rodriguez, Rafael; Marugan, Immaculada; Salas, Rosario

2008-01-01

This paper presents the layout and results of a three-year follow-up of a national intercomparison campaign organized on a voluntary basis among the Spanish Laboratories in charge of environmental monitoring at and in the vicinity of Spanish nuclear installations. The dosemeters were exposed in the field at an environmental reference station with a known ambient dose equivalent, and controlled meteorological parameters. The study aimed at verifying the consistency of the different laboratories in estimating the ambient dose equivalent in realistic fields and to evaluate the influence of two different procedures to estimate the transit dose during the transfer of the dosemeters both from and to the dosimetric laboratory and the monitored site. All the results were within 20% of the reference doses for all the dosemeters tested, and in most cases they were within 10%

Environmental assessment of lightweight electric vehicles

CERN Document Server

Egede, Patricia

2017-01-01

This monograph adresses the challenge of the environmental assessment of leightweight electric vehicles. It poses the question whether the use of lightweight materials in electric vehicles can reduce the vehicles’ environmental impact and compares the environmental performance of a lightweight electric vehicle (LEV) to other types of vehicles. The topical approach focuses on methods from life cycle assessment (LCA), and the book concludes with a comprehensive concept on the environmental assessment of LEVs. The target audience primarily comprises LCA practitioners from research institutes and industry, but it may also be beneficial for graduate students specializing in the field of environmental assessment.

7 CFR 1955.136 - Environmental Assessment (EA) and Environmental Impact Statement (EIS).

Science.gov (United States)

2010-01-01

... 7 Agriculture 14 2010-01-01 2009-01-01 true Environmental Assessment (EA) and Environmental Impact... Disposal of Inventory Property General § 1955.136 Environmental Assessment (EA) and Environmental Impact Statement (EIS). (a) Prior to a final decision on some disposal actions, an environmental assessment must be...

ENVIRONMENTAL IMPACT ASSESSMENT AND MONITORING ...

African Journals Online (AJOL)

protect the environment, it is imperative to conduct environmental impact assessment ... Ethiopia enacted the Environmental Impact Assessment Proclamation in 2002 ... flora, fauna, soil, air, water, climate, natural or cultural heritage, other.

Comparison of environmental radiation doses estimated for Hanford Operations, 1977 through 1982

International Nuclear Information System (INIS)

McCormack, W.D.; Carlile, J.M.V.; Peloquin, R.A.; Napier, B.A.

1983-12-01

Offsite environmental radiation dose equivalents based on Hanford operations are compared for the years 1977 through 1981 to those calculated for 1982. The comparison revealed a downward trend in calculated offsite doses over the period 1977 through 1982, due primarily to reported reduced effluent releases, changes in effluent reporting methods, and increased Columbia River flow over this period. The calculated doses verify the surveillance program findings that potential offsite radiation doses due to Hanford Operations are small and well below our ability to detect in the environment. 11 references, 23 tables

Environmental contaminants: assessment and control

National Research Council Canada - National Science Library

Vallero, Daniel A

2004-01-01

... Understanding Policy by Understanding Science Connections and Interrelationships of Environmental Science Environmental Assessment and Intervention Engineering Technical Note: Cleaning up a Hazardous Waste Site Social Aspects of Environmental Science Introduction to Environmental Policy The National Environmental Policy Act Issues in Environmental Science: Co...

Environmental assessment in the uranium industry

International Nuclear Information System (INIS)

Frost, S.E.

2002-01-01

The paper examines the subject matter to be dealt with in environmental impact assessments for uranium production facilities, the development of environmental impact statements and the processes used for assessing projects. Different types of regulatory process used to assess projects are described, using Canadian and Australian examples. Some of the techniques used in developing environmental assessments are described. Public participation, including that of special interest groups, is discussed. Some examples of assessments are examined, particularly looking at recent assessments for uranium mining projects in Canada. Trends in environmental assessment are described, using examples from a number of different projects over the past 25 years. Some recommendations for the future are offered. (author)

Environmental assessment in the uranium industry

International Nuclear Information System (INIS)

Frost, S.E.

2000-01-01

The paper examines the subject matter to be dealt with in environmental impact assessments for uranium production facilities, the development of environmental impact statements and the processes used for assessing projects. Different types of regulatory process used to assess projects are described, using Canadian and Australian examples. Some of the techniques used in developing environmental assessments are described. Public participation, including that of special interest groups, is discussed. Some examples of assessments are examined, particularly looking at recent assessments for uranium mining projects in Canada. Trends in environmental assessment are described, using examples from a number of different projects over the past 25 years. Some recommendations for the future are offered. (author)

Environmental and biological monitoring in the estimation of absorbed doses of pesticides.

Science.gov (United States)

Aprea, Maria Cristina

2012-04-25

Exposure to pesticides affects most of the population, not only persons occupationally exposed. In a context of high variability of exposure, biological monitoring is important because of the various routes by which exposure can occur and because it assesses both occupational and non-occupational exposure. The main aim of this paper was to critically compare estimates of absorbed dose measured by environmental and biological monitoring in situations in which they could both be applied. The combination of exposure measurements and biological monitoring was found to provide extremely important information on the behaviour of employees, and on the proper use and effectiveness of personal protection equipment. Copyright © 2011 Elsevier Ireland Ltd. All rights reserved.

Dose assessment for brachytherapy with Henschke applicator

International Nuclear Information System (INIS)

Yu, Pei-Chieh; Chao, Tsi-Chian; Tung, Chuan-Jong; Wu, Ching-Jung; Lee, Chung-Chi

2011-01-01

Dose perturbation caused by the Henschke applicator is a major concern for the brachytherapy planning system (BPS) in recent years. To investigate dose impact owing to neglect of the metal shielding effect, Monte Carlo (MC) simulation, BPS calculation, and film measurement have been performed for dose assessment in a water phantom. Additionally, a cylindrical air cavity representing the rectum was added into the MC simulation to study its effect on dose distribution. Monte Carlo N-Particle Transport Code (MCNP) was used in this study to simulate the dose distribution using a mesh tally. This Monte Carlo simulation has been validated using the TG-43 data in a previous report. For the measurement, the Henschke applicator was placed in a specially-designed phantom, and Gafchromic films were inserted in the center plane for 2D dose assessment. Isodose distributions with and without the Henschke applicator by the MC simulation show significant deviation from those by the BPS. For MC simulation, the isodose curves shrank more significantly when the metal applicator was applied. For the impact of the added air cavity, the results indicate that it is hard to distinguish between with and without the cavity. Thus, the rectum cavity has little impact on the dose distribution around the Henschke applicator.

Indoor aerosol modeling for assessment of exposure and respiratory tract deposited dose

Science.gov (United States)

Hussein, Tareq; Wierzbicka, Aneta; Löndahl, Jakob; Lazaridis, Mihalis; Hänninen, Otto

2015-04-01

Air pollution is one of the major environmental problems that influence people's health. Exposure to harmful particulate matter (PM) occurs both outdoors and indoors, but while people spend most of their time indoors, the indoor exposures tend to dominate. Moreover, higher PM concentrations due to indoor sources and tightness of indoor environments may substantially add to the outdoor originating exposures. Empirical and real-time assessment of human exposure is often impossible; therefore, indoor aerosol modeling (IAM) can be used as a superior method in exposure and health effects studies. This paper presents a simple approach in combining available aerosol-based modeling techniques to evaluate the real-time exposure and respiratory tract deposited dose based on particle size. Our simple approach consists of outdoor aerosol data base, IAM simulations, time-activity pattern data-base, physical-chemical properties of inhaled aerosols, and semi-empirical deposition fraction of aerosols in the respiratory tract. These modeling techniques allow the characterization of regional deposited dose in any metric: particle mass, particle number, and surface area. The first part of this presentation reviews recent advances in simple mass-balance based modeling methods that are needed in analyzing the health relevance of indoor exposures. The second part illustrates the use of IAM in the calculations of exposure and deposited dose. Contrary to previous methods, the approach presented is a real-time approach and it goes beyond the exposure assessment to provide the required information for the health risk assessment, which is the respiratory tract deposited dose. This simplified approach is foreseen to support epidemiological studies focusing on exposures originating from both indoor and outdoor sources.

Disequilibrium implications on dose assessment in the use of NORM as building material

International Nuclear Information System (INIS)

Rosa, R.; Amaral, E.C.S.

2002-01-01

The need of reusing industrial wastes to avoid environmental impact resulting from their deposition and to reduce the management costs, indicates the building industry as an important user of large quantities of industrial wastes, mainly those generated in the ore milling. The industry of phosphate fertilizers is a typical example of this situation. The phosphate rock contains radionuclides of the U and Th decay series. During the chemical attack these radionuclides are distributed in different proportions between the phosphoric acid and the phosphogypsum, depending on the process. Several countries adopt a methodology based on the Ra-226, Th-232 and K-40 content in order to allow the use of materials with natural radionuclides. Dose assessment for the use of phosphogypsum as building material have shown that methodology is not adequate when disequilibrium exists. This paper will present some implications on dose assessment and on the use of that methodology when disequilibrium exists, using two phosphogypsum radionuclides distribution patterns obtained through different milling processes in Brazil. (author)

Biota dose assessment of small mammals sampled near uranium mines in northern Arizona

Energy Technology Data Exchange (ETDEWEB)

Jannik, T. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Minter, K. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Kuhne, W. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Kubilius, W. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2018-01-09

In 2015, the U. S. Geological Survey (USGS) collected approximately 50 small mammal carcasses from Northern Arizona uranium mines and other background locations. Based on the highest gross alpha results, 11 small mammal samples were selected for radioisotopic analyses. None of the background samples had significant gross alpha results. The 11 small mammals were identified relative to the three ‘indicator’ mines located south of Fredonia, AZ on the Kanab Plateau (Kanab North Mine, Pinenut Mine, and Arizona 1 Mine) (Figure 1-1) and are operated by Energy Fuels Resources Inc. (EFRI). EFRI annually reports soil analysis for uranium and radium-226 using Arizona Department of Environmental Quality (ADEQ)-approved Standard Operating Procedures for Soil Sampling (EFRI 2016a, 2016b, 2017). In combination with the USGS small mammal radioiosotopic tissue analyses, a biota dose assessment was completed by Savannah River National Laboratory (SRNL) using the RESidual RADioactivity-BIOTA (RESRAD-BIOTA, V. 1.8) dose assessment tool provided by the Argonne National Laboratory (ANL 2017).

Uncertainties in environmental impact assessments due to expert opinion. Case study. Radioactive waste in Slovenia

International Nuclear Information System (INIS)

Kontic, B.; Ravnik, M.

1998-01-01

A comprehensive study was done at the J. Stefan Institute in Ljubljana and the School of Environmental Sciences in Nova Gorica in relation to sources of uncertainties in long-term environmental impact assessment (EIA). Under the research two main components were examined: first, methodology of the preparation of an EIA, and second validity of an expert opinion. Following the findings of the research a survey was performed in relation to assessing acceptability of radioactive waste repository by the regulatory. The components of dose evaluation in different time frames were examined in terms of susceptibility to uncertainty. Uncertainty associated to human exposure in the far future is so large that dose and risk, as individual numerical indicators of safety, by our opinion, should not be used in compliance assessment for radioactive waste repository. On the other hand, results of the calculations on the amount and activity of low and intermediate level waste and the spent fuel from the Krsko NPP show that expert's understanding of the treated questions can be expressed in transparent way giving credible output of the models used.(author)

Advancing Dose-Response Assessment Methods for Environmental Regulatory Impact Analysis: A Bayesian Belief Network Approach Applied to Inorganic Arsenic.

Science.gov (United States)

Zabinski, Joseph W; Garcia-Vargas, Gonzalo; Rubio-Andrade, Marisela; Fry, Rebecca C; Gibson, Jacqueline MacDonald

2016-05-10

Dose-response functions used in regulatory risk assessment are based on studies of whole organisms and fail to incorporate genetic and metabolomic data. Bayesian belief networks (BBNs) could provide a powerful framework for incorporating such data, but no prior research has examined this possibility. To address this gap, we develop a BBN-based model predicting birthweight at gestational age from arsenic exposure via drinking water and maternal metabolic indicators using a cohort of 200 pregnant women from an arsenic-endemic region of Mexico. We compare BBN predictions to those of prevailing slope-factor and reference-dose approaches. The BBN outperforms prevailing approaches in balancing false-positive and false-negative rates. Whereas the slope-factor approach had 2% sensitivity and 99% specificity and the reference-dose approach had 100% sensitivity and 0% specificity, the BBN's sensitivity and specificity were 71% and 30%, respectively. BBNs offer a promising opportunity to advance health risk assessment by incorporating modern genetic and metabolomic data.

Environmental aspects of commercial radioactive waste management

International Nuclear Information System (INIS)

1979-05-01

Volume 3 contains eight appendices: a reference environment for assessing environmental impacts associated with construction and operation of waste treatment, interim storage and/or final disposition facilities; dose calculations and radiologically related health effects; socioeconomic impact assessments; release/dose factors and dose in 5-year intervals to regional and world wide population from reference integrated systems; resource availability; environmental monitoring; detailed dose results for radionuclide migration groundwater from a waste repository; and annual average dispersion factors for selected release points

Environmental aspects of commercial radioactive waste management

Energy Technology Data Exchange (ETDEWEB)

1979-05-01

Volume 3 contains eight appendices: a reference environment for assessing environmental impacts associated with construction and operation of waste treatment, interim storage and/or final disposition facilities; dose calculations and radiologically related health effects; socioeconomic impact assessments; release/dose factors and dose in 5-year intervals to regional and world wide population from reference integrated systems; resource availability; environmental monitoring; detailed dose results for radionuclide migration groundwater from a waste repository; and annual average dispersion factors for selected release points. (LK)

FY 1992 revised task plans for the Hanford Environmental Dose Reconstruction Project

International Nuclear Information System (INIS)

Shipler, D.B.

1992-04-01

The purpose of the Hanford Environmental Dose Reconstruction (HEDR) Project is to estimate radiation doses from Hanford Site operations since 1944 to populations and individuals. The primary objectives of work to be performed in FY 1992 is to determine the appropriate scope (space, time, and radionuclides, pathways and individuals/population groups) and accuracy (level of uncertainty in dose estimates) for the project. Another objective is to use a refined computer model to estimate Native American tribal doses and individual doses for the Hanford Thyroid Disease Study (HTDS). Project scope and accuracy requirements defined in FY 1992 can translated into model and data requirements that must be satisfied during FY 1993

Communication tools for the Hanford Environmental Dose Reconstruction Project

International Nuclear Information System (INIS)

Blazek, Mary Lou; Power, Max S.

1992-01-01

From 1944 to 1989, the U.S. Department of Energy produced plutonium at the Hanford Site in southeast Washington State. In the early days of operation, large amounts of radioactive materials were released to the environment. Documents about the releases were made public in 1986. The Hanford Environmental Dose Reconstruction Project began in 1987. The Project will determine how much radioactive material was released, how that material may have exposed people, and what radiation doses people may have received. The Project will be complete in 1995. The federal government pays for the work. The scientific work on the study is done by Battelle's Pacific Northwest Laboratory. Public credibility and valid science are equally important to those directing the dose reconstruction work. A number of tools are used to inform the public and encourage public participation. These tools are examined in this paper. (author)

Environmental impact assessment: use of literature data versus use of specific local and regional data

International Nuclear Information System (INIS)

Rochedo, Elaine R.R.; Wasserman, Maria Angelica

2000-01-01

The environmental radiological impact assessment methodology includes a large number of parameters to simulate the environmental transfer and population exposure. Local and regional data are often not available, particularly for tropical regions, which leads to the use of literature data, mostly determined at temperate climate countries. Since 1993, IRD has been developing radioecological studies aiming the determination soil-plant transfer factors, which showed the possibility of finding values up to one order of magnitude higher than those found at temperate climate countries literature. This paper compares dose results for several scenarios, using regional and literature data, assessing the relevance of using site specific data for radiological impact assessments, for both practices and intervention situations. (author)

Environmental impact assessment screening tool

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-05-01

An environmental assessment and impact planning software, SCREENER, was tested at a pilot project at the Cameco site (Port Hope). SCREENER was used to screen the impacts of a new construction project in accordance with the process and reporting requirements laid out in the Canadian Environmental Assessment Act. The software test concentrated on the activities that are directly involved with the structure construction and site preparation activities. In addition, a two and one half day training course was given to three AECB staff using the test case as a hands on example. The conclusion of this project is that an automated tool such as SCREENER (or Calyx, the new generation of environmental assessment tools from ESSA Software Ltd.), will help the AECB to standardize the approach to environmental assessment, assist in project planning, and save resources in the screening process. The new approach could allow to allocate AECB limited resources to the detailed assessments required for maximum impact activities. 2 figs. 7 refs.

Environmental impact assessment screening tool

International Nuclear Information System (INIS)

1995-05-01

An environmental assessment and impact planning software, SCREENER, was tested at a pilot project at the Cameco site (Port Hope). SCREENER was used to screen the impacts of a new construction project in accordance with the process and reporting requirements laid out in the Canadian Environmental Assessment Act. The software test concentrated on the activities that are directly involved with the structure construction and site preparation activities. In addition, a two and one half day training course was given to three AECB staff using the test case as a hands on example. The conclusion of this project is that an automated tool such as SCREENER (or Calyx, the new generation of environmental assessment tools from ESSA Software Ltd.), will help the AECB to standardize the approach to environmental assessment, assist in project planning, and save resources in the screening process. The new approach could allow to allocate AECB limited resources to the detailed assessments required for maximum impact activities

Decision management for the Hanford Environmental Dose Reconstruction Project

Energy Technology Data Exchange (ETDEWEB)

Roberds, W.J.; Haerer, H.A. [Golder Associates, Inc., Redmond, WA (United States); Winterfeldt, D.V. [Decision Insights, Laguna Beach, CA (United States)

1992-04-01

The Hanford Environmental Dose Reconstruction (HEDR) Project is in the process of developing estimates for the radiation doses that individuals and population groups may have received as a result of past activities at the Hanford Reservation in Eastern Washington. A formal decision-aiding methodology has been developed to assist the HEDR Project in making significant and defensible decisions regarding how this study will be conducted. These decisions relate primarily to policy (e.g., the appropriate level of public participation in the study) and specific technical aspects (e.g., the appropriate domain and depth of the study), and may have significant consequences with respect to technical results, costs, and public acceptability.

Decision management for the Hanford Environmental Dose Reconstruction Project

International Nuclear Information System (INIS)

Roberds, W.J.; Haerer, H.A.; Winterfeldt, D.V.

1992-04-01

The Hanford Environmental Dose Reconstruction (HEDR) Project is in the process of developing estimates for the radiation doses that individuals and population groups may have received as a result of past activities at the Hanford Reservation in Eastern Washington. A formal decision-aiding methodology has been developed to assist the HEDR Project in making significant and defensible decisions regarding how this study will be conducted. These decisions relate primarily to policy (e.g., the appropriate level of public participation in the study) and specific technical aspects (e.g., the appropriate domain and depth of the study), and may have significant consequences with respect to technical results, costs, and public acceptability

Biological dose assessment of 15 victims in Haerbin radiation accident

International Nuclear Information System (INIS)

Liu, Jian-xiang; Huang, Min-yan; Ruan, Jian-lei; Bai, Yu-shu; Xu, Su

2008-01-01

Full text: a) On July 5 and 8, 2005, Two patients with bone marrow suppression were successively hospitalized by the First Affiliated Hospital of Haerbin Medical University. Examination results showed that the patients seemed to get suspicious radiation disease. On July 13, 2005, a radioactive source was found in the patients' dwelling. The radiation source is Iridium-192 with 0.5 Ci(1.85 x 10 10 Bq) radioactivity. The radiation source is a metal bar which is a kind of radioactive industrial detection source for welding. The source is currently stored in the urban radioactive waste storehouse of Heilongjiang province. After finding the radioactive source on July 13, The Haerbin municipal government initiated an emergency response plan and developed medical rescue, radioactive source examination and case detection through organizing ministries involving health, environmental protection and public security. After receiving a report at 17:00 on July 14, 2005, Chinese Ministry of Health immediately sent experts to the spot for investigation, dose estimation and direction of patients' rescue. Health authority carried out physical examination twice on 113 residents within 30 meters to the source, among which 4 got radiation sickness, 5 showed abnormal hemotogram, and others showed no abnormal response. Of 4 patients with radiation sickness, one 81 year old patient has died of severe bone marrow form of sub acute radiation sickness coupled with lung infection and prostrate apparatus at 13:00 on Oct., 20. Two children have been treated in Beitaiping Road Hospital in Beijing, another patient has been treated in local hospital. b) Biological dosimetry using conventional chromosome aberration analysis in human peripheral blood lymphocytes has been shown as a reliable and useful tool in medical management of radiation accident victims. Peripheral blood lymphocytes of the victims were cultured using conventional culture medium with colchicine added at the beginning. Chromosome

Interactive Rapid Dose Assessment Model (IRDAM): reactor-accident assessment methods. Vol.2

International Nuclear Information System (INIS)

Poeton, R.W.; Moeller, M.P.; Laughlin, G.J.; Desrosiers, A.E.

1983-05-01

As part of the continuing emphasis on emergency preparedness, the US Nuclear Regulatory Commission (NRC) sponsored the development of a rapid dose assessment system by Pacific Northwest Laboratory (PNL). This system, the Interactive Rapid Dose Assessment Model (IRDAM) is a micro-computer based program for rapidly assessing the radiological impact of accidents at nuclear power plants. This document describes the technical bases for IRDAM including methods, models and assumptions used in calculations. IRDAM calculates whole body (5-cm depth) and infant thyroid doses at six fixed downwind distances between 500 and 20,000 meters. Radionuclides considered primarily consist of noble gases and radioiodines. In order to provide a rapid assessment capability consistent with the capacity of the Osborne-1 computer, certain simplifying approximations and assumptions are made. These are described, along with default values (assumptions used in the absence of specific input) in the text of this document. Two companion volumes to this one provide additional information on IRDAM. The user's Guide (NUREG/CR-3012, Volume 1) describes the setup and operation of equipment necessary to run IRDAM. Scenarios for Comparing Dose Assessment Models (NUREG/CR-3012, Volume 3) provides the results of calculations made by IRDAM and other models for specific accident scenarios

Methods of assessing total doses integrated across pathways

International Nuclear Information System (INIS)

Grzechnik, M.; Camplin, W.; Clyne, F.; Allott, R.; Webbe-Wood, D.

2006-01-01

Calculated doses for comparison with limits resulting from discharges into the environment should be summed across all relevant pathways and food groups to ensure adequate protection. Current methodology for assessments used in the radioactivity in Food and the Environment (R.I.F.E.) reports separate doses from pathways related to liquid discharges of radioactivity to the environment from those due to gaseous releases. Surveys of local inhabitant food consumption and occupancy rates are conducted in the vicinity of nuclear sites. Information has been recorded in an integrated way, such that the data for each individual is recorded for all pathways of interest. These can include consumption of foods, such as fish, crustaceans, molluscs, fruit and vegetables, milk and meats. Occupancy times over beach sediments and time spent in close proximity to the site is also recorded for inclusion of external and inhalation radiation dose pathways. The integrated habits survey data may be combined with monitored environmental radionuclide concentrations to calculate total dose. The criteria for successful adoption of a method for this calculation were: Reproducibility can others easily use the approach and reassess doses? Rigour and realism how good is the match with reality?Transparency a measure of the ease with which others can understand how the calculations are performed and what they mean. Homogeneity is the group receiving the dose relatively homogeneous with respect to age, diet and those aspects that affect the dose received? Five methods of total dose calculation were compared and ranked according to their suitability. Each method was labelled (A to E) and given a short, relevant name for identification. The methods are described below; A) Individual doses to individuals are calculated and critical group selection is dependent on dose received. B) Individual Plus As in A, but consumption and occupancy rates for high dose is used to derive rates for application in

Meteorological monitoring for dose assessment and emergency response modeling - how much is enough?

International Nuclear Information System (INIS)

Glantz, C.S.

1990-01-01

Individuals responsible for emergency response or environmental/dose assessment routinely ask if there are enough meteorological data to adequately support their objectives. The answer requires detailed consideration of the intended applications, capabilities of the atmospheric dispersion model data, pollutant release characteristics, terrain in the modeling region, and size and distribution of the human population in the modeling domain. The meteorologist's detailed knowledge of, and experience in, studying atmospheric transport and diffusion can assist in determining the appropriate level of meteorological monitoring

Interactive Rapid Dose Assessment Model (IRDAM): user's guide

International Nuclear Information System (INIS)

Poeton, R.W.; Moeller, M.P.; Laughlin, G.J.; Desrosiers, A.E.

1983-05-01

As part of the continuing emphasis on emergency preparedness the US Nuclear Regulatory Commission (NRC) sponsored the development of a rapid dose assessment system by Pacific Northwest Laboratory (PNL). This system, the Interactive Rapid Dose Assessment Model (IRDAM) is a micro-computer based program for rapidly assessing the radiological impact of accidents at nuclear power plants. This User's Guide provides instruction in the setup and operation of the equipment necessary to run IRDAM. Instructions are also given on how to load the magnetic disks and access the interactive part of the program. Two other companion volumes to this one provide additional information on IRDAM. Reactor Accident Assessment Methods (NUREG/CR-3012, Volume 2) describes the technical bases for IRDAM including methods, models and assumptions used in calculations. Scenarios for Comparing Dose Assessment Models (NUREG/CR-3012, Volume 3) provides the results of calculations made by IRDAM and other models for specific accident scenarios

Criticism on Environmental Assessment Tools

NARCIS (Netherlands)

Abdalla, G.; Maas, G.J.; Huyghe, J.; Oostra, M.; Saji Baby, xx; Bogdan Zygmunt, xx

2011-01-01

Using environmental assessment tools to assess the sustainability of buildings, homes and mixed- use area is increasing. Environmental tools assign scores to projects using some sustainability (sub) aspects according to design and realization documents and evidences. Six European sustainable urban

Uncertainty on faecal analysis on dose assessment

Energy Technology Data Exchange (ETDEWEB)

Juliao, Ligia M.Q.C.; Melo, Dunstana R.; Sousa, Wanderson de O.; Santos, Maristela S.; Fernandes, Paulo Cesar P. [Instituto de Radioprotecao e Dosimetria, Comissao Nacional de Energia Nuclear, Av. Salvador Allende s/n. Via 9, Recreio, CEP 22780-160, Rio de Janeiro, RJ (Brazil)

2007-07-01

Monitoring programmes for internal dose assessment may need to have a combination of bioassay techniques, e.g. urine and faecal analysis, especially in workplaces where compounds of different solubilities are handled and also in cases of accidental intakes. Faecal analysis may be an important data for assessment of committed effective dose due to exposure to insoluble compounds, since the activity excreted by urine may not be detectable, unless a very sensitive measurement system is available. This paper discusses the variability of the daily faecal excretion based on data from just one daily collection; collection during three consecutive days: samples analysed individually and samples analysed as a pool. The results suggest that just 1 d collection is not appropriate for dose assessment, since the 24 h uranium excretion may vary by a factor of 40. On the basis of this analysis, the recommendation should be faecal collection during three consecutive days, and samples analysed as a pool, it is more economic and faster. (authors)

Scope and profoundness of environmental assessments. A study in the frame of environmental impact assessments. Strategic environmental assessment and FFH (fauna-flora-habitat) impact assessment under specific consideration of the conflict wind energy - bird protection

International Nuclear Information System (INIS)

Erb, Mareen

2013-01-01

The legal background of environmental impact assessments and the principle regulations and guidelines for this assessment are shortly summarized. The following Issues are discussed in detail: fundamentals of environmental assessments, profoundness and scope in environmental assessments; the conflict wind energy parks and birds.

Assessment of low absorbed dose with a MOSFET detector

International Nuclear Information System (INIS)

Butson, M.J.; Cancer Services, Wollongong, NSW; Cheung, T.; Yu, P.K.N.

2004-01-01

Full text: The ability of a MOSFET dosimetry system to measure low therapeutic doses has been evaluated for accuracy for high energy x-ray radiotherapy applications. The MOSFET system in high sensitivity mode produces a dose measurement reproducibility of within 10%, 4% and 2.5% for 2 cGy, 5 cGy and 10cGy dose assessment respectively. This is compared to 7%, 4% and 2% for an Attix parallel plate ionisation chamber and 20%, 7% and 3.5% for a Wellhofer IC4 small volume ionisation chamber. Results for our dose standard thimble ionisation chamber and low noise farmer dosemeter were 2%, 0.5% and 0.25% respectively for these measurements. The quoted accuracy of the MOSFET dosimetry system is partially due to the slight non linear dose response (reduced response) with age of the detector but mainly due to the intrinsic variations in measured voltage differential per applied dose. Results have shown that the MOSFET dosimetry system provides an adequate measure of dose at low dose levels and is comparable in accuracy to the Attix parallel plate ionisation chambers for relative dose assessment at levels of 2cGy to 10cGy. The use of the MOSFET dosimeter at low doses can extend the life expectancy of the device and may provide useful information for areas where low dose assessment is required. Copyright (2004) Australasian College of Physical Scientists and Engineers in Medicine

Challenges in Creating Evidence in Environmental Health Risk Assessments: The Example of Second-Hand Smoke

Directory of Open Access Journals (Sweden)

Florian Fischer

2016-01-01

Full Text Available Public health interventions are directed to influence the (state of a risk factor, either by behavioral or environmental changes. Therefore, environmental health risk assessments are highly relevant for public health decision making and policy development. The credibility of an environmental health risk assessment depends, to a large extent, on the strength of the scientific evidence on which it is based. In this article, the main challenges for assessing the impact of a potential adverse health effect from an environmental pollutant are described. Second-hand smoke (SHS was chosen to illustrate the current state of evidence. The assessment of the impact of potential adverse health effects from environmental risk factors is dependent on several issues, such as the hypothesized health outcome, the nature of the exposure, the dose-response-relationship and the variability and susceptibility of the exposed population. The example of SHS exposure highlights the need for evidence-based public health. Several challenges in terms of study design, assessment methods, as well as data analysis and synthesis with respect to the stratification of results, and consideration of bias and confounding exist. Future research needs to take into account which methods and techniques will be used to generate evidence for population-level decisions.

Environmental Workplace Assessment.

Science.gov (United States)

Bernier, Jacques; And Others

1994-01-01

Describes environmental workplace assessments as tools in developing customized training, highlighting the group process and individual interview techniques. Suggests that, by assessing the cultural climate of an organization, education providers can gather essential baseline information on an organization and thereby provide a guide for further…

Strategic environmental assessment

DEFF Research Database (Denmark)

Kørnøv, Lone

1997-01-01

The integration of environmental considerations into strategic decision making is recognized as a key to achieving sustainability. In the European Union a draft directive on Strategic Environmental Assessment (SEA) is currently being reviewed by the member states. The nature of the proposed SEA...... that the SEA directive will influence the decision-making process positively and will help to promote improved environmental decisions. However, the guidelines for public participation are not sufficient and the democratic element is strongly limited. On the basis of these findings, recommendations relating...

Oak Ridge Reservation Environmental Protection Rad Neshaps Radionuclide Inventory Web Database and Rad Neshaps Source and Dose Database.

Science.gov (United States)

Scofield, Patricia A; Smith, Linda L; Johnson, David N

2017-07-01

The U.S. Environmental Protection Agency promulgated national emission standards for emissions of radionuclides other than radon from US Department of Energy facilities in Chapter 40 of the Code of Federal Regulations (CFR) 61, Subpart H. This regulatory standard limits the annual effective dose that any member of the public can receive from Department of Energy facilities to 0.1 mSv. As defined in the preamble of the final rule, all of the facilities on the Oak Ridge Reservation, i.e., the Y-12 National Security Complex, Oak Ridge National Laboratory, East Tennessee Technology Park, and any other U.S. Department of Energy operations on Oak Ridge Reservation, combined, must meet the annual dose limit of 0.1 mSv. At Oak Ridge National Laboratory, there are monitored sources and numerous unmonitored sources. To maintain radiological source and inventory information for these unmonitored sources, e.g., laboratory hoods, equipment exhausts, and room exhausts not currently venting to monitored stacks on the Oak Ridge National Laboratory campus, the Environmental Protection Rad NESHAPs Inventory Web Database was developed. This database is updated annually and is used to compile emissions data for the annual Radionuclide National Emission Standards for Hazardous Air Pollutants (Rad NESHAPs) report required by 40 CFR 61.94. It also provides supporting documentation for facility compliance audits. In addition, a Rad NESHAPs source and dose database was developed to import the source and dose summary data from Clean Air Act Assessment Package-1988 computer model files. This database provides Oak Ridge Reservation and facility-specific source inventory; doses associated with each source and facility; and total doses for the Oak Ridge Reservation dose.

Impacts Analyses Supporting the National Environmental Policy Act Environmental Assessment for the Resumption of Transient Testing Program

Energy Technology Data Exchange (ETDEWEB)

Schafer, Annette L. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Brown, LLoyd C. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Carathers, David C. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Christensen, Boyd D. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Dahl, James J. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Miller, Mark L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Farnum, Cathy Ottinger [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Peterson, Steven [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Sondrup, A. Jeffrey [Idaho National Lab. (INL), Idaho Falls, ID (United States); Subaiya, Peter V. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Wachs, Daniel M. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Weiner, Ruth F. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2014-02-01

This document contains the analysis details and summary of analyses conducted to evaluate the environmental impacts for the Resumption of Transient Fuel and Materials Testing Program. It provides an assessment of the impacts for the two action alternatives being evaluated in the environmental assessment. These alternatives are (1) resumption of transient testing using the Transient Reactor Test Facility (TREAT) at Idaho National Laboratory (INL) and (2) conducting transient testing using the Annular Core Research Reactor (ACRR) at Sandia National Laboratory in New Mexico (SNL/NM). Analyses are provided for radiologic emissions, other air emissions, soil contamination, and groundwater contamination that could occur (1) during normal operations, (2) as a result of accidents in one of the facilities, and (3) during transport. It does not include an assessment of the biotic, cultural resources, waste generation, or other impacts that could result from the resumption of transient testing. Analyses were conducted by technical professionals at INL and SNL/NM as noted throughout this report. The analyses are based on bounding radionuclide inventories, with the same inventories used for test materials by both alternatives and different inventories for the TREAT Reactor and ACRR. An upper value on the number of tests was assumed, with a test frequency determined by the realistic turn-around times required between experiments. The estimates provided for impacts during normal operations are based on historical emission rates and projected usage rates; therefore, they are bounding. Estimated doses for members of the public, collocated workers, and facility workers that could be incurred as a result of an accident are very conservative. They do not credit safety systems or administrative procedures (such as evacuation plans or use of personal protective equipment) that could be used to limit worker doses. Doses estimated for transportation are conservative and are based on

Environmental radioactivity in the UK: the airborne geophysical view of dose rate estimates

International Nuclear Information System (INIS)

Beamish, David

2014-01-01

This study considers UK airborne gamma-ray data obtained through a series of high spatial resolution, low altitude surveys over the past decade. The ground concentrations of the naturally occurring radionuclides Potassium, Thorium and Uranium are converted to air absorbed dose rates and these are used to assess terrestrial exposure levels from both natural and technologically enhanced sources. The high resolution airborne information is also assessed alongside existing knowledge from soil sampling and ground-based measurements of exposure levels. The surveys have sampled an extensive number of the UK lithological bedrock formations and the statistical information provides examples of low dose rate lithologies (the formations that characterise much of southern England) to the highest sustained values associated with granitic terrains. The maximum dose rates (e.g. >300 nGy h −1 ) encountered across the sampled granitic terrains are found to vary by a factor of 2. Excluding granitic terrains, the most spatially extensive dose rates (>50 nGy h −1 ) are found in association with the Mercia Mudstone Group (Triassic argillaceous mudstones) of eastern England. Geological associations between high dose rate and high radon values are also noted. Recent studies of the datasets have revealed the extent of source rock (i.e. bedrock) flux attenuation by soil moisture in conjunction with the density and porosity of the temperate latitude soils found in the UK. The presence or absence of soil cover (and associated presence or absence of attenuation) appears to account for a range of localised variations in the exposure levels encountered. The hypothesis is supported by a study of an extensive combined data set of dose rates obtained from soil sampling and by airborne geophysical survey. With no attenuation factors applied, except those intrinsic to the airborne estimates, a bias to high values of between 10 and 15 nGy h −1 is observed in the soil data. A wide range of

Health assessment of environmental pollutants: proliferative and degenerative diseases

International Nuclear Information System (INIS)

Stuart, B.O.

1988-01-01

In order to achieve a balanced approach to risk assessment between carcinogenic and non-carcinogenic health effects one must examine the risk of disease or death in the general population exposed to a particular air pollutant that can be related quantitatively to intensity and duration of exposures (National Academy of Sciences, 1983). Such risk assessment should be based upon careful evaluation of scientific findings of dose-response relationships in the chronically exposed population. Quantitative assessment of environmentally produced disease in man has proven to be complex and demanding. A variety of factors play important roles in this task. As an example, there are induction-latency periods for chronic diseases, including cancer, which may range from five to twenty-five years. The diseases themselves, whether proliferative or degenerative, may follow several stages of progression. There is only sparse epidemiological data on serious health effects that may be due to environmental as compared to occupational exposures. Exposures to chemical or radiological air contaminants do not occur singly but to a multiplicity of agents, and disease processes are frequently markedly affected by the interaction of a variety of factors, particularly that of cigarette smoking. There is growing recognition of potentially sensitive subpopulations, including the elderly and the very young, but adequate techniques for assessing the magnitude of increased risks to these groups have not yet been developed

Real time source term and dose assessment

International Nuclear Information System (INIS)

Breznik, B.; Kovac, A.; Mlakar, P.

2001-01-01

The Dose Projection Programme is a tool for decision making in case of nuclear emergency. The essential input data for quick emergency evaluation in the case of hypothetical pressurised water reactor accident are following: source term, core damage assessment, fission product radioactivity, release source term and critical exposure pathways for an early phase of the release. A reduced number of radio-nuclides and simplified calculations can be used in dose calculation algorithm. Simple expert system personal computer programme has been developed for the Krsko Nuclear Power Plant for dose projection within the radius of few kilometers from the pressurised water reactor in early phase of an accident. The input data are instantaneous data of core activity, core damage indicators, release fractions, reduction factor of the release pathways, spray operation, release timing, and dispersion coefficient. Main dose projection steps are: accurate in-core radioactivity determination using reactor power input; core damage and in-containment source term assessment based on quick indications of instrumentation or on activity analysis data; user defines release pathway for typical PWR accident scenarius; dose calculation is performed only for exposure pathway critical for decision about evacuation or sheltering in early phase of an accident.(author)

Transboundary Environmental Impact Assessment : An Introduction

NARCIS (Netherlands)

Bastmeijer, C.J.; Koivurova, T.; Bastmeijer, K.; Koivurova, T.

2008-01-01

Environmental Impact Assessment (EIA) is a well-established instrument of environmental law and policy that aims to ensure that potential adverse environmental effects of human activities are assessed before decisions on such activities are made. The instrument is increasingly being applied in

Environmental assessment of the proposed Continuous Wave Deuterium Demonstrator (CWDD)

International Nuclear Information System (INIS)

1992-03-01

An assessment was made of the potential environmental impacts of construction and operation of the Continuous Wave Deuterium Demonstrator (CWDD) at Argonne National Laboratory (ANL), including an evaluation of alternative actions. Key elements considered were on- and off-site radiological effects and potential impacts to cultural resources. The radiological consequences of routine operations of the CWDD are readily reduced to insignificant levels by bulk shielding, confinement, and containment. The radiation dose to the maximally exposed off-site individual would be 0.52 mrem/yr from direct radiation and 1.2 x 10 -3 mrem/yr from airborne radionuclides, based on maximum planned facility operation. The maximum credible postulated accident would result in a dose to the maximally exposed individual of less than 20 mrem. A cultural resource survey has determined that the location for the CWDD has, no cultural resource sites or materials and construction is permitted by the Illinois Historic Preservation Agency. Demands for utility services would require only about two percent of excess capacity already installed at Argonne. Other environmental impact categories were considered, including socioeconomic effects, aquatic and terrestrial flora and fauna, wetlands, and water and air quality

Issues in environmental control data used in DD ampersand ER worker dose exposures

International Nuclear Information System (INIS)

White, M.G.

1995-01-01

Sites for decontamination and decommissioning (DD) or environmental remediation (ER) are often from US DOE operations that began during and shortly after World War II. This paper discusses selected problems in the use of environmental data for DD and ER worker dose exposure calculations

Internal dose assessment in radiation accidents

International Nuclear Information System (INIS)

Toohey, R.E.

2003-01-01

Although numerous models have been developed for occupational and medical internal dosimetry, they may not be applicable to an accident situation. Published dose coefficients relate effective dose to intake, but if acute deterministic effects are possible, effective dose is not a useful parameter. Consequently, dose rates to the organs of interest need to be computed from first principles. Standard bioassay methods may be used to assess body contents, but, again, the standard models for bioassay interpretation may not be applicable because of the circumstances of the accident and the prompt initiation of decorporation therapy. Examples of modifications to the standard methodologies include adjustment of biological half-times under therapy, such as in the Goiania accident, and the same effect, complicated by continued input from contaminated wounds, in the Hanford 241 Am accident. (author)

Long-Term Assessment of Critical Radionuclides and Associated Environmental Media at the Savannah River Site

Energy Technology Data Exchange (ETDEWEB)

Jannik, G. T.; Baker, R. A.; Lee, P. L.; Eddy, T. P.; Blount, G. C.; Whitney, G. R.

2012-11-06

During the operational history of the Savannah River Site (SRS), many different radionuclides have been released from site facilities. However, only a relatively small number of the released radionuclides have been significant contributors to doses and risks to the public. At SRS dose and risk assessments indicate tritium oxide in air and surface water, and Cs-137 in fish and deer have been, and continue to be, the critical radionuclides and pathways. In this assessment, indepth statistical analyses of the long-term trends of tritium oxide in atmospheric and surface water releases and Cs-137 concentrations in fish and deer are provided. Correlations also are provided with 1) operational changes and improvements, 2) geopolitical events (Cold War cessation), and 3) recent environmental remediation projects and decommissioning of excess facilities. For example, environmental remediation of the F- and H-Area Seepage Basins and the Solid Waste Disposal Facility have resulted in a measurable impact on the tritium oxide flux to the onsite Fourmile Branch stream. Airborne releases of tritium oxide have been greatly affected by operational improvements and the end of the Cold War in 1991. However, the effects of SRS environmental remediation activities and ongoing tritium operations on tritium concentrations in the environment are measurable and documented in this assessment. Controlled hunts of deer and feral hogs are conducted at SRS for approximately six weeks each year. Before any harvested animal is released to a hunter, SRS personnel perform a field analysis for Cs-137 concentrations to ensure the hunter's dose does not exceed the SRS administrative game limit of 0.22 millisievert (22 mrem). However, most of the Cs-137 found in SRS onsite deer is not from site operations but is from nuclear weapons testing fallout from the 1950's and early 1960's. This legacy source term is trended in the SRS deer, and an assessment of the ''effective'' half-life of Cs-137 in deer

The MESORAD dose assessment model: Computer code

International Nuclear Information System (INIS)

Ramsdell, J.V.; Athey, G.F.; Bander, T.J.; Scherpelz, R.I.

1988-10-01

MESORAD is a dose equivalent model for emergency response applications that is designed to be run on minicomputers. It has been developed by the Pacific Northwest Laboratory for use as part of the Intermediate Dose Assessment System in the US Nuclear Regulatory Commission Operations Center in Washington, DC, and the Emergency Management System in the US Department of Energy Unified Dose Assessment Center in Richland, Washington. This volume describes the MESORAD computer code and contains a listing of the code. The technical basis for MESORAD is described in the first volume of this report (Scherpelz et al. 1986). A third volume of the documentation planned. That volume will contain utility programs and input and output files that can be used to check the implementation of MESORAD. 18 figs., 4 tabs

Assessment of external dose indoors in Lithuania

International Nuclear Information System (INIS)

Pilkyte, L.; Butkus, D.; Morkunas, G.

2006-01-01

The aim of this paper was an assessment of external exposure indoors and its dependence on construction materials and indoor radon concentrations in Lithuanian living houses. Relationship of absorbed dose rate in air indoors and activity indexes of the most commonly used construction materials (wood, concrete and bricks) have been studied using results received in measurements done in >4700 rooms in 1995-2005. Possible connections of dose rate indoors with indoor radon concentrations are also discussed. Findings of this study helped to make an assessment of the mean value of effective dose of Lithuanian population due to external exposure indoors which is equal to 0.58 mSv y -1 . The received data might also be used in improvement of quality of personal dosimetric measurements done in premises constructed of different construction materials. (authors)

Methodology of environmental risk assessment management

Directory of Open Access Journals (Sweden)

Saša T. Bakrač

2012-04-01

Full Text Available Successful protection of environment is mostly based on high-quality assessment of potential and present risks. Environmental risk management is a complex process which includes: identification, assessment and control of risk, namely taking measures in order to minimize the risk to an acceptable level. Environmental risk management methodology: In addition to these phases in the management of environmental risk, appropriate measures that affect the reduction of risk occurrence should be implemented: - normative and legal regulations (laws and regulations, - appropriate organizational structures in society, and - establishing quality monitoring of environment. The emphasis is placed on the application of assessment methodologies (three-model concept, as the most important aspect of successful management of environmental risk. Risk assessment methodology - European concept: The first concept of ecological risk assessment methodology is based on the so-called European model-concept. In order to better understand this ecological risk assessment methodology, two concepts - hazard and risk - are introduced. The European concept of environmental risk assessment has the following phases in its implementation: identification of hazard (danger, identification of consequences (if there is hazard, estimate of the scale of consequences, estimate of consequence probability and risk assessment (also called risk characterization. The European concept is often used to assess risk in the environment as a model for addressing the distribution of stressors along the source - path - receptor line. Risk assessment methodology - Canadian concept: The second concept of the methodology of environmental risk assessment is based on the so-called Canadian model-concept. The assessment of ecological risk includes risk arising from natural events (floods, extreme weather conditions, etc., technological processes and products, agents (chemical, biological, radiological, etc

Assessment of a new p-Mosfet usable as a dose rate insensitive gamma dose sensor

International Nuclear Information System (INIS)

Vettese, F.; Donichak, C.; Bourgeault, P.

1995-01-01

Dosimetric response of unbiased MOS devices has been assessed at dose rates greater than 2000 cGy/h. Application have been made to a personal dosemeter / dose rate meter to measure the absorbed tissue dose received in the case of acute external irradiation. (D.L.)

An overview of the ERICA Integrated Approach to the assessment and management of environmental risks from ionising contaminants

International Nuclear Information System (INIS)

Larsson, Carl-Magnus

2008-01-01

The ERICA project (environmental risks from ionising contaminants: assessment and management, EC contract no. FI6R-CT-2004-508847) concluded with the publication of two main outputs: the ERICA Integrated Approach to the assessment and management of environmental risks from ionising radiation, of which also introduces the user to the second main output, the ERICA Tool, which is a software programme with supporting databases, that together with its associated help will guide users through the assessment process. More than 60 European scientists contributed to the ERICA Integrated Approach. In addition, a large number of experts, policy makers, and decision-makers in different areas have contributed views on the ERICA Integrated Approach and its associated Tool from the user's perspective, through participation in the End-Users Group set up under the ERICA project. Databases on transfer, dose conversion coefficients and radiation effects on biota have been developed specifically for the purpose of the Integrated Approach, and incorporated into, or interacting with, the Tool. Species sensitivity distributions of biological effects data have been performed and did not reveal, for chronic exposure, any statistical grounds for separation between terrestrial, marine and freshwater ecosystems in terms of species sensitivity to radiation; on the basis of such analysis a universal screening dose rate criterion of 10 μGy h -1 incremental dose rate is suggested for exiting the assessment procedure while being confident that environmental risks are negligible. This criterion is used for the two first tiers (conservative assessment with limited data requirement and various possibilities of incorporating user-defined parameter values, including the screening dose rate criterion) of the assessment methodology. Exposure situations of concern are carried through a third tier, making use of all relevant databases and with a number of issues and options listed to support and guide

Recent advances in assessment of workplace exposure--epidemiologic linkage of medical and environmental data

International Nuclear Information System (INIS)

Landrigan, P.J.

1982-01-01

The toxicity to man of environmental agents is most accurately assessed when quantitative data are available on both exposure (dose) and response. Worker populations are of unique importance in the study of toxic effects because they are relatively well defined, easily traced, and more heavily exposed to toxic chemical and physical agents than are members of the general community. The union of epidemiology, industrial hygiene, and occupational subacute, and chronic dose-response relationships in worker populations. This report describes the application of epidemiology to evaluations of workers exposed to methyl alcohol vapor (acute toxicity), ozone (subacute), and lead and ionizing radiation (chronic). The derivation of accurate dose-response data provides a rational basis for the establishment of exposure standards

An assessment methodology of environmental risks associated with radioactive waste management

International Nuclear Information System (INIS)

Goldberg, S.M.; Logan, S.E.; Berbano, M.C.

1977-01-01

One major environmental concern associated with the projected increase in nuclear power generation is the treatment and storage or disposal of radioactive wastes. The US Environmental Protection Agency (EPA), in collaboration with the University of New Mexico, has been developing a detailed assessment methodology of short- and long-term quantitative risks to the environment resulting from release of radionuclides during all phases of radioactive waste management operations. The paper describes a comprehensive model developed during 1976 for the public health and environmental impacts from the disposal of high-level and transuranic waste in geological formations. Parametric studies have been performed with this model for various geological disposal media and for waste in different forms. EPA has planned to utilize these parametric risk calculations to translate probabilities and consequences of risk occurrences into a cost-effectiveness perspective for decision-making purposes. This comprehensive model consisted of a release or fault-tree model, an environmental model and an economic model. Fault trees have been constructed to provide the relationships between various geophysical, meteorological and man-caused events which are potential mechanisms for release of radioactive material to the environment from waste repositories. The environmental model includes transport to and accumulations at various receptors in the biosphere, including a determination of pathways from environmental input concentrations to radiation dose to man. Finally, the economic results are used to compare and assess the various disposal concepts as a basis for formulating policy decisions. Implementation of this assessment methodology is possible for a whole range of radioactive and non-radioactive hazardous materials which require perpetual care. Further, the output will be used by EPA in the short term to develop general environmental standards applicable to any radioactive waste management

An assessment methodology of environmental risks associated with radioactive waste management

International Nuclear Information System (INIS)

Goldberg, S.M.; Logan, S.E.; Brebano, M.C.

1977-01-01

One of the major environmental concerns associated with the projected increase in nuclear power generation is the treatment and storage or disposal of radioactive wastes. The U.S. Environmental Protection Agency (EPA) in collaboration with the University of New Mexico has been developing a detailed assessment methodology of both the short-term as well as long-term quantitative risks on the environment resulting from the release of radionuclides during all phases of radioactive waste management operations. This past year a comprehensive model has been developed for the public health and environmental impacts from the disposal of high-level and transuranic waste in geological formations. Parametric studies have been performed with this model for various geological disposal media and for waste in different forms. EPA has planned to utilize these parametric risk calculations to translate probabilities and consequences of risk occurrences into a cost-effectiveness perspective for decision-making purposes. This comprehensive model has consisted of a release or fault tree model, an environmental model, and an economic model. Fault trees have been constructed to provide the relationships between various geophysical, meteorological, and man-caused events which are potential mechanisms for release of radioactive material to the environment from waste repositories. The environmental model includes the transport to and accumulations at various receptors in the biosphere, including a determination of pathways from environmental input concentrations to radiation dose to man. Finally, the economic results are used to compare and assess the various disposal concepts as a basis for formulating policy decisions. Implementation of this assessment methodology is possible for a whole range of both radioactive as well as non-radioactive hazardous materials which require perpetual care. Further, the output will be used by EPA in the short-term to develop general environmental standards

Going beyond the most exposed people in a dose assessment

Energy Technology Data Exchange (ETDEWEB)

Hjerpe, Thomas; Broed, Robert [Facilia AB, Gustavslundsvaegen 151C, SE-167 51 Bromma (Sweden); Ikonen, Ari T.K. [Environmental Research and Assessment, EnviroCase, Ltd., Hallituskatu 1 D 4, FI-28 100 Pori (Finland)

2014-07-01

The dose assessment in a long-term radiation safety assessment often focus on assessing dose of a representative person to be used for determining compliance with a radiation dose constraint. This representative person is often assumed to receive a dose that is representative of the most exposed people, i.e., the more highly exposed individuals in the population. This is not always sufficient, the Finnish regulations for disposal of nuclear waste has radiation dose constraint to the most exposed people as well as for larger groups of exposed people. This work presents the methodology to assessing dose of a representative person for a larger group of exposed people as applied by Posiva in the TURVA-2012 safety case for the spent nuclear fuel disposal at Olkiluoto. In addition, annual doses from the set of biosphere calculation cases analysed in TURVA-2012 are presented and discussed. Special focus is given on explaining the differences in exposure levels and exposure routes between the estimated annual doses to representative persons for most exposed people and a larger exposed group. The results show that the annual doses to a larger group of people ranges from one to three orders of magnitude below the annual doses to the most exposed people. Furthermore, the exposure route related to food ingestion is less significant for the larger group of people compared to the most exposed people and that the exposure route related to water ingestion shows the opposite behaviour. (authors)

Assessment of body doses from photon exposures using human voxel models

International Nuclear Information System (INIS)

Zankl, M.; Fill, U.; Petoussi-Henss, N.; Regulla, D.

2000-01-01

For the scope of risk assessment in protection against ionising radiation (occupational, environmental and medical) it is necessary to determine the radiation dose to specific body organs and tissues. For this purpose, a series of models of the human body were designed in the past, together with computer codes simulating the radiation transport and energy deposition in the body. Most of the computational body models in use are so-called mathematical models; the most famous is the MIRD-5 phantom developed at Oak Ridge National Laboratory. In the 1980s, a new generation of human body models was introduced at GSF, constructed from whole body CT data. Due to being constructed from image data of real persons, these 'voxel models' offer an improved realism of external and internal shape of the body and its organs, compared to MIRD-type models. Comparison of dose calculations involving voxel models with respective dose calculations for MIRD-type models revealed that the deviation of the individual anatomy from that described in the MIRD-type models indeed introduces significant deviations of the calculated organ doses. Specific absorbed fractions of energy released in a source organ due to incorporated activity which are absorbed in target organs may differ by more than an order of magnitude between different body models; for external photon irradiation, the discrepancies are more moderate. (author)

TSD-DOSE: A radiological dose assessment model for treatment, storage, and disposal facilities

International Nuclear Information System (INIS)

Pfingston, M.; Arnish, J.; LePoire, D.; Chen, S.-Y.

1998-01-01

Past practices at US Department of Energy (DOE) field facilities resulted in the presence of trace amounts of radioactive materials in some hazardous chemical wastes shipped from these facilities. In May 1991, the DOE Office of Waste Operations issued a nationwide moratorium on shipping all hazardous waste until procedures could be established to ensure that only nonradioactive hazardous waste would be shipped from DOE facilities to commercial treatment, storage, and disposal (TSD) facilities. To aid in assessing the potential impacts of shipments of mixed radioactive and chemically hazardous wastes, a radiological assessment computer model (or code) was developed on the basis of detailed assessments of potential radiological exposures and doses for eight commercial hazardous waste TSD facilities. The model, called TSD-DOSE, is designed to incorporate waste-specific and site-specific data to estimate potential radiological doses to on-site workers and the off-site public from waste-handling operations at a TSD facility. The code is intended to provide both DOE and commercial TSD facilities with a rapid and cost-effective method for assessing potential human radiation exposures from the processing of chemical wastes contaminated with trace amounts of radionuclides

Environmental gamma dose rate monitoring along Mumbai-Pune route using environmental radiation monitor with navigational aid

International Nuclear Information System (INIS)

Padmanabhan, N.; Kale, M.S.; Raman, N.; Krishnamachari, G.; Harikumar, M.; Sharma, D.N.; Mehta, S.K.

1997-01-01

A continuous environmental radiation monitor with navigational aid (ERMNA) for mapping natural gamma radiation background on country wide scale by deployment in railway coaches, has been designed. The system makes use of Indian railway network which is one of the widest network of railways in the world covering nearly complete length and breadth of the country. The system uses an energy compensated (within ± 30%) GN detectors for measurement of environmental dose rate due to natural background, a global positioning system (GPS) for on-line acquisition of positional co-ordinates (longitude and latitude) and an 8085 based data acquisition and processing unit. This system is deployed in guard's cabin of a train. The dose rate data tagged with positional co-ordinates and collected by the system during train journey is down loaded into a Lap Top PC for storage, analysis and graphical representation. The system has been used for background monitoring between Mumbai and Pune. The dose rates recorded over a period of three months ranging from November 1996 to February 1997 along the route show no change in the values which vary from 4 μr/h to 6 μR/h along the route. It drops down to <3 μR/h within tunnels en route. (author)

Dose. Detriment. Limit assessment

International Nuclear Information System (INIS)

Breckow, J.

2015-01-01

One goal of radiation protection is the limitation of stochastic effects due to radiation exposure. The probability of occurrence of a radiation induced stochastic effect, however, is only one of several other parameters which determine the radiation detriment. Though the ICRP-concept of detriment is a quantitative definition, the kind of detriment weighting includes somewhat subjective elements. In this sense, the detriment-concept of ICRP represents already at the stage of effective dose a kind of assessment. Thus, by comparing radiation protection standards and concepts interconvertible or with those of environment or occupational protection one should be aware of the possibly different principles of detriment assessment.

Site environmental report for 1994. Environmental report, January--December 1994

International Nuclear Information System (INIS)

1994-01-01

This document is the 1994 site environmental report for the Rocky Flats Environmental Technology Site for January thru December. Compliance programs, radiological and nonradiological monitoring, and significant issues and events are described. In addition, the methodology for radiation dose assessment and the Environmental Restoration, Waste Management, and Quality Assurance programs are discussed

Dose related risk and effect assessment model (DREAM) -- A more realistic approach to risk assessment of offshore discharges

International Nuclear Information System (INIS)

Johnsen, S.; Furuholt, E.

1995-01-01

Risk assessment of discharges from offshore oil and gas production to the marine environment features determination of potential environmental concentration (PEC) levels and no observed effect concentration (NOEC) levels. The PEC values are normally based on dilution of chemical components in the actual discharge source in the recipient, while the NOEC values are determined by applying a safety factor to acute toxic effects from laboratory tests. The DREAM concept focuses on realistic exposure doses as function of contact time and dilution, rather than fixed exposure concentrations of chemicals in long time exposure regimes. In its present state, the DREAM model is based on a number of assumptions with respect to the link between real life exposure doses and effects observed in laboratory tests. A research project has recently been initiated to develop the concept further, with special focus on chronic effects of different chemical compounds on the marine ecosystem. One of the questions that will be addressed is the link between exposure time, dose, concentration and effect. Validation of the safety factors applied for transforming acute toxic data into NOEC values will also be included. The DREAM model has been used by Statoil for risk assessment of discharges from new and existing offshore oil and gas production fields, and has been found to give a much more realistic results than conventional risk assessment tools. The presentation outlines the background for the DREAM approach, describes the model in its present state, discusses further developments and applications, and shows a number of examples on the performance of DREAM

Assessment of concomitant testicular dose with radiochromic film

International Nuclear Information System (INIS)

Fricker, Katherine; Thompson, Christine; Meyer, Juergen

2013-01-01

To assess the suitability of EBT2 and XRQA2 Gafchromic film for measuring low doses in the periphery of treatment fields, and to measure the accumulative concomitant dose to the contralateral testis resulting from CT imaging, pre-treatment imaging (CBCT) and seminoma radiotherapy with and without gonadal shielding. Superficial peripheral dose measurements made using EBT2 Gafchromic film on the surface of water equivalent material were compared to measurements made with an ionisation chamber in a water phantom to evaluate the suitability and accuracy of the film dosimeter for such measurements. Similarly, XRQA2 was used to measure surface doses within a kilovoltage beam and compared with ionisation chamber measurements. Gafchromic film was used to measure CT, CBCT and seminoma treatment related testicular doses on an anthropomorphic phantom. Doses were assessed for two clinical plans, both with and without gonadal shielding. Testicular doses resulting from the treatment of up to 0.83 ± 0.17 Gy were measured per treatment. Additional doses of up to 0.49 ± 0.01 and 2.35 ± 0.05 cGy were measured per CBCT and CT image, respectively. Reductions in the testicular dose in the order of 10, 36 and 78 % were observed when gonadal shielding was fitted for treatment, CT and CBCT imaging, respectively. Gafchromic film was found to be suitable for measuring dose in the periphery of treatment fields. The dose to the testis should be limited to minimise the risk of radiation related side effects. This can be achieved by using appropriate gonadal shielding, irrespective of the treatment fields employed.

Assessment of exposure dose to workers in virtual decommissioning environments

International Nuclear Information System (INIS)

Jeong, KwanSeong; Moon, JeiKwon; Choi, ByungSeon; Hyun, Dongjun; Lee, Jonghwan; Kim, Ikjune; Kim, GeunHo; Seo, JaeSeok

2014-01-01

This paper is intended to suggest the method analyze and assess the exposure dose to workers in virtual decommissioning environments. To simulate a lot of decommissioning scenarios, decommissioning environments were designed in virtual reality. To simulate and assess the exposure dose to workers, human model also was designed in virtual environments. These virtual decommissioning environments made it possible to real-time simulate and assess the exposure dose to workers. This work was to be able to simulate scenarios of decommissioning so that exposure dose to workers could be measured and assessed. To establish the plan of exposure dose to workers during decommissioning of nuclear facilities before decommissioning activities are accomplished, the method of simulation assessment was developed in virtual radiological environments. But this work was developed as a tool of simulation for single subject mode. Afterwards, the simulation environment for multi-subjects mode will be upgraded by simultaneous modules with networking environments. Then the much more practical method will be developed by changing number of workers and duration of time under any circumstances of decommissioning

Assessment of exposure dose to workers in virtual decommissioning environments

Energy Technology Data Exchange (ETDEWEB)

Jeong, KwanSeong; Moon, JeiKwon; Choi, ByungSeon; Hyun, Dongjun; Lee, Jonghwan; Kim, Ikjune; Kim, GeunHo; Seo, JaeSeok [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2014-10-15

This paper is intended to suggest the method analyze and assess the exposure dose to workers in virtual decommissioning environments. To simulate a lot of decommissioning scenarios, decommissioning environments were designed in virtual reality. To simulate and assess the exposure dose to workers, human model also was designed in virtual environments. These virtual decommissioning environments made it possible to real-time simulate and assess the exposure dose to workers. This work was to be able to simulate scenarios of decommissioning so that exposure dose to workers could be measured and assessed. To establish the plan of exposure dose to workers during decommissioning of nuclear facilities before decommissioning activities are accomplished, the method of simulation assessment was developed in virtual radiological environments. But this work was developed as a tool of simulation for single subject mode. Afterwards, the simulation environment for multi-subjects mode will be upgraded by simultaneous modules with networking environments. Then the much more practical method will be developed by changing number of workers and duration of time under any circumstances of decommissioning.

International cooperation in the safety and environmental assessment for the ITER engineering design activities

International Nuclear Information System (INIS)

Gordon, C.; Baker, D.J.; Bartels, H-W.

1998-01-01

The ITER Project includes design and assessment activities to ensure the safety and environmental attractiveness of ITER and demonstrate that it can be sited in any of the sponsoring Parties with a minimum of site-specific redesign. This paper highlights some of the efforts to develop an international consensus approach for ITER safety design and assessment, including: development of general safety and environmental design criteria; development of quantitative dose-release assessment criteria; development of a radiation protection program; waste characterization; and development of safety analysis guidelines. The high level of interaction, cooperation and collaboration between the Joint Central Team and the Home Teams, and between the safety team and designers, and the spirit of consensus that has guided them have resulted in a safe design for ITER and a safety design and assessment that can meet the needs of the potential host countries. (author)

The FASSET Framework for assessment of environmental impact of ionising radiation in European ecosystems-an overview

International Nuclear Information System (INIS)

Larsson, C-M

2004-01-01

The FASSET project was launched in November 2000 under the EC 5th Framework Programme to develop a framework for the assessment of environmental impact of ionising radiation in European ecosystems. It involved 15 organisations in seven European countries and delivered its final report in spring 2004. The project set out to organise radioecological and radiobiological data into a logical structure that would facilitate the assessment of likely effects on non-human biota resulting from known or postulated depositions of radionuclides in the environment. The project included an overview of 20 pathway-based environmental assessment systems targeted at radioactive substances, or at hazardous substances in general. The resulting framework includes the following fundamental elements: source characterisation; description of seven major European ecosystems; selection of a number of reference organisms on the basis of prior ecosystem and exposure analysis; environmental transfer analysis; dosimetric considerations; effects analysis; and general guidance on interpretation including consideration of uncertainties. The project has used existing information supplemented with development in some areas, e.g. Monte Carlo calculations to derive dose conversion coefficients, model development, and the building of an effects database (FRED, the FASSET Radiation Effects Database). On the basis of experience from FASSET and other recent programmes, it can be concluded that (i) there is substantial agreement in terms of conceptual approaches between different frameworks currently in use or proposed, (ii) differences in technical approaches can be largely attributed to differences in ecosystems of concern or in national regulatory requirements, (iii) sufficient knowledge is available to scientifically justify assessments following the Framework structure, but (iv) significant data gaps exist for environmental transfer of key nuclides as well as for effects data for key wildlife groups at

Committed dose assessment based on background outdoor gamma exposure in Chihuahua City, Mexico

International Nuclear Information System (INIS)

Luevano G, S.; Perez T, A.; Pinedo A, C.; Renteria V, M.; Carrillo F, J.; Montero C, M. E.

2015-10-01

Full text: Determining ionizing radiation in a geographic area serves to assess its effects on populations health. The aim of this study was to evaluate the spatial distribution of the background environmental outdoor gamma dose rates in Chihuahua City. This study also estimated the committed dose and the lifetime cancer risks of the population of this city. To determine the outdoor gamma dose rate in air, annual effective dose, and the lifetime cancer risk, 48 sampling points were randomly selected along the Chihuahua City. Outdoor gamma dose rate measurements were carried out by using a Geiger-Muller counter. At the same sites, 48 soil samples were taken to obtain the activity concentrations of 226 Ra, 232 Th, 40 K and their terrestrial gamma dose rates. Radioisotope activity concentrations were determined by gamma spectrometry. Outdoor gamma dose rates ranged from 56 to 193 n Gy h -1 . Results indicated that lifetime effective dose to inhabitants of Chihuahua City is in average of 19.8 mSv, resulting in a lifetime cancer risk of 0.001. In addition, the mean of activity concentrations in soil were 51.8, 73.1, and 1096.5 Bq kg -1 , of 226 Ra, 232 Th and 40 K, respectively. From the analysis of the spatial distribution of 232 Th, 226 Ra, and 40 K is to north, to north-center, and to south of city, respectively. In conclusion, natural background gamma dose received by inhabitants of Chihuahua City is high and mainly due to geological characteristics of the zone. (Author)

Assessment of temporal trend of radiation dose to the public living in the large area contaminated with radioactive materials after a nuclear power plant accident

Energy Technology Data Exchange (ETDEWEB)

Go, A Ra; Kim, Min Jun; Kim, Kwang Pyo [Dept. of Nuclear Engineering, Kyung Hee University, Seoul (Korea, Republic of); Cho, Nam Chan; Seol, Jeung Gun [Radiation Safety Team, Korea Electric Power Corporation Nuclear Fuel, Seoul (Korea, Republic of)

2015-12-15

It has been about 5 years since the Fukushima nuclear power plant accident, which contaminated large area with radioactive materials. It is necessary to assess radiation dose to establish evacuation areas and to set decontamination goal for the large contaminated area. In this study, we assessed temporal trend of radiation dose to the public living in the large area contaminated with radioactive materials after the Fukushima nuclear power plant accident. The dose assessment was performed based on Chernobyl model and RESRAD model for two evacuation lift areas, Kawauchi and Naraha. It was reported that deposition densities in the areas were 4.3-96 kBq m{sup -2} for {sup 134}Cs, 1.4-300 kBq m{sup -2} for {sup 137}Cs, respectively. Radiation dose to the residents depended on radioactive cesium concentrations in the soil, ranging 0.11-2.4 mSv y{sup -1} at Kawauchi area and 0.69-1.1 mSv y{sup -1} at Naraha area in July 2014. The difference was less than 5% in radiation doses estimated by two different models. Radiation dose decreased with calendar time and the decreasing slope varied depending on dose assessment models. Based on the Chernobyl dosimetry model, radiation doses decreased with calendar time to about 65% level of the radiation dose in 2014 after 1 year, 11% level after 10 years, and 5.6% level after 30 years. RESRAD dosimetry model more slowly decreased radiation dose with time to about 85% level after 1 year, 40% level after 10 years, and 15% level after 30 years. The decrease of radiation dose can be mainly attributed into radioactive decays and environmental transport of the radioactive cesium. Only environmental transports of radioactive cesium without consideration of radioactive decays decreased radiation dose additionally 43% after 1 year, 72% after 3 years, 80% after 10 years, and 83% after 30 years. Radiation doses estimated with cesium concentration in the soil based on Chernobyl dosimetry model were compared with directly measured radiation doses

Thermoluminescent dosimetry and assessment of personal dose

International Nuclear Information System (INIS)

Boas, J.F.; Martin, L.J.; Young, J.G.

1982-01-01

Thermoluminescence is discussed in terms of the energy band structure of a crystalline solid and the trapping of charge carriers by point defects. Some general properties of thermoluminescent materials used for dosimetry are outlined, with thermoluminescence of CaSO 4 :Dy being described in detail. The energy response function and the modification of the energy response of a dosimeter by shielding are discussed. The final section covers the connection between exposure, as recorded by a TLD badge, and the absorbed dose to various organs from gamma radiation in a uranium mine; the conversion from absorbed dose to dose equivalent; and uncertainties in assessment of dose equivalent

Environmental biodosimetry: a biologically relevant tool for ecological risk assessment and biomonitoring

Energy Technology Data Exchange (ETDEWEB)

Ulsh, B. E-mail: ulshb@mcmaster.ca; Hinton, T.G.; Congdon, J.D.; Dugan, L.C.; Whicker, F.W.; Bedford, J.S

2003-07-01

Biodosimetry, the estimation of received doses by determining the frequency of radiation-induced chromosome aberrations, is widely applied in humans acutely exposed as a result of accidents or for clinical purposes, but biodosimetric techniques have not been utilized in organisms chronically exposed to radionuclides in contaminated environments. The application of biodosimetry to environmental exposure scenarios could greatly improve the accuracy, and reduce the uncertainties, of ecological risk assessments and biomonitoring studies, because no assumptions are required regarding external exposure rates and the movement of organisms into and out of contaminated areas. Furthermore, unlike residue analyses of environmental media environmental biodosimetry provides a genetically relevant biomarker of cumulative lifetime exposure. Symmetrical chromosome translocations can impact reproductive success, and could therefore prove to be ecologically relevant as well. We describe our experience in studying aberrations in the yellow-bellied slider turtle as an example of environmental biodosimetry.

Iodine-129 Dose in LLW Disposal Facility Performance Assessments

International Nuclear Information System (INIS)

Wilhite, E.L.

1999-01-01

Iodine-129 has the lowest Performance Assessment derived inventory limit in SRS disposal facilities. Because iodine is concentrated in the body to one organ, the thyroid, it has been thought that dilution with stable iodine would reduce the dose effects of 129I.Examination of the dose model used to establish the Dose conversion factor for 129I shows that, at the levels considered in performance assessments of low-level waste disposal facilities, the calculated 129I dose already accounts for ingestion of stable iodine. At higher than normal iodine ingestion rates, the uptake of iodine by the thyroid itself decrease, which effectively cancels out the isotopic dilution effect

Assessment of doses to non-human biota: Review of developments and demonstration assessment for Olkiluoto repository

International Nuclear Information System (INIS)

Smith, K.; Robinson, C.

2006-12-01

This report provides a summary of work commissioned by Posiva Oy and undertaken by Enviros Consulting Ltd to support the development of a strategy for the assessment of environmental impacts from ionising radiation associated with the Olkiluoto waste repository, Finland, as part of the development of the Posiva Safety Case Portfolio. This project included a review of the development of international policies and standards related to protection of biota from the effects of ionizing radiation and of biota assessment methodologies, paying particular attention to those that have been applied to waste repository performance assessments. On the basis of this review, recommendations were developed on the most appropriate methodology to apply in order to assess the impact of radioactive releases from the planned spent fuel repository in Olkiluoto. A test-case was developed, in collaboration with staff from Posiva and Facilia AB, and an assessment was performed. The results and experience of which were analysed and summarised to develop recommendations for a future strategy. The test case highlighted some significant data gaps related to the assessment of impacts to both generic biota types and to interest species. In particular, concentration ratios for generic carnivorous mammals and migratory species such as moose that may consume food from multiple ecosystems and dose conversion factors for large burrowing (i.e. hibernating) mammals. However, in general terms, the dose rates predicted for all organism types were several orders of magnitude below those at which population effects would be expected to be observed and those at which effects on the individual may be anticipated. There would therefore be scope for simplifying the approach applied, although there would be value in performing a sensitivity analysis to ensure that the simplification is applied appropriately. There would also be value in ensuring consistency of the developing approach for non-human biota with

Assessment of doses to non-human biota: Review of developments and demonstration assessment for Olkiluoto repository

Energy Technology Data Exchange (ETDEWEB)

Smith, K. [Carol Robinson Enviros Consulting Ltd, Edinburgh (United Kingdom)

2006-12-15

This report provides a summary of work commissioned by Posiva Oy and undertaken by Enviros Consulting Ltd to support the development of a strategy for the assessment of environmental impacts from ionising radiation associated with the Olkiluoto waste repository, Finland, as part of the development of the Posiva Safety Case Portfolio. This project included a review of the development of international policies and standards related to protection of biota from the effects of ionizing radiation and of biota assessment methodologies, paying particular attention to those that have been applied to waste repository performance assessments. On the basis of this review, recommendations were developed on the most appropriate methodology to apply in order to assess the impact of radioactive releases from the planned spent fuel repository in Olkiluoto. A test-case was developed, in collaboration with staff from Posiva and Facilia AB, and an assessment was performed. The results and experience of which were analysed and summarised to develop recommendations for a future strategy. The test case highlighted some significant data gaps related to the assessment of impacts to both generic biota types and to interest species. In particular, concentration ratios for generic carnivorous mammals and migratory species such as moose that may consume food from multiple ecosystems and dose conversion factors for large burrowing (i.e. hibernating) mammals. However, in general terms, the dose rates predicted for all organism types were several orders of magnitude below those at which population effects would be expected to be observed and those at which effects on the individual may be anticipated. There would therefore be scope for simplifying the approach applied, although there would be value in performing a sensitivity analysis to ensure that the simplification is applied appropriately. There would also be value in ensuring consistency of the developing approach for non-human biota with

Technology Assessment and Roadmap for the Emergency Radiation Dose Assessment Program

International Nuclear Information System (INIS)

Turteltaub, K W; Hartman-Siantar, C; Easterly, C; Blakely, W

2005-01-01

A Joint Interagency Working Group (JIWG) under the auspices of the Department of Homeland Security Office of Research and Development conducted a technology assessment of emergency radiological dose assessment capabilities as part of the overall need for rapid emergency medical response in the event of a radiological terrorist event in the United States. The goal of the evaluation is to identify gaps and recommend general research and development needs to better prepare the Country for mitigating the effects of such an event. Given the capabilities and roles for responding to a radiological event extend across many agencies, a consensus of gaps and suggested development plans was a major goal of this evaluation and road-mapping effort. The working group consisted of experts representing the Departments of Homeland Security, Health and Human Services (Centers for Disease Control and the National Institutes of Health), Food and Drug Administration, Department of Defense and the Department of Energy's National Laboratories (see appendix A for participants). The specific goals of this Technology Assessment and Roadmap were to: (1) Describe the general context for deployment of emergency radiation dose assessment tools following terrorist use of a radiological or nuclear device; (2) Assess current and emerging dose assessment technologies; and (3) Put forward a consensus high-level technology roadmap for interagency research and development in this area. This report provides a summary of the consensus of needs, gaps and recommendations for a research program in the area of radiation dosimetry for early response, followed by a summary of the technologies available and on the near-term horizon. We then present a roadmap for a research program to bring present and emerging near-term technologies to bear on the gaps in radiation dose assessment and triage. Finally we present detailed supporting discussion on the nature of the threats we considered, the status of technology

Technology Assessment and Roadmap for the Emergency Radiation Dose Assessment Program

Energy Technology Data Exchange (ETDEWEB)

Turteltaub, K W; Hartman-Siantar, C; Easterly, C; Blakely, W

2005-10-03

A Joint Interagency Working Group (JIWG) under the auspices of the Department of Homeland Security Office of Research and Development conducted a technology assessment of emergency radiological dose assessment capabilities as part of the overall need for rapid emergency medical response in the event of a radiological terrorist event in the United States. The goal of the evaluation is to identify gaps and recommend general research and development needs to better prepare the Country for mitigating the effects of such an event. Given the capabilities and roles for responding to a radiological event extend across many agencies, a consensus of gaps and suggested development plans was a major goal of this evaluation and road-mapping effort. The working group consisted of experts representing the Departments of Homeland Security, Health and Human Services (Centers for Disease Control and the National Institutes of Health), Food and Drug Administration, Department of Defense and the Department of Energy's National Laboratories (see appendix A for participants). The specific goals of this Technology Assessment and Roadmap were to: (1) Describe the general context for deployment of emergency radiation dose assessment tools following terrorist use of a radiological or nuclear device; (2) Assess current and emerging dose assessment technologies; and (3) Put forward a consensus high-level technology roadmap for interagency research and development in this area. This report provides a summary of the consensus of needs, gaps and recommendations for a research program in the area of radiation dosimetry for early response, followed by a summary of the technologies available and on the near-term horizon. We then present a roadmap for a research program to bring present and emerging near-term technologies to bear on the gaps in radiation dose assessment and triage. Finally we present detailed supporting discussion on the nature of the threats we considered, the status of

Assessment methodology for radioactive effluents

International Nuclear Information System (INIS)

Anon.

1977-01-01

The objective of this environmental assessment is to define and rank the needs for controlling radioactive effluents from nuclear fuel cycle facilities. The assessment is based on environmental standards and dose-to-man calculations. The study includes three calculations for each isotope from each facility: maximum individual dose for a 50-year dose commitment from a 1-yr exposure according to the organ affected; population dose for a 50-yr dose commitment from a 1-yr exposure according to the organ affected; and annual dose rate for the maximally exposed individual. The relative contribution of a specific nuclide and source to the total dose provides a method of ranking the nuclides, which in turn identifies the sources that should receive the greatest control in the future. These results will be used in subsequent tasks to assess the environmental impact of the total nuclear fuel cycle

Assessment of environmental gamma radiation levels at locations having different source characteristics using TLDs

International Nuclear Information System (INIS)

Sahu, S.K.; Swarnkar, M.; Takale, R.A.; Shetty, P.G.; Pandit, G.G.; Puranik, V.D.

2012-01-01

Naturally occurring radionuclides are the major contributor to the total effective dose of ionizing radiation received by the population (UNSCEAR, 1993). The dose in environment thus depends largely on natural radiation than manmade or artificially produced radiation. In the last few decades, there is a growing concern all over the world about radiation and their exposure to population. Thus, it is a necessity to conduct frequent radiological environmental surveillance in order to assess population exposure accurately. Recently, application of thermoluminescence dosimeters (TLDs) has been extended to the measurement of mixed radiation field as encountered in the environment. The advantages of passive TL dosimeters for environmental monitoring are that they are small, cheap and do not require power supply during application. The passive TL dosimeters play an important role to provide data on natural background radiation and to determine the contribution to the dose to public from man-made sources. In the present study, three different sites were chosen to compare environmental gamma radiation levels in different scenarios. Kaiga has been chosen as site 1, where four unit of pressurized heavy water reactor (PHWR) of 220 MWe each are in operation. Site 2 is chosen at natural high background radiation area (NHBRA) of Kerala and Vishakhapatnam was chosen as site 3, which is situated at a normal background area. The objective of the study is to illustrate the effect, if any, of an operating nuclear power reactor on environmental gamma radiation levels

Emergency preparedness in Finland: improvement of the measurement equipment used in the assessment of internal doses

Energy Technology Data Exchange (ETDEWEB)

Muikku, M.; Rahola, T. [STUK - Radiation and nuclear safety authority, Helsinki (Finland)

2006-07-01

The need for assessing internal radiation doses in emergency situations is evident. Internal exposure can be assessed using direct measurement results or by using information on activity concentrations in inhaled air and in foodstuffs combined with inhalation and consumption data. As a part of the continuous improving of emergency preparedness in Finland, S.T.U.K. - Radiation and Nuclear Safety Authority has obtained 35 monitors for thyroid measurements in field conditions and initiated a project to revise the radiation measurement equipment in local food and environmental laboratories. (authors)

Environmental assessment: challenges and opportunities

International Nuclear Information System (INIS)

Hilbig, J.; Moffett, D.; Beri, K.

2007-01-01

As part of a $4.5 billion investment,Bruce Power is refurbishing Bruce A Units 1 and 2, having successfully completed an environmental assessment to return these units to service after a lay-up of almost 10 years. The project includes implementing a series of refurbishments and upgrades which will enhance safety, increase electricity generation capacity and improve reliability for the 30-year extended life of the units. This paper describes four challenges that were successfully managed during the extensive environmental assessment: (i) defining the scope of the Project; (ii) understanding the EA trigger under the Canadian Environmental Assessment Act; (iii) maintaining an effective relationship with the regulatory agencies; and (iv) managing stakeholder communications. (author)

Environmental assessment: challenges and opportunities

International Nuclear Information System (INIS)

Hilbig, J.; Moffett, D.; Beri, K.

2007-01-01

As part of a $4.5 billion investment, Bruce Power is refurbishing Bruce A Units 1 and 2, having successfully completed an environmental assessment to return these units to service after a lay-up of almost 10 years. The project includes implementing a series of refurbishments and upgrades which will enhance safety, increase electricity generation capacity and improve reliability for the 30-year extended life of the units. This paper describes four challenges that were successfully managed during the extensive environmental assessment: (i) defining the scope of the Project; (ii) understanding the EA trigger under the Canadian Environmental Assessment Act; (iii) maintaining an effective relationship with the regulatory agencies; and (iv) managing stakeholder communications. (author)

A dose assessment for a U.S. nuclear test site -- Bikini Atoll

International Nuclear Information System (INIS)

Robison, W.L.; Bogen, K.T.; Conrado, C.L.

1993-07-01

On March 1, 1954, a nuclear weapon test, code-named BRAVO, conducted at Bikini Atoll in the northern Marshall Islands contaminated the major residence island. Here the authors provide a radiological dose assessment for the main residence island, Bikini, using extensive radionuclide concentration data derived from analysis of food crops, ground water, cistern water, fish and other marine species, animals, air, and soil collected at Bikini Island. The unique composition of coral soil greatly alters the relative contribution of cesium-137 and strontium-90 to the total estimated dose relative to expectations based on North American and European soils. Cesium-137 produces 96% of the estimated dose for returning residents, mostly through uptake from the soil to terrestrial food crops but also from external gamma exposure. The estimated maximum annual effective dose is 4.4 mSv y -1 when imported foods, which are now an established part of the diet, are available. The 30-, 50-, and 70-y integral effective doses are 10 cSv, 14 cSv, and 16 cSv, respectively. An analysis of interindividual variability in 0- to 30-y expected integral dose indicates that 95% of Bikini residents would have expected doses within a factor of 3.4 above and 4.8 below the population-average value. A corresponding uncertainty analysis showed that after about 5 y of residence, the 95% confidence limits on population-average dose would be ±35% of its expected value. The authors have evaluated various countermeasures to reduce 137 Cs in food crops. Treatment with potassium reduces the uptake of 137 Cs into food crops, and therefore the ingestion dose, to less than 10% of pretreatment levels and has essentially no negative environmental consequences

Relationship between dose and risk, and assessment of carcinogenic risks associated with low doses of ionizing radiation

International Nuclear Information System (INIS)

Tubiana, M.; Aurengo, A.

2005-01-01

This report raises doubts on the validity of using LNT (linear no-threshold) relationship for evaluating the carcinogenic risk of low doses (< 100 mSv) and even more for very low doses (< 10 mSv). The LNT concept can be a useful pragmatic tool for assessing rules in radioprotection for doses above 10 mSv; however since it is not based on biological concepts of our current knowledge, it should not be used without precaution for assessing by extrapolation the risks associated with low and even more so, with very low doses (< 10 mSv), especially for benefit-risk assessments imposed on radiologists by the European directive 97-43. The biological mechanisms are different for doses lower than a few dozen mSv and for higher doses. The eventual risks in the dose range of radiological examinations (0.1 to 5 mSv, up to 20 mSv for some examinations) must be estimated taking into account radiobiological and experimental data. An empirical relationship which has been just validated for doses higher than 200 mSv may lead to an overestimation of risks (associated with doses one hundred fold lower), and this overestimation could discourage patients from undergoing useful examinations and introduce a bias in radioprotection measures against very low doses (< 10 mSv). Decision makers confronted with problems of radioactive waste or risk of contamination, should re-examine the methodology used for the evaluation of risks associated with very low doses and with doses delivered at a very low dose rate. This report confirms the inappropriateness of the collective dose concept to evaluate population irradiation risks

Research toward the development of a biologically based dose response assessment for inorganic arsenic carcinogenicity: A progress report

International Nuclear Information System (INIS)

Clewell, Harvey J.; Thomas, Russell S.; Gentry, P. Robinan; Crump, Kenny S.; Kenyon, Elaina M.; El-Masri, Hisham A.; Yager, Janice W.

2007-01-01

Cancer risk assessments for inorganic arsenic have been based on human epidemiological data, assuming a linear dose response below the range of observation of tumors. Part of the reason for the continued use of the linear approach in arsenic risk assessments is the lack of an adequate biologically based dose response (BBDR) model that could provide a quantitative basis for an alternative nonlinear approach. This paper describes elements of an ongoing collaborative research effort between the CIIT Centers for Health Research, the U.S. Environmental Protection Agency, ENVIRON International, and EPRI to develop BBDR modeling approaches that could be used to inform a nonlinear cancer dose response assessment for inorganic arsenic. These efforts are focused on: (1) the refinement of physiologically based pharmacokinetic (PBPK) models of the kinetics of inorganic arsenic and its metabolites in the mouse and human; (2) the investigation of mathematical solutions for multi-stage cancer models involving multiple pathways of cell transformation; (3) the review and evaluation of the literature on the dose response for the genomic effects of arsenic; and (4) the collection of data on the dose response for genomic changes in the urinary bladder (a human target tissue for arsenic carcinogenesis) associated with in vivo drinking water exposures in the mouse as well as in vitro exposures of both mouse and human cells. An approach is proposed for conducting a biologically based margin of exposure risk assessment for inorganic arsenic using the in vitro dose response for the expression of genes associated with the obligatory precursor events for arsenic tumorigenesis

Determination of the equivalent of environmental dose, H*(d), in a radiotherapy installation

International Nuclear Information System (INIS)

Lima, M.A.F.; Borges, J.C.; Mota, H.C.

1998-01-01

In order to put into practice radiological protection has been required conversion factors for environmental dose equivalent determination to air kerma value for different kinds of photon and electron beams, such dose values have been determined in a spheric phantom of 30 cm diameter in a alignment field and expanded in a depth of this sphere. Details will be given for determining of equivalent dose distribution calculation using Monte Carlo computational method (ESG4) following the recommendations of ICRU. (Author)

Indicator system for the environmental assessment of energy transport systems

International Nuclear Information System (INIS)

Knoepfel, I.

1995-01-01

The aim of this dissertation is to define a consistent set of indicators for the environmental assessment of different energy transport systems: high-voltage alternating and direct current transmission lines, electric cables, pipelines for gas and oil, inland waterway, road and rail transportation, according to state-of-the-art technologies. The indicator system is used for comparative analysis and identification of environmental hot-spots of the different systems. The environmental performance of power plants close to production or unloading terminals with subsequent power transmission and the transport of fossil fuels with power production close to the end-users is compared. Quantitative indicators are defined for different impact categories: fossil energy depletion, impacts from emissions, land use, noise impacts and visibility. A further aggregation of the different indicators to obtain a universal environmental score was not envisaged. It was not possible to define a quantitative indicator for possible electric and magnetic field effects because of insufficient knowledge of the involved dose-response metrics. The proposed indicators quantify dose-response relationships also below emission or immission limits imposed by law, which was one of the main requirements in this work. By reducing all information to an equivalent impacted area, a high level of consistency was achieved for land use, noise impacts and visibility indicators. Other indicators refer to the energy content of fossil resources and to equivalent emissions of reference substances. The calculation of an equivalent impacted area was not considered an efficient approach in these cases. The performance of the proposed indicator system and its applicability to infrastructure and regional planning is tested in two practical examples. (author) figs., tabs., refs

Improvement of Off-site Dose Assessment Code for Operating Nuclear Power Plant

Energy Technology Data Exchange (ETDEWEB)

Kim, Juyub; Kim, Juyoul; Shin, Kwangyoung [FNC Technology Co. Ltd., Yongin (Korea, Republic of); You, Songjae; Moon, Jongyi [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

2014-05-15

XOQDOQ code which calculates atmospheric Dispersion factor was included into INDAC also. A research on the improvement of off-site dose assessment system for an operating nuclear power plant was performed by KINS in 2011. As a result, following improvements were derived: - Separation of dose assessment for new and existing facilities - Update of food ingestion data - Consideration of multi-unit operation and so on In order to reflect the results, INDAC is under modification. INDAC is an integrated dose assessment code for an operating nuclear power plant and consists of three main modules: XOQDOQ, GASDOS and LIQDOS. The modules are under modification in order to improve the accuracy of assessment and usability. Assessment points for multi-unit release can be calculated through the improved code and the method on dose assessment for multi-unit release has been modified, so that the dose assessment result of multi-unit site becomes more realistic by relieving excessive conservatism. Finally, as the accuracy of calculation modules has been improved, the reliability of dose assessment result has been strengthened.

Development of Landscape Dose Factors for dose assessments in SR-Can

Energy Technology Data Exchange (ETDEWEB)

Avila, Rodolfo; Ekstroem, Per-Anders [Facilia AB, Bromma (Sweden); Kautsky, Ulrik [Swedish Nuclear Fuel and Waste Management Co., Stockholm (Sweden)

2006-08-15

discrete events, by substituting one model by another. All radionuclides of relevance for safety assessments, except for C-14, are included in the study. Predictions of the long-term distribution in the landscape resulting from unit continuous release rates with groundwater discharges are presented for each studied radionuclide. In the main calculation variant, the releases are assumed to start at the beginning of the simulation period; and distributed between the landscape objects according to release fractions obtained from analyses of the results of the hydrological modelling. Additionally, to study the effect of the start time and location of the releases, a series of complementary simulation variants are carried out in different environmental media, comprising soils, waters and sediments. The predictions of the distribution of the radionuclides in the landscape per unit release rates are used to derive time-dependent dose conversion factors for each landscape object and for the whole landscape. To ensure that the dose to a representative member of the public in the population is identified, calculations of the dose rate are made for population groups taken to occupying a single landscape object and obtain all their resources from that object. The number of individuals that can be sustained by a landscape object is calculated for each time period by dividing the potential food production by the yearly food demand of a reference adult person. The average Dose Conversion Factors, i.e. the LDFs, for different groups in the landscape, including the most exposed group are derived, which take into account the distribution of radionuclides in the whole landscape. For each radionuclide derived maximum LDF values are given for the two studied sites, Forsmark and Laxemar. The derived maximum LDF values estimate effective dose rates to the most exposed population group per unit release of activity from a repository. By multiplying these factors by estimates of the release rates

The assessment of effects of low doses of ionizing radiations: contributions of epidemiology

International Nuclear Information System (INIS)

Verger, P.; Hubert, Ph.; Bard, D.

1998-01-01

After a brief recall of the history of the application of epidemiological studies to the field of ionizing radiations (actually to study the consequences of Hiroshima and Nagasaki bombing), and after having outlined that most of these epidemiological studies addressed carcinogenic effects of radiations on populations exposed to doses greater than 0,2 Gy, this article more particularly addresses epidemiological studies for low doses (lower than 0,5-1 Gy). The authors present objectives and methods (monitoring, etiological research, risk quantification), and discuss the limitations of epidemiology and its strengths. In the next part, they comment and discuss the main data sources used for the epidemiological assessment of low doses. These sources respectively deal with Hiroshima and Nagasaki (the Life Span Study, its results in terms of solid cancers and leukaemia, its limitations), with occupational exposures (radiologists, workers in nuclear installations, crews of intercontinental flights, Chernobyl liquidators, uranium minors exposed to radon), with environmental exposures (domestic exposures to radon, exposure to natural radiation, to nuclear test fallouts, and to Chernobyl accident fallouts, exposure about nuclear installations), and with other types of exposure

An environmental dose experiment

Science.gov (United States)

Peralta, Luis

2017-11-01

Several radiation sources worldwide contribute to the delivered dose to the human population. This radiation also acts as a natural background when detecting radiation, for instance from radioactive sources. In this work a medium-sized plastic scintillation detector is used to evaluate the dose delivered by natural radiation sources. Calibration of the detector involved the use of radioactive sources and Monte Carlo simulation of the energy deposition per disintegration. A measurement of the annual dose due to background radiation to the body was then estimated. A dose value compatible with the value reported by the United Nations Scientific Committee on the Effects of Atomic Radiation was obtained.

An environmental dose experiment

International Nuclear Information System (INIS)

Peralta, Luis

2017-01-01

Several radiation sources worldwide contribute to the delivered dose to the human population. This radiation also acts as a natural background when detecting radiation, for instance from radioactive sources. In this work a medium-sized plastic scintillation detector is used to evaluate the dose delivered by natural radiation sources. Calibration of the detector involved the use of radioactive sources and Monte Carlo simulation of the energy deposition per disintegration. A measurement of the annual dose due to background radiation to the body was then estimated. A dose value compatible with the value reported by the United Nations Scientific Committee on the Effects of Atomic Radiation was obtained. (paper)

How strategic environmental assessment can inform lenders about potential environmental risks

DEFF Research Database (Denmark)

Banhalmi-Zakar, Zsuzsa; Larsen, Sanne Vammen

2015-01-01

at a time when it can be used as an input to bank lending decisions, which can assist banks in making lending decisions with better environmental outcomes. For these reasons, we argue that in some circumstances, and particularly for project finance transactions, SEA may be a more useful environmental......In this paper, we explore the potential for strategic environmental assessment (SEA) to be a useful tool for banks to manage environmental risks and inform lending decisions. SEA is an environmental assessment tool that was developed to assist strategic-level decision-makers, such as policy...

Monitoring and radiation dose estimation for internal contamination of occupational workers

Energy Technology Data Exchange (ETDEWEB)

Kol, R; Laichter, Y [Israel Atomic Energy Commission, Beersheba (Israel). Nuclear Research Center-Negev

1996-12-01

The assessment of interval radiation doses due to intake of radionuclides differs totally from external dosimetry. External dosimetry is relatively straight forward: Workers are equipped with appropriate dosimeters that give the dose upon direct reading. Internal dosimetry is actually an assessment of the dose based on results of personnel and environmental monitoring (authors).

Personal monitoring and assessment of doses received by radiation workers

International Nuclear Information System (INIS)

Swindon, T.N.; Morris, N.D.

1981-12-01

The Personal Radiation Monitoring Service operated by the Australian Radiation Laboratory is outlined and the types of monitors used for assessment of doses received by radiation workers are described. The distribution of doses received by radiation workers in different occupational categories is determined. From these distributions, the average doses received have been assessed and the maximum likely additional increase in cancer deaths in Australia as a result of occupational exposure estimated. This increase is shown to be very small. There is, however, a considerable spread of doses received by individuals within occupational groups

Radionuclide releases to the atmosphere from Hanford Operations, 1944--1972. Hanford Environmental Dose Reconstruction Project

Energy Technology Data Exchange (ETDEWEB)

Heeb, C.M.

1994-05-01

The purpose of the Hanford Environmental Dose Reconstruction Project is to estimate the radiation dose that individuals could have received as a result of radionuclide emissions since 1944 from the Hanford Site. The first step in determining dose is to estimate the amount and timing of radionuclide releases to air and water. This report provides the air release information.

Establish the Foundation of Environmental Assessment Technique in ROK via the International Environmental Modelling for Radiation Safety Managed by IAEA

Energy Technology Data Exchange (ETDEWEB)

Lee, Han Soo; Choi, Y. H.; Keum, D. K.; Kang, H. S.; Ahn, S. S.; Chung, Y. S.; Lee, C. W.; Hwang, W. T.; Seo, K. S

2005-08-15

Tritiated water (HTO) released from the nuclear facilities can easily be absorbed by plants via their stomata and incorporated into organics by metabolic processes such as photosynthesis. Organically bound tritium (OBT) in plant cells is mostly inexchangeable and remains at harvest to contribute some to the ingestion radiation dose (Barry et al., 1999). In assessing the ingestion dose due to an accidental release of HTO, a dynamic model simulating its environmental behaviors is needed. Various types of dynamic HTO models have been developed in many different countries. Joint international researches have been conducted many times for model comparisons and validations (BIOMOVS II, 1996a, 1996b). In 2003, however, with the understanding of an insufficiency in the validation test, the IAEA started on a joint international research program for the validation of environmental models (EMRAS : Environmental Modelling for Radiation Safety) as a successor to the BIOMASS (2001). The KAERI submitted 'a scenario of an acute soybean exposure to HTO' to the Tritium Working Group (Theme 1) in the EMRAS program. It was accepted as Task 2 of the working group. This report is the result of a joint research for the KAERI scenario carried out by the EMRAS tritium working group with the KAERI playing a role of a coordinator.

Establish the Foundation of Environmental Assessment Technique in ROK via the International Environmental Modelling for Radiation Safety Managed by IAEA

International Nuclear Information System (INIS)

Lee, Han Soo; Choi, Y. H.; Keum, D. K.; Kang, H. S.; Ahn, S. S.; Chung, Y. S.; Lee, C. W.; Hwang, W. T.; Seo, K. S.

2005-08-01

Tritiated water (HTO) released from the nuclear facilities can easily be absorbed by plants via their stomata and incorporated into organics by metabolic processes such as photosynthesis. Organically bound tritium (OBT) in plant cells is mostly inexchangeable and remains at harvest to contribute some to the ingestion radiation dose (Barry et al., 1999). In assessing the ingestion dose due to an accidental release of HTO, a dynamic model simulating its environmental behaviors is needed. Various types of dynamic HTO models have been developed in many different countries. Joint international researches have been conducted many times for model comparisons and validations (BIOMOVS II, 1996a, 1996b). In 2003, however, with the understanding of an insufficiency in the validation test, the IAEA started on a joint international research program for the validation of environmental models (EMRAS : Environmental Modelling for Radiation Safety) as a successor to the BIOMASS (2001). The KAERI submitted 'a scenario of an acute soybean exposure to HTO' to the Tritium Working Group (Theme 1) in the EMRAS program. It was accepted as Task 2 of the working group. This report is the result of a joint research for the KAERI scenario carried out by the EMRAS tritium working group with the KAERI playing a role of a coordinator

Improving the risk assessment of lipophilic persistent environmental chemicals in breast milk.

Science.gov (United States)

Lehmann, Geniece M; Verner, Marc-André; Luukinen, Bryan; Henning, Cara; Assimon, Sue Anne; LaKind, Judy S; McLanahan, Eva D; Phillips, Linda J; Davis, Matthew H; Powers, Christina M; Hines, Erin P; Haddad, Sami; Longnecker, Matthew P; Poulsen, Michael T; Farrer, David G; Marchitti, Satori A; Tan, Yu-Mei; Swartout, Jeffrey C; Sagiv, Sharon K; Welsh, Clement; Campbell, Jerry L; Foster, Warren G; Yang, Raymond S H; Fenton, Suzanne E; Tornero-Velez, Rogelio; Francis, Bettina M; Barnett, John B; El-Masri, Hisham A; Simmons, Jane Ellen

2014-08-01

Lipophilic persistent environmental chemicals (LPECs) have the potential to accumulate within a woman's body lipids over the course of many years prior to pregnancy, to partition into human milk, and to transfer to infants upon breastfeeding. As a result of this accumulation and partitioning, a breastfeeding infant's intake of these LPECs may be much greater than his/her mother's average daily exposure. Because the developmental period sets the stage for lifelong health, it is important to be able to accurately assess chemical exposures in early life. In many cases, current human health risk assessment methods do not account for differences between maternal and infant exposures to LPECs or for lifestage-specific effects of exposure to these chemicals. Because of their persistence and accumulation in body lipids and partitioning into breast milk, LPECs present unique challenges for each component of the human health risk assessment process, including hazard identification, dose-response assessment, and exposure assessment. Specific biological modeling approaches are available to support both dose-response and exposure assessment for lactational exposures to LPECs. Yet, lack of data limits the application of these approaches. The goal of this review is to outline the available approaches and to identify key issues that, if addressed, could improve efforts to apply these approaches to risk assessment of lactational exposure to these chemicals.

Environmental impact assessment: Process and implementation

International Nuclear Information System (INIS)

Chen, S.Y.; Tsai, S.Y.

1989-01-01

In this paper, the procedures and issues regarding the preparation of an environmental impact assessment in accordance with the National Environmental Policy Act (NEPA) as promulgated by the US Congress in 1969 are discussed. NEPA procedures and requirements are covered in general, while particular attention is given to the preparation of the environmental impact assessment. Also included is a discussion of the social impact assessment. The aim of the social impact assessment is to address the social issues involved in enhancing public understanding of the hazardous risks, thereby mitigating any conflicts that may arise in the NEPA process. 3 refs., 1 fig., 1 tab

Committed dose assessment based on background outdoor gamma exposure in Chihuahua City, Mexico

Energy Technology Data Exchange (ETDEWEB)

Luevano G, S.; Perez T, A.; Pinedo A, C.; Renteria V, M. [Universidad Autonoma de Chihuahua, Facultad de Zootecnia y Ecologia, Perif. Francisco R. Almada Km 1, 31415 Chihuahua, Chih. (Mexico); Carrillo F, J.; Montero C, M. E., E-mail: mrenteria@uach.mx [Centro de Investigacion en Materiales Avanzados, Miguel de Cervantes 120, 31136 Chihuahua, Chih. (Mexico)

2015-10-15

Full text: Determining ionizing radiation in a geographic area serves to assess its effects on populations health. The aim of this study was to evaluate the spatial distribution of the background environmental outdoor gamma dose rates in Chihuahua City. This study also estimated the committed dose and the lifetime cancer risks of the population of this city. To determine the outdoor gamma dose rate in air, annual effective dose, and the lifetime cancer risk, 48 sampling points were randomly selected along the Chihuahua City. Outdoor gamma dose rate measurements were carried out by using a Geiger-Muller counter. At the same sites, 48 soil samples were taken to obtain the activity concentrations of {sup 226}Ra, {sup 232}Th, {sup 40}K and their terrestrial gamma dose rates. Radioisotope activity concentrations were determined by gamma spectrometry. Outdoor gamma dose rates ranged from 56 to 193 n Gy h{sup -1}. Results indicated that lifetime effective dose to inhabitants of Chihuahua City is in average of 19.8 mSv, resulting in a lifetime cancer risk of 0.001. In addition, the mean of activity concentrations in soil were 51.8, 73.1, and 1096.5 Bq kg{sup -1}, of {sup 226}Ra, {sup 232}Th and {sup 40}K, respectively. From the analysis of the spatial distribution of {sup 232}Th, {sup 226}Ra, and {sup 40}K is to north, to north-center, and to south of city, respectively. In conclusion, natural background gamma dose received by inhabitants of Chihuahua City is high and mainly due to geological characteristics of the zone. (Author)

Strategic environmental assessment can help solve environmental impact assessment failures in developing countries

International Nuclear Information System (INIS)

Alshuwaikhat, Habib M.

2005-01-01

The current trend of industrialization and urbanization in developing nations has a huge impact on anthropogenic and natural ecosystems. Pollution sources increase with the expansion of cities and cause contamination of water, air and soil. The absence of urban environmental planning and management strategies has resulted in greater concern for future urban development. This paper advocates the adoption of strategic environmental assessment (SEA) as a means to achieve sustainable development in developing countries. It investigates project-level environmental impact assessment (EIA) and its limitations. The exploration of SEA and its features are addressed. The effective implementation of SEA can create a roadmap for sustainable development. In many developing countries, the lack of transparency and accountability and ineffective public participation in the development of the policy, plan and program (PPP) would be mitigated by the SEA process. Moreover, the proactive and broadly based characteristics of SEA would benefit the institutional development of the PPP process, which is rarely experienced in many developing countries. The paper also explores the prospects for SEA and its guiding principles in developing countries. Finally, the paper calls for a coordinated effort between all government, nongovernment and international organizations involved with PPPs to enable developing countries to pursue a path of sustainable development through the development and application of strategic environmental assessment

Environmental Sensitivity in Nuclear Emergencies in Rural and Semi-natural Environments. Report of Working Group 8, Environmental Sensitivity of EMRAS II Topical Heading Approaches for Assessing Emergency Situations. Environmental Modelling for RAdiation Safety (EMRAS II) Programme

International Nuclear Information System (INIS)

2013-11-01

Environmental assessment models are used for evaluating the radiological impact of actual and potential releases of radionuclides to the environment. They are essential tools for use in the regulatory control of routine discharges to the environment and also in planning measures to be taken in the event of accidental releases. They are also used for predicting the impact of releases which may occur far into the future, for example, from underground radioactive waste repositories. It is important to verify, to the extent possible, the reliability of the predictions of such models by comparison with measured values in the environment or by comparing them with the predictions of other models. The IAEA has been organizing programmes of international model testing since the 1980s. The programmes have contributed to a general improvement in models, in transfer data and in the capabilities of modellers in Member States. IAEA publications on this subject over the past three decades demonstrate the comprehensive nature of the programmes and record the associated advances which have been made. From 2009 to 2011, the IAEA organized a programme entitled Environmental Modelling for RAdiation Safety (EMRAS II), which concentrated on the improvement of environmental transfer models and the development of reference approaches to estimate the radiological impacts on humans, as well as on flora and fauna, arising from radionuclides in the environment. The following topics were addressed in nine working groups: Reference Approaches for Human Dose Assessment - Working Group 1: Reference Methodologies for Controlling Discharges of Routine Releases; - Working Group 2: Reference Approaches to Modelling for Management and Remediation at NORM and Legacy Sites; - Working Group 3: Reference Models for Waste Disposal Reference Approaches for Biota Dose Assessment; - Working Group 4: Biota Modelling; - Working Group 5: Wildlife Transfer Coefficient Handbook; - Working Group 6: Biota Dose

Environmental Assessment

OpenAIRE

The Inspection Panel

2017-01-01

The Inspection Panel, the World Bank’s independent accountability mechanism, has released the third report in its Emerging Lessons Series. The latest report identifies lessons from Panel cases related to environmental assessment (EA) issues. The Panel is an impartial fact-finding body, independent from the World Bank management and staff, reporting directly to the Board. In response to com...

Development of a real-time radiological dose assessment system

Energy Technology Data Exchange (ETDEWEB)

Han, Moon Hee; Lee, Young Bok; Kim, Eun Han; Suh, Kyung Suk; Hwang, Won Tae; Choi, Young Gil

1997-07-01

A radiological dose assessment system named FADAS has been developed. This system is necessary to estimated the radiological consequences against a nuclear accident. Mass-consistent wind field module was adopted for the generation of wind field over the whole domain using the several measured wind data. Random-walk dispersion module is used for the calculation of the distribution of radionuclides in the atmosphere. And volume-equivalent numerical integration method has been developed for the assessment of external gamma exposure given from a randomly distributed radioactive materials and a dose data library has been made for rapid calculation. Field tracer experiments have been carried out for the purpose of analyzing the site-specific meteorological characteristics and increasing the accuracy of wind field generation and atmospheric dispersion module of FADAS. At first, field tracer experiment was carried out over flat terrain covered with rice fields using the gas samplers which were designed and manufactured by the staffs of KAERI. The sampled gas was analyzed using gas chromatograph. SODAR and airsonde were used to measure the upper wind. Korean emergency preparedness system CARE was integrated at Kori 4 nuclear power plants in 1995. One of the main functions of CARE is to estimate the radiological dose. The developed real-time dose assessment system FADAS was adopted in CARE as a tool for the radiological dose assessment. (author). 79 refs., 52 tabs., 94 figs.

A study on the radiation and environmental safety -Development of a real-time radiological dose assessment system-

Energy Technology Data Exchange (ETDEWEB)

Han, Moon Heui; Lee, Yung Bok; Kim, Eun Han; Suh, Kyung Suk; Hwang, Won Tae [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1995-07-01

The real-time dose assessment system under development has been updated and the technology for tracer experiment has been established. The calculation of external gamma dose is the most difficult and time-consuming part of the dose calculations. The characteristics of external gamma exposure have been investigated and the method for reducing the calculation time has been devised. The internal exposure via the ingestion of the contaminated foodstuffs is one of the important pathways to the total radiological exposure. In the emergency, it is necessary to take an action such like food ban to protect the internal exposure. An algorithm for the interface between the real-time system and the food chain model has been provided. The second field tracer experiment over flat terrain has been carried out on a plain in Iksan city in Junrabook-Do. Sequential tracer sampler which can be sampled the tracer gas over arbitrary 12 time interval has been designed and manufactured. SF{sub 6} has been used as the tracer gas and the sampled gas has been analysed by gas-chromatographer. 55 figs, 32 tabs, 65 refs. (Author).

Environmental impact assessment of fish farm hatcheries ...

African Journals Online (AJOL)

Environmental impact assessment of fish farm hatcheries management in lower ... Environmental impact assessments were taken to determine the causes of ... Of significance of impact assessment were activities like air, traffic, noise, had ...

Assessment of prospective foodchain doses from radioactive discharges from BNFL Sellafield

International Nuclear Information System (INIS)

Ould-Dada, Z.; Tucker, S.; Webbe-Wood, D.; Mondon, K.; Hunt, J.

2002-01-01

This paper presents the method used by the UK Food Standards Agency (FSA) to assess the potential impact of proposed radioactive discharges from the Sellafield nuclear site on food and determine their acceptability. It explains aspects of a cautious method that has been adopted to reflect the UK government policy and uncertainties related to people's habits with regard to food production and consumption. Two types of ingestion doses are considered in this method: 'possible' and 'probable' doses. The method is specifically applied to Sellafield discharge limits and calculated possible and probable ingestion doses are presented and discussed. Estimated critical group ingestion doses are below the dose limit and constraint set for members of the public. The method may be subject to future amendments to take account of changes in government policy and the outcome of a recent Consultative Exercise on Dose Assessments carried out by FSA. Uncertainties inherent in dose assessments are discussed and quantified wherever possible

Calculation of the effective environmental dose rate for ESR and luminescence dating

International Nuclear Information System (INIS)

Brennan, B.J.

2001-01-01

The determination of the age of a sample using luminescence and ESR dating techniques requires knowledge of the sample's average effective environmental dose rate due to natural radiation sources (alpha, beta, gamma, and cosmic), and age estimates can never be more accurate than the estimate of this dose rate. The estimation process is often complicated by spatial and temporal inhomogeneities in the distribution of natural radiation sources. This paper discusses applications of radiation physics in modelling the effects of these inhomogeneities to ensure accurate estimation of the average dose rate for the sample. For natural alpha, beta, and gamma sources, 'dose point kernels' are employed in calculations using an assumed model for the spatial and temporal dependence of source concentrations. These three types of radiation have rather different penetration properties, with their typical effective ranges being multiples of 10 micrometre, 1 mm, and 100 mm respectively. For each type of radiation, applications are discussed where spatial inhomogeneity in the distribution of sources around and in a sample has a serious effect on the average dose rate to the sample. In some cases, (e.g. gamma dose estimation in 'lumpy' environments) lack of detailed knowledge precludes accurate modelling of the site for a particular sample, but useful statistical information can still be obtained. Temporal variation of radioactive source concentrations is usually coupled with spatial effects and can arise from processes such as parent-daughter disequilibrium, uptake or leaching of sources, or variation in burial depth or water saturation. Again, calculations based non a known or assumed history can be employed to obtain a time-averaged dose rate for a sample. The accuracy with which these calculations can reflect the true environmental dose rate is limited principally by the reliability of the model assumed, which in turn depends on the state of knowledge of the site and its history

Radiation environmental impact assessment of copper exploitation

International Nuclear Information System (INIS)

Fan Guang; Wen Zhijian

2010-01-01

The radiation environmental impact of mineral exploitation on the surrounding environment has become a public concern. This paper presents the radiation environmental impact assessment of copper exploitation. Based on the project description and detailed investigations of surrounding environment, systematic radiation environmental impacts have been identified. The environmental impacts are assessed during both construction and operation phase. The environmental protection measures have also been proposed. The related conclusion and measures can play an active role in copper exploitation and environmental protection. (authors)

Development of dose assessment code for accidental releases of activation products

International Nuclear Information System (INIS)

Noguchi, H.; Yokoyama, S.

2000-01-01

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

Mesorad dose assessment model. Volume 1. Technical basis

International Nuclear Information System (INIS)

Scherpelz, R.I.; Bander, T.J.; Athey, G.F.; Ramsdell, J.V.

1986-03-01

MESORAD is a dose assessment model for emergency response applications. Using release data for as many as 50 radionuclides, the model calculates: (1) external doses resulting from exposure to radiation emitted by radionuclides contained in elevated or deposited material; (2) internal dose commitment resulting from inhalation; and (3) total whole-body doses. External doses from airborne material are calculated using semi-infinite and finite cloud approximations. At each stage in model execution, the appropriate approximation is selected after considering the cloud dimensions. Atmospheric processes are represented in MESORAD by a combination of Lagrangian puff and Gaussian plume dispersion models, a source depletion (deposition velocity) dry deposition model, and a wet deposition model using washout coefficients based on precipitation rates

Methodologies of environmental impact assessment

International Nuclear Information System (INIS)

Schroll, H.

1994-01-01

This article gives a brief introduction covering the objectives of environmental impact assessment (EIA) and sustainable development, before going on to describe the screening procedure to define the environmental and socio-economic impacts of projects. The EIA procedure outlined encompasses a description of the project, examination of all environmental effects (scoping), identification of existing and predicted environmental conditions and impacts, alternative measures and mitigating measures, co-ordination, with environmental regulations, public participation, and monitoring and approval of the EIA. (UK)

A PROBABILISTIC EXPOSURE ASSESSMENT FOR CHILDREN WHO CONTACT CCA-TREATED PLAYSETS AND DECKS USING THE STOCHASTIC HUMAN EXPOSURE AND DOSE SIMULATION (SHEDS) MODEL FOR THE WOOD PRESERVATIVE EXPOSURE SCENARIO

Science.gov (United States)

The U.S. Environmental Protection Agency has conducted a probabilistic exposure and dose assessment on the arsenic (As) and chromium (Cr) components of Chromated Copper Arsenate (CCA) using the Stochastic Human Exposure and Dose Simulation model for wood preservatives (SHEDS-Wood...

16 CFR 260.8 - Environmental assessment.

Science.gov (United States)

2010-01-01

....8 Commercial Practices FEDERAL TRADE COMMISSION GUIDES AND TRADE PRACTICE RULES GUIDES FOR THE USE OF ENVIRONMENTAL MARKETING CLAIMS § 260.8 Environmental assessment. (a) National Environmental Policy... and analysis to determine whether issuing the Guides for the Use of Environmental Marketing Claims...

Potential radionuclide emissions from stacks on the Hanford Site. Part 1: Dose assessment

International Nuclear Information System (INIS)

Davis, W.E.; Barnett, J.M.

1994-06-01

On February 3, 1993, the US Department of Energy, Richland Operations Office (RL) received a Compliance Order and Information Request from the Director of the Air and Toxics Division of the US Environmental Protection Agency (EPA), Region 10. The Compliance Plan specified that a dose assessment would be performed for 84 Westinghouse Hanford Company (WHC) stacks registered with the Washington State Department of Health (WAC 246-247) on the Hanford Site. Stacks that have the potential emissions to cause an effective dose equivalent (EDE) to a maximum exposed individual (MEI) greater than 0.1 mrem y -1 must be monitored continuously for radionuclide emissions. Five methods were approved by EPA, Region 10 for performing the assessments: Release Fractions from Appendix D of 40 CFR 61, Back Calculations Using A HEPA Filtration Factor, Nondestructive Assay of HEPA Filters, A Spill Release Fraction, and Upstream of HEPA Filter Air Concentrations. The first two methods were extremely conservative for estimating releases. The third method which used a state-of-the-art portable gamma spectrometer, yielded surprising results from the distribution of radionuclides on the HEPA filters. All five methods are described

Framework for conducting environmental assessments of trade negotiations

International Nuclear Information System (INIS)

2001-02-01

This document described the complex task of assessing the environmental impacts of trade negotiations with particular emphasis on the framework of the Strategic Environmental Assessment which the Government of Canada will conduct through a systematic process which can identify and evaluate possible and significant environmental impacts of an initiative. The objective of the assessment is to integrate environmental considerations into decision-making processes at the earliest possible stage. The first part of the framework identifies the importance of recognizing environmental considerations of trade and explains how the framework will contribute to environmental policy. The second part of the framework outlines the process and analytical requirements for conducting an environmental assessment of a trade negotiation. Environmental Assessment Committees will be formed by the Department of Foreign Affairs and International Trade, and will include representatives from federal government departments and agencies. All analyses will be conducted in four stages which will include identifying the economic effect of the negotiation, identifying the likely environmental impact of such changes, assessing the significance of the likely environmental impacts, and identifying enhancement/mitigation options to inform the negotiations. The framework is designed to be flexible enough to be used at current and future trade negotiations in the World Trade Organization, the Free Trade Area of the Americas and in bilateral Free Trade Agreements. An environmental assessment of trade negotiations is considered to be an important decision-making tool for promoting sustainable development. 16 refs., 1 tab

The food chain and dose submodel, CALDOS, for the assessment of Canada's nuclear fuel waste management concept

International Nuclear Information System (INIS)

Zach, R.; Sheppard, S.C.

1992-12-01

The food chain and dose submodel, CALDOS, for assessing Canada's nuclear fuel management (NFWM) concept of disposal in a vault deep in the Canadian Shield is presented. Together with the surface water, soil and atmosphere submodels, CALDOS is integrated into a comprehensive, probabilistic biosphere model for post-closure assessment. This model is representative of the Canadian Shield in Ontario and CALDOS is fully generic. CALDOS calculates radionuclide transfer through the environment to make dose predictions for man. It considers 68 radionuclides explicitly and takes into account another 28 short-lived daughters in the dose calculations. Nine potentially toxic elements are also considered. CALDOS is of the multiplicative chain type for most of the radionuclides, but some, such as 3H , 129I and 222R n, are treated specially. The model accounts for all the major internal exposure pathways, including root uptake, leaf deposition, terrestrial animal's drinking water, terrestrial animal soil ingestion, freshwater fish ingestion, human drinking water, human soil ingestion and human inhalation. External exposure from air immersion, water immersion, ground and building materials are also considered. Dose predictions are based on the recommendations of the International Commission on Radiation Protection (ICRP 26) methodologies, ICRP reference man (ICRP 23) and the critical group concept. CALDOS considers ingrowth of some radioactive daughters, radionuclide availability in soil, recycling and depletion. The model has numerous parameters, some element, radionuclide or food type specific. Sensitivity analysis is used to assess parameter importance in dose prediction. Quality assurance is addressed through general literature, model and parameter evaluations, specifically designed for environmental assessment models. This also involves validation and code comparison studies. (author). 43 refs., 36 tabs., 24 figs

Distribution of exposure concentrations and doses for constituents of environmental tobacco smoke

Energy Technology Data Exchange (ETDEWEB)

LaKind, J.S. [LaKind Associates (United States); Ginevan, M.E. [M.E. Ginevan and Associates (United States); Naiman, D.Q. [Johns Hopkins Univ., Baltimore, MD (United States). Dept. of Mathematical Sciences; James, A.C. [A.C. James and Associates (United States); Jenkins, R.A. [Oak Ridge National Lab., TN (United States); Dourson, M.L.; Felter, S.P. [TERA (United States); Graves, C.G.; Tardiff, R.G. [Sapphire Group, Inc., Bethesda, MD (United States)

1999-06-01

The ultimate goal of the research reported in this series of three articles is to derive distributions of doses of selected environmental tobacco smoke (ETS)-related chemicals for nonsmoking workers. This analysis uses data from the 16-City Study collected with personal monitors over the course of one workday in workplaces where smoking occurred. In this article, the authors describe distributions of ETS chemical concentrations and the characteristics of those distributions for the workplace exposure. Next, they present population parameters relevant for estimating dose distributions and the methods used for estimating those dose distributions. Finally, they derive distributions of doses of selected ETS-related constituents obtained in the workplace for people in smoking work environments. Estimating dose distributions provided information beyond the usual point estimate of dose and showed that the preponderance of individuals exposed to ETS in the workplace were exposed at the low end of the dose distribution curve. The results of this analysis include estimations of hourly maxima and time-weighted average (TWA) doses of nicotine from workplace exposures to ETS and doses derived from modeled lung burdens of ultraviolet-absorbing particulate matter (UVPM) and solanesol resulting from workplace exposures to ETS (extrapolated from 1 day to 1 year).

Assessment of population external irradiation doses with consideration of Rospotrebnadzor bodies equipment for monitoring of photon radiation dose

Directory of Open Access Journals (Sweden)

I. P. Stamat

2016-01-01

Full Text Available This paper provides review of equipment and methodology for measurement of photon radiation dose; analysis of possible reasons for considerable deviation between the Russian Federation population annual effective external irradiation doses and the relevant average global value. Data on Rospotrebnadzor bodies dosimetry equipment used for measurement of gamma radiation dose are collected and systematized. Over 60 kinds of dosimeters are used for monitoring of population external irradiation doses. Most of dosimeters used in the country have gas-discharge detectors (Geiger-Mueller counters, minor biochemical annunciators, etc. which have higher total values of own background level and of space radiation response than the modern dosimeters with scintillation detectors. This feature of dosimeters is apparently one of most plausible reasons of a bit overstating assessment of population external irradiation doses. The options for specification of population external irradiation doses assessment are: correction of gamma radiation dose measurement results with consideration of dosimeters own background level and space radiation response, introduction of more up-to-date dosimeters with scintillation detectors, etc. The most promising direction of research in verification of population external irradiation doses assessment is account of dosimetry equipment.

Environmental impact assessment methods of the radiation generated by the runing medical linear accelerator

International Nuclear Information System (INIS)

Yin haihua; Yao Zhigang

2014-01-01

This article describes the environmental impact assessment methods of the radiation generated by the runing. medical linear accelerator. The material and thickness of shielding wall and protective doors of the linear accelerator were already knew, therefore we can evaluate the radiation by the runing. medical linear accelerator whether or not in the normal range of national standard by calculating the annual effective radiation dose of the surrounding personnel suffered. (authors)

Research and assessment of national population dose

International Nuclear Information System (INIS)

Pan Ziqiang

1984-01-01

This article describes the necessity and probability of making researches on assessment of national population dose, and discusses some problems which might be noticeable in the research work. (author)

Calculational Tool for Skin Contamination Dose Assessment

CERN Document Server

Hill, R L

2002-01-01

Spreadsheet calculational tool was developed to automate the calculations preformed for dose assessment of skin contamination. This document reports on the design and testing of the spreadsheet calculational tool.

Assessment and recording of radiation doses to workers

International Nuclear Information System (INIS)

1986-01-01

The assessment and recording of the radiation exposure of workers in activities involving radiation risks are required for demonstrating compliance with institutional dose limitations and for a number of other complementary purposes. A significant proportion of the labor force involved in radiation work is currently represented by those specialised workers who operate as itinerant contractors for different nuclear installations and in different countries. In order to ensure that the exposure of these workers is adequately and consistently controlled and kept within acceptable limits, there is a need for the criteria and methods for dose assessment and recording to be harmonised throughout the different countries. An attempt in that direction has been made in this report, which has been prepared by a group of experts convened by the Committee on Radiation Protection and Public Health of the OECD Nuclear Energy Agency. Its primary purpose is to describe recommended technical procedures for an unified approach to the assessment and recording of worker doses. The report is published under the responsibility of the Secretary-General of the OECD, and does not commit Member governments

Disability adjusted life year (DALY): a useful tool for quantitative assessment of environmental pollution.

Science.gov (United States)

Gao, Tingting; Wang, Xiaochang C; Chen, Rong; Ngo, Huu Hao; Guo, Wenshan

2015-04-01

Disability adjusted life year (DALY) has been widely used since 1990s for evaluating global and/or regional burden of diseases. As many environmental pollutants are hazardous to human health, DALY is also recognized as an indicator to quantify the health impact of environmental pollution related to disease burden. Based on literature reviews, this article aims to give an overview of the applicable methodologies and research directions for using DALY as a tool for quantitative assessment of environmental pollution. With an introduction of the methodological framework of DALY, the requirements on data collection and manipulation for quantifying disease burdens are summarized. Regarding environmental pollutants hazardous to human beings, health effect/risk evaluation is indispensable for transforming pollution data into disease data through exposure and dose-response analyses which need careful selection of models and determination of parameters. Following the methodological discussions, real cases are analyzed with attention paid to chemical pollutants and pathogens usually encountered in environmental pollution. It can be seen from existing studies that DALY is advantageous over conventional environmental impact assessment for quantification and comparison of the risks resulted from environmental pollution. However, further studies are still required to standardize the methods of health effect evaluation regarding varied pollutants under varied circumstances before DALY calculation. Copyright © 2014 Elsevier B.V. All rights reserved.

Effect of postnatal low-dose exposure to environmental chemicals on the gut microbiome in a rodent model.

Science.gov (United States)

Hu, Jianzhong; Raikhel, Vincent; Gopalakrishnan, Kalpana; Fernandez-Hernandez, Heriberto; Lambertini, Luca; Manservisi, Fabiana; Falcioni, Laura; Bua, Luciano; Belpoggi, Fiorella; L Teitelbaum, Susan; Chen, Jia

2016-06-14

This proof-of-principle study examines whether postnatal, low-dose exposure to environmental chemicals modifies the composition of gut microbiome. Three chemicals that are widely used in personal care products-diethyl phthalate (DEP), methylparaben (MPB), triclosan (TCS)-and their mixture (MIX) were administered at doses comparable to human exposure to Sprague-Dawley rats from birth through adulthood. Fecal samples were collected at two time points: postnatal day (PND) 62 (adolescence) and PND 181 (adulthood). The gut microbiome was profiled by 16S ribosomal RNA gene sequencing, taxonomically assigned and assessed for diversity. Metagenomic profiling revealed that the low-dose chemical exposure resulted in significant changes in the overall bacterial composition, but in adolescent rats only. Specifically, the individual taxon relative abundance for Bacteroidetes (Prevotella) was increased while the relative abundance of Firmicutes (Bacilli) was reduced in all treated rats compared to controls. Increased abundance was observed for Elusimicrobia in DEP and MPB groups, Betaproteobacteria in MPB and MIX groups, and Deltaproteobacteria in TCS group. Surprisingly, these differences diminished by adulthood (PND 181) despite continuous exposure, suggesting that exposure to the environmental chemicals produced a more profound effect on the gut microbiome in adolescents. We also observed a small but consistent reduction in the bodyweight of exposed rats in adolescence, especially with DEP and MPB treatment (p gut microbiota in adolescent rats; whether these changes lead to downstream health effects requires further investigation.

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

Regional Environmental Monitoring and Assessment Program Data (REMAP)

Data.gov (United States)

U.S. Environmental Protection Agency — The Regional Environmental Monitoring and Assessment Program (REMAP) was initiated to test the applicability of the Environmental Monitoring and Assessment Program...

Dose assessment under incidental and accidental conditions

International Nuclear Information System (INIS)

Huebschmann, W.G.

1988-01-01

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

Dose assessment from potential radionuclide emissions from stacks on the Hanford Site

International Nuclear Information System (INIS)

Davis, W.E.; Barnett, J.M.

1995-04-01

On February 3, 1993, the US Department of Energy, Richland Operations Office (RL), received a Compliance Order and Information Request from the Director of the Air and Toxics Division of the US Environmental Protection Agency (EPA), Region 10. The Compliance Order required RL to (1) evaluate all radionuclide emission points at the Hanford Site to determine which points are subject to the continuous emission sampling requirements of Title 40, Code of Federal Regulations, Part 61 (40 CFR 61), Subpart H, and (2) continuously sample radionuclide emissions in accordance with requirements in 40 CFR 61.93. The Information Request required RL to provide a written Compliance Plan to meet the requirements of the Compliance Order. A Compliance Plan was submitted to EPA, Region 10, on April 30, 1993. The Compliance Plan specified that a dose assessment would be performed for 84 Westinghouse Hanford Company (WHC) stacks registered with the Washington State Department of Health on the Hanford Site. Any stack identified in the assessment as having potential emissions to cause an effective dose equivalent (EDE) to a maximum exposed individual (MEI) greater than 0.1 mrem y -1 must have a compliant sampling system. In addition, a Federal Facility Compliance Agreement (FFCA) was signed on. February 7, 1994. The FFCA required that all unregistered stacks on the Hanford Site be assessed. This requirement increased the number of stacks to be assessed to 123 stacks. Six methods for performing the assessments are described. An initial assessment using only the HEPA filtration factor for back calculations identified 32 stacks that would have emissions which would cause an EDE to the MEI greater than 0.1 mrem y -1 . When the other methods were applied the number was reduced to 20 stacks. The paper discusses reasons for these overestimates

Skin dose assessment in routine personnel beta/gamma dosimetry

International Nuclear Information System (INIS)

Christensen, P.

1980-01-01

The International Commission on Radiological Protection (Publication 26) has recommended a tissue depth of 5 to 10 mg.cm -2 for skin dose assessments. This requirement is generally not fulfilled by routine monitoring procedures because of practical difficulties in using very thin dosemeters with low sensitivity and therefore a high minimum detectable dose. Especially for low-energy beta-ray exposures underestimations of the skin dose by a factor of more than ten may occur. Low-transparent graphite-mixed sintered LiF and Li 2 B 4 0 7 : Mn dosemeters were produced which show a skin-equivalent response to beta and gamma exposures over a wide range of energies. These have found wide-spread application for extremity dosimetry but have not yet been generally introduced in routine personnel beta/gamma monitoring. The following adaptations of existing routine monitoring systems for improved skin dose assessments have been investigated: 1) Placement of a supplementary, thin, skin-dose equivalent dosemeter in the TLD badge to give additional information on low-energy exposures. 2) Introduction of a second photomultiplier in the read-out chamber which enables a simultaneous determination of emitted TL from both sides of the dosemeter separately. This method makes use of the selfshielding of the dosemeter to give information on the low-energy dose contribution. 3) By diffusion of Li 2 B 4 0 7 into solid LiF-dosemeters it was possible to produce a surface layer with a new distinct glow-peak at about 340 deg C which is not present in the undiffused part of the LiF chip, and which can be utilized for the assessment of the skin-dose. Data on energy response and accuracy of dose measurement for beta/gamma exposures are given for the three methods and advantages and disadvantages are discussed (H.K.)

Planning Environmental Impact Assessment Orienting Sustainable Development:Opportunities and Challenges

Institute of Scientific and Technical Information of China (English)

Sun Yanjun; Chen Xingeng; Bao Yun; Peng Xiaochun; Gao Changbo

2005-01-01

Strategic Environmental Assessment is a frontier subject in the field of Environmental Impact Assessment. In the past two decades, especially in recent years, much more importance has been attached to Strategic Environmental Assessment. The Environmental Impact Assessment Law of the P.R.China which was promulgated provides a great opportunity for the development of Planning Environmental Impact Assessment and brings great challenges for the development of traditional Project Environmental Impact Assessment and Planning Environmental Impact Assessment at the same time.In order to promote the implementation of"The EIA Law", the inherent limitations of Project Environmental Impact Assessment must be identified sufficiendy and the theory research and practice of Planning Environmental Impact Assessment should be strengthened as well. Measures should be taken currendy to enforce the operation system. The authors wish to offer a few references to the progress and implementation of Planning Environmental Impact Assessment in China.

Columbia River pathway report: phase I of the Hanford Environmental Dose Reconstruction Project

Energy Technology Data Exchange (ETDEWEB)

1991-07-01

This report summarizes the river-pathway portion of the first phase of the Hanford Environmental Dose Reconstruction (HEDR) Project. The HEDR Project is estimating radiation doses that could have been received by the public from the Department of Energy's Hanford Site, in southeastern Washington State. Phase 1 of the river-pathway dose reconstruction effort sought to determine whether dose estimates could be calculated for populations in the area from above the Hanford Site at Priest Rapids Dam to below the site at McNary Dam from January 1964 to December 1966. Of the potential sources of radionuclides from the river, fish consumption was the most important. Doses from drinking water were lower at Pasco than at Richland and lower at Kennewick than at Pasco. The median values of preliminary dose estimates calculated by HEDR are similar to independent, previously published estimates of average doses to Richland residents. Later phases of the HEDR Project will address dose estimates for periods other than 1964--1966 and for populations downstream of McNary Dam. 17 refs., 19 figs., 1 tab.

Environmental flow assessments for transformed estuaries

Science.gov (United States)

Sun, Tao; Zhang, Heyue; Yang, Zhifeng; Yang, Wei

2015-01-01

Here, we propose an approach to environmental flow assessment that considers spatial pattern variations in potential habitats affected by river discharges and tidal currents in estuaries. The approach comprises four steps: identifying and simulating the distributions of critical environmental factors for habitats of typical species in an estuary; mapping of suitable habitats based on spatial distributions of the Habitat Suitability Index (HSI) and adopting the habitat aggregation index to understand fragmentation of potential suitable habitats; defining variations in water requirements for a certain species using trade-off analysis for different protection objectives; and recommending environmental flows in the estuary considering the compatibility and conflict of freshwater requirements for different species. This approach was tested using a case study in the Yellow River Estuary. Recommended environmental flows were determined by incorporating the requirements of four types of species into the assessments. Greater variability in freshwater inflows could be incorporated into the recommended environmental flows considering the adaptation of potential suitable habitats with variations in the flow regime. Environmental flow allocations should be conducted in conjunction with land use conflict management in estuaries. Based on the results presented here, the proposed approach offers flexible assessment of environmental flow for aquatic ecosystems that may be subject to future change.

Long-Term Assessment of Critical Radionuclides and Associated Environmental Media at the Savannah River Site - 13038

Energy Technology Data Exchange (ETDEWEB)

Jannik, G.T.; Baker, R.A.; Lee, P.L. [Savannah River National Laboratory, Savannah River Site, Aiken, SC 29808 (United States); Eddy, T.P.; Blount, G.C. [Savannah River Nuclear Solutions, Savannah River Site, Aiken, SC 29808 (United States); Whitney, G.R. [US Department of Energy, Savannah River Operations, Aiken, SC 29808 (United States)

2013-07-01

During the operational history of the Savannah River Site (SRS), many different radionuclides have been released from site facilities. However, only a relatively small number of the released radionuclides have been significant contributors to doses and risks to the public. At SRS dose and risk assessments indicate tritium oxide in air and surface water, and Cs-137 in fish and deer have been, and continue to be, the critical radionuclides and pathways. In this assessment, statistical analyses of the long-term trends of tritium oxide in atmospheric and surface water releases and Cs-137 concentrations in fish and deer are provided. Correlations also are provided with 1) operational changes and improvements, 2) geopolitical events (Cold War cessation), and 3) recent environmental remediation projects and decommissioning of excess facilities. For example, environmental remediation of the F- and H-Area Seepage Basins and the Solid Waste Disposal Facility have resulted in a measurable impact on the tritium oxide flux to the onsite Fourmile Branch stream. Airborne releases of tritium oxide have been greatly affected by operational improvements and the end of the Cold War in 1991. However, the effects of SRS environmental remediation activities and ongoing tritium operations on tritium concentrations in the environment are measurable and documented in this assessment. Controlled hunts of deer and feral hogs are conducted at SRS for approximately six weeks each year. Before any harvested animal is released to a hunter, SRS personnel perform a field analysis for Cs-137 concentrations to ensure the Hunter's dose does not exceed the SRS administrative game limit of 0.22 milli-sievert (22 mrem). However, most of the Cs-137 found in SRS onsite deer is not from site operations but is from nuclear weapons testing fallout from the 1950's and early 1960's. This legacy source term is trended in the SRS deer, and an assessment of the 'effective' half-life of Cs

Radiation dose reduction in paediatric coronary computed tomography: assessment of effective dose and image quality

International Nuclear Information System (INIS)

Habib Geryes, Bouchra; Calmon, Raphael; Boddaert, Nathalie; Khraiche, Diala; Bonnet, Damien; Raimondi, Francesca

2016-01-01

To assess the impact of different protocols on radiation dose and image quality for paediatric coronary computed tomography (cCT). From January-2012 to June-2014, 140 children who underwent cCT on a 64-slice scanner were included. Two consecutive changes in imaging protocols were performed: 1) the use of adaptive statistical iterative reconstruction (ASIR); 2) the optimization of acquisition parameters. Effective dose (ED) was calculated by conversion of the dose-length product. Image quality was assessed as excellent, good or with significant artefacts. Patients were divided in three age groups: 0-4, 5-7 and 8-18 years. The use of ASIR combined to the adjustment of scan settings allowed a reduction in the median ED of 58 %, 82 % and 85 % in 0-4, 5-7 and 8-18 years group, respectively (7.3 ± 1.4 vs 3.1 ± 0.7 mSv, 5.5 ± 1.6 vs 1 ± 1.9 mSv and 5.3 ± 5.0 vs 0.8 ± 2.0 mSv, all p < 0,05). Prospective protocol was used in 51 % of children. The reduction in radiation dose was not associated with reduction in diagnostic image quality as assessed by the frequency of coronary segments with excellent or good image quality (88 %). cCT can be obtained at very low radiation doses in children using ASIR, and prospective acquisition with optimized imaging parameters. (orig.)

Environmental impact assessment - a selected bibliography

International Nuclear Information System (INIS)

Lawson, W.J.

1989-01-01

This bibliography of literature relevant to the environmental impact assessment process is essentially a list of material dealing with the environmental impact assessment process held by Griffith University Library. The list is however well supplemented with citations of material not held in the Griffith University Library. Some economic and social impact assessment citations have been included in the bibliography, as the the environmental impact assessment concept has been interpreted very broadly. The citations are arranged according to broad subject areas, such as methodology, critical reviews, social impacts etc. Citations in each of these subject areas, which are listed in the table of contents, are identified by prefixes which are given in parentheses before the subjects headings. Within each subject area the citations are arragend in alphabetic author sequence

Environmental Assessment of R&D Programmes

DEFF Research Database (Denmark)

Lyhne, Ivar; Byriel, Inger Pihl

2013-01-01

cause severe negative environmental impacts. This paper presents an innovative environmental assessment practice on R&D programmes in Denmark. It reports on the challenges and experiences of assessing the Danish R&D programme ForskEL, which promotes R&D projects within the electricity sector......Despite their important role in shaping the technologies of the future, public research and development (R&D) programmes are rarely based on systematic assessments of the environmental effects. R&D programmes thus allocate a huge amount of financial resources to projects, which potentially may....... The programme is characterised by uncertainty about impacts and incomparable project types and technologies. A methodology for dealing with these challenges is presented, and experiences from a testing of the methodology on the 2012 programme are reflected upon. Finally the assessment is discussed in terms...

Generic models and parameters for assessing the environmental transfer of radionuclides from routine releases

International Nuclear Information System (INIS)

1982-01-01

This report is addressed to national regulatory bodies and technical and administrative personnel responsible for performing environmental impact analyses, in particular for generic assessments of doses to most exposed individuals from routine releases of radioactive effluents to atmospheric and aquatic environments. The concern of society in general for the quality of the environment and the realization that all human activities have some environmental effect, in which actions and reactions are coupled in a complex but predictable manner, have led to the development of a procedure for environmental impact analysis. This procedure is a predictive one, which tries to forecast probable environmental effects before some action, such as the construction and operation of a nuclear power station, is decided upon. The method of prediction is by the application of models that attempt to describe the environmental processes in mathematical terms in order to produce a quantitative result which can be used in the decision-making process

Revue of some dosimetry and dose assessment European projects

International Nuclear Information System (INIS)

Bolognese-Milsztajn, T.; Frank, D.; Lacoste, V.; Pihet, P.

2006-01-01

Full text of publication follows: Within the 5. Framework Programme of the European Commission several project dealing with dosimetry and dose assessment for internal and external exposure have been supported. A revue of the results of some of them is presented in this paper. The EURADOS network which involved 50 dosimetry institutes in EUROPE has coordinated the project DOSIMETRY NETWORK: the main results achieved within this action are the following: - The release on the World Wide Web of the EURADOS Database of Dosimetry Research Facilities; - The realisation of the report 'Harmonization of Individual Monitoring (IM) in Europe'; - The continuation of the intercomparisons programme of environmental radiation monitoring systems; - The realisation of the report Cosmic radiation exposure of aircraft crew. The EVIDOS project aimed at evaluating state of the art dosimetry techniques in representative workplaces of the nuclear industry with complex mixed neutron-photon radiation fields. This paper summarises the main findings from a practical point of view. Conclusions and recommendations will be given concerning characterisation of radiation fields, methods to derive radiation protection quantities and dosimeters results. The IDEA project aimed to improve the assessment of incorporated radionuclides through developments of advanced in-vivo and bioassay monitoring techniques and making use of such enhancements for improvements in routine monitoring. The primary goal was to categorize those new developments regarding their potential and eligibility for the routine monitoring community. The costs of monitoring for internal exposures in the workplace are usually significantly greater than the equivalent costs for external exposures. There is therefore a need to ensure that resources are employed with maximum effectiveness. The EC-funded OMINEX (Optimisation of Monitoring for Internal Exposure) project has developed methods for optimising the design and implementation of

Proceedings of the international symposium on environmental monitoring and dose estimation of residents after accident of TEPCO's Fukushima Daiichi Nuclear Power Stations

International Nuclear Information System (INIS)

Takahashi, Sentaro; Yamana, Hajimu; Takahashi, Tomoyuki; Takamiya, Koichi; Fukutani, Satoshi; Sato, Nobuhiro; Nakatani, Maki

2013-02-01

In March 2011, a massive earthquake and the resulting tsunami struck the Tohoku area in Japan, causing serious damages to TEPCO's Fukushima Daiichi nuclear plant and the release of a significant quantity of radionuclides into the surrounding environment. This accident underlined the necessity of establishing new and comprehensive scientific research for promoting safety in nuclear technology. With this aim, the Kyoto University Research Reactor Institute (KURRI) developed a new research program called the “KUR Research Program for Scientific Basis of Nuclear Safety” from this year. In this program, we are planning to hold an annual series of international symposiums along with many other research activities. The first in this series of symposiums, entitled “The International Symposium on Environmental Monitoring and Dose Estimation of Residents after Accident of TEPCO's Fukushima Daiichi Nuclear Power Station,” deals with the radiological effect of the March 2011 accident in Fukushima Daiichi NPP on the public. The purpose of this symposium is to collate data on environmental radioactivity anadiation dose in residents, discuss and verify these data, and clarify the actual situation of environmental contamination anesultant radiation exposed to the residents. We believe that an accurate estimation of the radiation dose is quite essential for planning for the healthy life and mental contentment of the residents, and we hope that many researchers who are studying the radiological effects of the accident will join us for these purposes. The environmental monitoring data are important for the dose assessment for residents. However, the monitoring data in the early stage are not sufficient for dose assessment, particularly near the NPP site, because of the confusion and blackout caused by the earthquake. However, many researchers and organizations in Japan and other countries have independently carried out radiation monitoring. We believe that the publication and

Public participation in Malawi's environmental impact assessment ...

African Journals Online (AJOL)

Since the adoption of the Environmental Management Act of 1996, Malawi has been using environmental impact assessment (EIA) as a tool for predicting and assessing the impact of development projects on the environment. This study assessed the extent of public participation in Malawi's EIA process. Desktop study of ...

Peak Dose Assessment for Proposed DOE-PPPO Authorized Limits

International Nuclear Information System (INIS)

Maldonado, Delis

2012-01-01

The Oak Ridge Institute for Science and Education (ORISE), a U.S. Department of Energy (DOE) prime contractor, was contracted by the DOE Portsmouth/Paducah Project Office (DOE-PPPO) to conduct a peak dose assessment in support of the Authorized Limits Request for Solid Waste Disposal at Landfill C-746-U at the Paducah Gaseous Diffusion Plant (DOE-PPPO 2011a). The peak doses were calculated based on the DOE-PPPO Proposed Single Radionuclides Soil Guidelines and the DOE-PPPO Proposed Authorized Limits (AL) Volumetric Concentrations available in DOE-PPPO 2011a. This work is provided as an appendix to the Dose Modeling Evaluations and Technical Support Document for the Authorized Limits Request for the C-746-U Landfill at the Paducah Gaseous Diffusion Plant, Paducah, Kentucky (ORISE 2012). The receptors evaluated in ORISE 2012 were selected by the DOE-PPPO for the additional peak dose evaluations. These receptors included a Landfill Worker, Trespasser, Resident Farmer (onsite), Resident Gardener, Recreational User, Outdoor Worker and an Offsite Resident Farmer. The RESRAD (Version 6.5) and RESRAD-OFFSITE (Version 2.5) computer codes were used for the peak dose assessments. Deterministic peak dose assessments were performed for all the receptors and a probabilistic dose assessment was performed only for the Offsite Resident Farmer at the request of the DOE-PPPO. In a deterministic analysis, a single input value results in a single output value. In other words, a deterministic analysis uses single parameter values for every variable in the code. By contrast, a probabilistic approach assigns parameter ranges to certain variables, and the code randomly selects the values for each variable from the parameter range each time it calculates the dose (NRC 2006). The receptor scenarios, computer codes and parameter input files were previously used in ORISE 2012. A few modifications were made to the parameter input files as appropriate for this effort. Some of these changes

Environmental assessment model for shallow land disposal of low-level radioactive wastes: interim report

International Nuclear Information System (INIS)

Little, C.A.; Fields, D.E.; Emerson, C.J.; Hiromoto, G.

1981-09-01

PRESTO (Prediction of Radiation Effects from Shallow Trench Operations) is a computer code developed under US Environmental Protection Agency (EPA) funding to evaluate possible health effects from shallow land burial trenches. The model is intended to be generic and to assess radionuclide transport, ensuing exposure, and health impact to a static local population for a 1000-y period following the end of burial operations. Human exposure scenarios considered by the model include normal releases (including leaching and operational spillage), human intrusion, and site farming or reclamation. Pathways and processes of transit from the trench to an individual or population include: groundwater transport, overland flow, erosion, surface water dilution, resuspension, atmospheric transport, deposition, inhalation, and ingestion of contaminated beef, milk, crops, and water. Both population doses and individual doses are calculated as well as doses to the intruder and farmer

Combination TLD/TED dose assessment

International Nuclear Information System (INIS)

Parkhurst, M.A.

1992-11-01

During the early 1980s, an appraisal of dosimetry programs at US Department of Energy (DOE) facilities identified a significant weakness in dose assessment in fast neutron environments. Basing neutron dose equivalent on thermoluminescence dosimeters (TLDS) was not entirely satisfactory for environments that had not been well characterized. In most operational situations, the dosimeters overrespond to neutrons, and this overresponse could be further exaggerated with changes in the neutron quality factor (Q). Because TLDs are energy dependent with an excellent response to thermal and low-energy neutrons but a weak response to fast neutrons, calibrating the dosimetry system to account for mixed and moderated neutron energy fields is a difficult and seldom satisfactory exercise. To increase the detection of fast neutrons and help improve the accuracy of dose equivalent determinations, a combination dosimeter was developed using TLDs to detect thermal and low-energy neutrons and a track-etch detector (TED) to detect fast neutrons. By combining the albedo energy response function of the TLDs with the track detector elements, the dosimeter can nearly match the fluence-to-dose equivalent conversion curve. The polymer CR-39 has neutron detection characteristics superior to other materials tested. The CR-39 track detector is beta and gamma insensitive and does not require backscatter (albedo) from the body to detect the exposure. As part of DOE's Personnel Neutron and Upgrade Program, we have been developing a R-39 track detector over the past decade to address detection and measurement of fast neutrons. Using CR-39 TEDs in combination with TLDs will now allow us to detect the wide spectrum of occupational neutron energies and assign dose equivalents much more confidently

The role of uncertainty analysis in dose reconstruction and risk assessment

International Nuclear Information System (INIS)

Hoffman, F.O.; Simon, S.L.; Thiessen. K.M.

1996-01-01

Dose reconstruction and risk assessment rely heavily on the use of mathematical models to extrapolate information beyond the realm of direct observation. Because models are merely approximations of real systems, their predictions are inherently uncertain. As a result, full disclosure of uncertainty in dose and risk estimates is essential to achieve scientific credibility and to build public trust. The need for formal analysis of uncertainty in model predictions was presented during the nineteenth annual meeting of the NCRP. At that time, quantitative uncertainty analysis was considered a relatively new and difficult subject practiced by only a few investigators. Today, uncertainty analysis has become synonymous with the assessment process itself. When an uncertainty analysis is used iteratively within the assessment process, it can guide experimental research to refine dose and risk estimates, deferring potentially high cost or high consequence decisions until uncertainty is either acceptable or irreducible. Uncertainty analysis is now mandated for all ongoing dose reconstruction projects within the United States, a fact that distinguishes dose reconstruction from other types of exposure and risk assessments. 64 refs., 6 figs., 1 tab

Environmental radioactivity and dose evaluation in Taiwan after the Chernobyl accident

International Nuclear Information System (INIS)

Chung, C.E.

1989-01-01

A substantial increase in fission product activity was observed in various environmental samples taken in Taiwan after the Chernobyl accident. The concentration of long-lived fission products in air above ground, precipitation, grass, vegetation and milk were monitored in the next 7 wk. The individual effective dose equivalent committed by the first year of exposure and intake following the accident were evaluated. Average individual doses for the population in Taiwan are estimated at 0.9 microSv due to global fallout from the Chernobyl accident. This value is lower than that reported in neighboring countries in the Far East and poses no increased health impact to the public in Taiwan

Draft environmental assessment of Argonne National Laboratory, East

Energy Technology Data Exchange (ETDEWEB)

1975-10-01

This environmental assessment of the operation of the Argonne National Laboratory is related to continuation of research and development work being conducted at the Laboratory site at Argonne, Illinois. The Laboratory has been monitoring various environmental parameters both offsite and onsite since 1949. Meteorological data have been collected to support development of models for atmospheric dispersion of radioactive and other pollutants. Gaseous and liquid effluents, both radioactive and non-radioactive, have been measured by portable monitors and by continuous monitors at fixed sites. Monitoring of constituents of the terrestrial ecosystem provides a basis for identifying changes should they occur in this regime. The Laboratory has established a position of leadership in monitoring methodologies and their application. Offsite impacts of nonradiological accidents are primarily those associated with the release of chlorine and with sodium fires. Both result in releases that cause no health damage offsite. Radioactive materials released to the environment result in a cumulative dose to persons residing within 50 miles of the site of about 47 man-rem per year, compared to an annual total of about 950,000 man-rem delivered to the same population from natural background radiation. 100 refs., 17 figs., 33 tabs.

31 CFR 26.3 - Availability of Environmental Impact Assessment Summaries (EIA Summaries) and Environmental...

Science.gov (United States)

2010-07-01

... 31 Money and Finance: Treasury 1 2010-07-01 2010-07-01 false Availability of Environmental Impact Assessment Summaries (EIA Summaries) and Environmental Impact Assessments (EIAs). 26.3 Section 26.3 Money and... DEVELOPMENT BANDS (MDBs) § 26.3 Availability of Environmental Impact Assessment Summaries (EIA Summaries) and...

Estimate on external effective doses received by the Iranian population from environmental gamma radiation sources

Energy Technology Data Exchange (ETDEWEB)

Roozitalab, J.; Reza deevband, M.; Rastkhah, N. [National Radiation Protection Dept. Atomic Energy Organization (Iran, Islamic Republic of); Sohrabi, M. [Intenatinal atomic Energy Agency, Vienna (Austria)

2006-07-01

Concentration of natural radioactive materials, especially available U 238, Ra 226, Th 232, and K 40 in construction materials and soil, as well as absorb dose from cosmic rays, is the most important source of the people for effective doses from the environment radiation. In order to evaluate external effective dose, it has been carried out more than 1000 measurements in 36 cities by sensitive dosimeters to environmental gamma radiation for indoor and outdoor conditions in residential areas; which its results show that range of gamma exposure for inside of buildings in Iran is 8.7-20.5 {mu}R/h, and outdoor environments of different cities is 7.9-20.6 {mu}R/h, which their mean value are 14.33 and 12.62 {mu}R/h respectively. Meanwhile, it has been estimated that beam-absorbing ratio between indoor and outdoor in measured environments is 1.55, except contribution of cosmic rays. This studies show that average effective dose for each Iranian person from environmental gamma is 96.9 n Sv/h, and annually effective dose for every person is 0.848 mSv. (authors)

Estimate on external effective doses received by the Iranian population from environmental gamma radiation sources

International Nuclear Information System (INIS)

Roozitalab, J.; Reza deevband, M.; Rastkhah, N.; Sohrabi, M.

2006-01-01

Concentration of natural radioactive materials, especially available U 238, Ra 226, Th 232, and K 40 in construction materials and soil, as well as absorb dose from cosmic rays, is the most important source of the people for effective doses from the environment radiation. In order to evaluate external effective dose, it has been carried out more than 1000 measurements in 36 cities by sensitive dosimeters to environmental gamma radiation for indoor and outdoor conditions in residential areas; which its results show that range of gamma exposure for inside of buildings in Iran is 8.7-20.5 μR/h, and outdoor environments of different cities is 7.9-20.6 μR/h, which their mean value are 14.33 and 12.62 μR/h respectively. Meanwhile, it has been estimated that beam-absorbing ratio between indoor and outdoor in measured environments is 1.55, except contribution of cosmic rays. This studies show that average effective dose for each Iranian person from environmental gamma is 96.9 n Sv/h, and annually effective dose for every person is 0.848 mSv. (authors)

Characteristics Of Dosimeter TL CaSO4:Dy Glass Capillaries For Environmental Radiation Dose Monitoring

International Nuclear Information System (INIS)

Sofyan Hasnel; Yulianti, Helfi; Ramain, Abubakar; Kusumawati, Dyah D.; Suyati

2000-01-01

research on the characteristic of dosimeter TL CaSO 4 : Dy glass capillaries for environmental dose radiation have been carried out. The results obtained are uniform response and reproducibility during three cycles consumption with average percentage standard deviation of 7.31 % and 5.45%. The response dose is linear and has a minimum detectable dose of 0.01 mGy, sunshine effect with non-penetrating light capsule of 4.65%, humidity effects is not significant by using non-penetrating light capsule. Radiation dose information during 30 days are fading 25%

Study, assessment of radioactive dose on China's population

Energy Technology Data Exchange (ETDEWEB)

Ziqiang, P.

1984-05-10

The national population dose is defined as the radioactive dose from both natural and artificial sources which is received by the entire Chinese population. The necessity and prospects for developing ways to assess China's national population dose and some noteworthy problems in this area are described.

Environmental Impact Assessment in Antarctica

NARCIS (Netherlands)

Bastmeijer, C.J.; Roura, R.; Bastmeijer, K.; Koivurova, T.

2008-01-01

This publication focuses on the instrument of Environmental Impact Assessment (EIA) that has been developed within the Antarctic Treaty System (ATS) as one of the tools to promote environmental protection. The states involved in the ATS already recognized the importance of this instrument in 1975

FY 1991 Task plans for the Hanford Environmental Dose Reconstruction Project

International Nuclear Information System (INIS)

1991-04-01

The purpose of the Hanford Environmental Dose Reconstruction (HEDR) Project is to estimate radiation doses from Hanford Site operations since 1944 to populations and individuals. The objectives of work in Fiscal Year (FY) 1991 are to analyze data and models used in Phase 1 and restructure the models to increase accuracy and reduce uncertainty in dose estimation capability. Databases will be expanded and efforts will begin to determine the appropriate scope (space, time, radionuclides, pathways and individuals/population groups) and accuracy (level of uncertainty in dose estimates) for the project. Project scope and accuracy requirements, once defined, can be translated into additional model and data requirements later in the project. Task plans for FY 1991 have been prepared based on activities approved by the Technical Steering Panel (TSP) in October 1990 and mid-year revisions discussed at the TSP planning/budget workshop in February 1991. The activities can be divided into two broad categories: (1) model and data development and evaluation, (2) project, technical and communication support. 3 figs., 1 tab

Objective function for the environmental assessment of waste

International Nuclear Information System (INIS)

Toy, A.J.; Boegel, J.; Cohen, J.J.

1976-01-01

Various waste management systems were examined in order to determine what the environmental impacts might be and to rank the relative importance of those impacts. This examination determined that radiation dose to man was the most significant, and probably overriding, impact. This report describes methods of providing an objective function for dose to man. The search for an objective function began with a reading of Federal Regulations and the output of various standard setting councils and committees. Ample guidance was found on maximum allowable doses to individuals but no guidance on dose to large populations or criteria by which systems could be compared or optimized. Several other ways were postulated by which waste management systems could be evaluated besides maximum allowable dose to individuals. 0.1 man-rem per MW(e)-year was selected as the measure of system performance. This unit compares a rational estimate of population dose commitment with the concurrent benefit

Setting boundaries of participation in environmental impact assessment

Energy Technology Data Exchange (ETDEWEB)

Salomons, Geoffrey H., E-mail: gsalomon@ualberta.ca [University of Alberta, Department of Political Science, 10-16 Henry Marshall Tory Building, University of Alberta, Edmonton, AB T6G 2H4 (Canada); Hoberg, George, E-mail: george.hoberg@ubc.ca [University of British Columbia, Faculty of Forestry, Forest Sciences Centre 2045, 2424 Main Mall, Vancouver, British Columbia V6T 1Z4 (Canada)

2014-02-15

Public participation processes are touted as an effective way to increase the capacity and legitimacy of environmental assessment and the regulatory process that rely on them. Recent changes to the Canadian environmental assessment process narrowed the criteria for who can participate in environmental assessments from any who were interested to those who were most directly affected. This article examines the potential consequences of this change by exploring other areas of Canadian regulatory law where a similar directed affected test has been applied. This new standard risks institutionalizing the long-understood representational bias confronted by more diffuse interest like environmental protection. Restricting participation to the “directly affected” is far too narrow a test for processes like environmental assessment that are designed to determine the public interest. -- Highlights: • Public participation can improve the legitimacy of environmental assessments. • New Canadian rules narrow the range of eligible participants. • Similar rules in Alberta have excluded environmental representation. • The new rules may institutionalize bias against more diffuse interests. • Restricting participation to the “directly affected” is far too narrow.

Setting boundaries of participation in environmental impact assessment

International Nuclear Information System (INIS)

Salomons, Geoffrey H.; Hoberg, George

2014-01-01

Public participation processes are touted as an effective way to increase the capacity and legitimacy of environmental assessment and the regulatory process that rely on them. Recent changes to the Canadian environmental assessment process narrowed the criteria for who can participate in environmental assessments from any who were interested to those who were most directly affected. This article examines the potential consequences of this change by exploring other areas of Canadian regulatory law where a similar directed affected test has been applied. This new standard risks institutionalizing the long-understood representational bias confronted by more diffuse interest like environmental protection. Restricting participation to the “directly affected” is far too narrow a test for processes like environmental assessment that are designed to determine the public interest. -- Highlights: • Public participation can improve the legitimacy of environmental assessments. • New Canadian rules narrow the range of eligible participants. • Similar rules in Alberta have excluded environmental representation. • The new rules may institutionalize bias against more diffuse interests. • Restricting participation to the “directly affected” is far too narrow

Institutional Assessment of Environmentally Oriented Subsoil Use

Directory of Open Access Journals (Sweden)

Irina Gennadyevna Polyanskaya

2017-06-01

Full Text Available The article solves two relevant problems related to the implementation of the institutional assessment of environmentally oriented subsoil use: 1 the definition of the ‘environmental security’ and 2 the determination of the development level of institutional bases of environmentally oriented subsoil use including the institutional capacity of subsoil use and institutional capacity of environmental security. The article shows an analysis of the existing definitions of “environmental security” and offers the own one. Despite the significant national and foreign experience in the institutional capacity assessment of various processes, there are still some difficulties in defining and measuring the institutional capacity. We eliminate these difficulties by employing 1 original factors, previously identified, and the content of the “institutional capacity” term; 2 quality characteristics for the institutional capacity assessment of the process regulated at the macroeconomic level, and 3 a consistent methodological tool for the institutional assessment of environmentally oriented subsoil use. The study is based on the hypothesis of the necessity of legal and discreet state intervention in the process of subsoil use. Therefore, we identify the evaluation indicator of state regulation in the environmentally oriented subsoil use as the institutional capacity level calculated by using the fuzzy-set theory. As a result, the institutional capacity levels of the environmentally oriented subsoil use have been defined for both the transport corridor «Arctic-Central Asia» and for the countries composing it. The obtained values of the assessment of institutional capacity levels of the environmentally oriented subsoil use can serve as a basis for identifying the vector of its increase

A comparison of radiological risk assessment methods for environmental restoration

International Nuclear Information System (INIS)

Dunning, D.E. Jr.; Peterson, J.M.

1993-01-01

Evaluation of risks to human health from exposure to ionizing radiation at radioactively contaminated sites is an integral part of the decision-making process for determining the need for remediation and selecting remedial actions that may be required. At sites regulated under the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), a target risk range of 10 -4 to 10 -6 incremental cancer incidence over a lifetime is specified by the US Environmental Protection Agency (EPA) as generally acceptable, based on the reasonable maximum exposure to any individual under current and future land use scenarios. Two primary methods currently being used in conducting radiological risk assessments at CERCLA sites are compared in this analysis. Under the first method, the radiation dose equivalent (i.e., Sv or rem) to the receptors of interest over the appropriate period of exposure is estimated and multiplied by a risk factor (cancer risk/Sv). Alternatively, incremental cancer risk can be estimated by combining the EPA's cancer slope factors (previously termed potency factors) for radionuclides with estimates of radionuclide intake by ingestion and inhalation, as well as radionuclide concentrations in soil that contribute to external dose. The comparison of the two methods has demonstrated that resulting estimates of lifetime incremental cancer risk under these different methods may differ significantly, even when all other exposure assumptions are held constant, with the magnitude of the discrepancy depending upon the dominant radionuclides and exposure pathways for the site. The basis for these discrepancies, the advantages and disadvantages of each method, and the significance of the discrepant results for environmental restoration decisions are presented

The food chain and dose submodel, CALDOS, for the assessment of Canada`s nuclear fuel waste management concept

Energy Technology Data Exchange (ETDEWEB)

Zach, R; Sheppard, S C

1992-12-01

The food chain and dose submodel, CALDOS, for assessing Canada`s nuclear fuel management (NFWM) concept of disposal in a vault deep in the Canadian Shield is presented. Together with the surface water, soil and atmosphere submodels, CALDOS is integrated into a comprehensive, probabilistic biosphere model for post-closure assessment. This model is representative of the Canadian Shield in Ontario and CALDOS is fully generic. CALDOS calculates radionuclide transfer through the environment to make dose predictions for man. It considers 68 radionuclides explicitly and takes into account another 28 short-lived daughters in the dose calculations. Nine potentially toxic elements are also considered. CALDOS is of the multiplicative chain type for most of the radionuclides, but some, such as {sup 3H}, {sup 129I} and {sup 222R}n, are treated specially. The model accounts for all the major internal exposure pathways, including root uptake, leaf deposition, terrestrial animal`s drinking water, terrestrial animal soil ingestion, freshwater fish ingestion, human drinking water, human soil ingestion and human inhalation. External exposure from air immersion, water immersion, ground and building materials are also considered. Dose predictions are based on the recommendations of the International Commission on Radiation Protection (ICRP 26) methodologies, ICRP reference man (ICRP 23) and the critical group concept. CALDOS considers ingrowth of some radioactive daughters, radionuclide availability in soil, recycling and depletion. The model has numerous parameters, some element, radionuclide or food type specific. Sensitivity analysis is used to assess parameter importance in dose prediction. Quality assurance is addressed through general literature, model and parameter evaluations, specifically designed for environmental assessment models. This also involves validation and code comparison studies. (author). 43 refs., 36 tabs., 24 figs.

Lifetime Effective Dose Assessment Based on Background Outdoor Gamma Exposure in Chihuahua City, Mexico

Directory of Open Access Journals (Sweden)

Sergio Luevano-Gurrola

2015-09-01

Full Text Available Determining ionizing radiation in a geographic area serves to assess its effects on a population’s health. The aim of this study was to evaluate the spatial distribution of the background environmental outdoor gamma dose rates in Chihuahua City. This study also estimated the annual effective dose and the lifetime cancer risks of the population of this city. To determine the outdoor gamma dose rate in air, the annual effective dose and the lifetime cancer risk, 48 sampling points were randomly selected in Chihuahua City. Outdoor gamma dose rate measurements were carried out by using a Geiger-Müller counter. Outdoor gamma dose rates ranged from 113 to 310 nGy·h−1. At the same sites, 48 soil samples were taken to obtain the activity concentrations of 226Ra, 232Th and 40K and to calculate their terrestrial gamma dose rates. Radioisotope activity concentrations were determined by gamma spectrometry. Calculated gamma dose rates ranged from 56 to 193 nGy·h−1. Results indicated that the lifetime effective dose of the inhabitants of Chihuahua City is on average 19.8 mSv, resulting in a lifetime cancer risk of 0.001. In addition, the mean of the activity concentrations in soil were 52, 73 and 1097 Bq·kg−1, for 226Ra, 232Th and 40K, respectively. From the analysis, the spatial distribution of 232Th, 226Ra and 40K is to the north, to the north-center and to the south of city, respectively. In conclusion, the natural background gamma dose received by the inhabitants of Chihuahua City is high and mainly due to the geological characteristics of the zone. From the radiological point of view, this kind of study allows us to identify the importance of manmade environments, which are often highly variable and difficult to characterize.

Lifetime Effective Dose Assessment Based on Background Outdoor Gamma Exposure in Chihuahua City, Mexico.

Science.gov (United States)

Luevano-Gurrola, Sergio; Perez-Tapia, Angelica; Pinedo-Alvarez, Carmelo; Carrillo-Flores, Jorge; Montero-Cabrera, Maria Elena; Renteria-Villalobos, Marusia

2015-09-30

Determining ionizing radiation in a geographic area serves to assess its effects on a population's health. The aim of this study was to evaluate the spatial distribution of the background environmental outdoor gamma dose rates in Chihuahua City. This study also estimated the annual effective dose and the lifetime cancer risks of the population of this city. To determine the outdoor gamma dose rate in air, the annual effective dose and the lifetime cancer risk, 48 sampling points were randomly selected in Chihuahua City. Outdoor gamma dose rate measurements were carried out by using a Geiger-Müller counter. Outdoor gamma dose rates ranged from 113 to 310 nGy·h(-1). At the same sites, 48 soil samples were taken to obtain the activity concentrations of (226)Ra, (232)Th and (40)K and to calculate their terrestrial gamma dose rates. Radioisotope activity concentrations were determined by gamma spectrometry. Calculated gamma dose rates ranged from 56 to 193 nGy·h(-1). Results indicated that the lifetime effective dose of the inhabitants of Chihuahua City is on average 19.8 mSv, resulting in a lifetime cancer risk of 0.001. In addition, the mean of the activity concentrations in soil were 52, 73 and 1097 Bq·kg(-1), for (226)Ra, (232)Th and (40)K, respectively. From the analysis, the spatial distribution of (232)Th, (226)Ra and (40)K is to the north, to the north-center and to the south of city, respectively. In conclusion, the natural background gamma dose received by the inhabitants of Chihuahua City is high and mainly due to the geological characteristics of the zone. From the radiological point of view, this kind of study allows us to identify the importance of manmade environments, which are often highly variable and difficult to characterize.

Lifetime Effective Dose Assessment Based on Background Outdoor Gamma Exposure in Chihuahua City, Mexico

Science.gov (United States)

Luevano-Gurrola, Sergio; Perez-Tapia, Angelica; Pinedo-Alvarez, Carmelo; Carrillo-Flores, Jorge; Montero-Cabrera, Maria Elena; Renteria-Villalobos, Marusia

2015-01-01

Determining ionizing radiation in a geographic area serves to assess its effects on a population’s health. The aim of this study was to evaluate the spatial distribution of the background environmental outdoor gamma dose rates in Chihuahua City. This study also estimated the annual effective dose and the lifetime cancer risks of the population of this city. To determine the outdoor gamma dose rate in air, the annual effective dose and the lifetime cancer risk, 48 sampling points were randomly selected in Chihuahua City. Outdoor gamma dose rate measurements were carried out by using a Geiger-Müller counter. Outdoor gamma dose rates ranged from 113 to 310 nGy·h−1. At the same sites, 48 soil samples were taken to obtain the activity concentrations of 226Ra, 232Th and 40K and to calculate their terrestrial gamma dose rates. Radioisotope activity concentrations were determined by gamma spectrometry. Calculated gamma dose rates ranged from 56 to 193 nGy·h−1. Results indicated that the lifetime effective dose of the inhabitants of Chihuahua City is on average 19.8 mSv, resulting in a lifetime cancer risk of 0.001. In addition, the mean of the activity concentrations in soil were 52, 73 and 1097 Bq·kg−1, for 226Ra, 232Th and 40K, respectively. From the analysis, the spatial distribution of 232Th, 226Ra and 40K is to the north, to the north-center and to the south of city, respectively. In conclusion, the natural background gamma dose received by the inhabitants of Chihuahua City is high and mainly due to the geological characteristics of the zone. From the radiological point of view, this kind of study allows us to identify the importance of manmade environments, which are often highly variable and difficult to characterize. PMID:26437425

Three years of seasonal dose assessment from outdoors gamma exposure in Sao Paulo city, Brazil

International Nuclear Information System (INIS)

Carneiro, Janete C.G.G.; Sanches, Matias P.; Betti, Flavio; Pecequilo, Brigitte R.S.

2011-01-01

Measurements of external (outdoors) gamma exposure from natural background radiation have been used to estimate the average annual doses in Sao Paulo city. Twelve monitoring stations were placed in different regions of the town including both urban (where building materials are present) and outskirts areas. Seasonally surveys observing the four seasons from 2008 to 2010 have been carried out. The data were drawn from a 3-month sampling using the thermoluminescent dosimetry. The effective doses values are quite similar (slightly higher during the winter), so it can be considered that these results are not under significant influence (or variability) of seasonal environmental conditions like temperature, wind or rain. Dose values over the three years period, from Vila Carrao district, exclusively an urban location with mostly no green areas, present the highest values, while the lower values were always obtained for Tucuruvi district, near the biggest urban forest, Parque Estadual da Cantareira. Over the assessed period, the mean of the average annual effective doses was 1.3 ± 0.1 mSv.y -1 . For the same period, the average annual background from nuclear and radioactive facility at IPEN was 0.75 ± 0.12 mSv.y -1 . (author)

Three years of seasonal dose assessment from outdoors gamma exposure in Sao Paulo city, Brazil

Energy Technology Data Exchange (ETDEWEB)

Carneiro, Janete C.G.G.; Sanches, Matias P.; Betti, Flavio; Pecequilo, Brigitte R.S., E-mail: janetegc@ipen.b [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

2011-07-01

Measurements of external (outdoors) gamma exposure from natural background radiation have been used to estimate the average annual doses in Sao Paulo city. Twelve monitoring stations were placed in different regions of the town including both urban (where building materials are present) and outskirts areas. Seasonally surveys observing the four seasons from 2008 to 2010 have been carried out. The data were drawn from a 3-month sampling using the thermoluminescent dosimetry. The effective doses values are quite similar (slightly higher during the winter), so it can be considered that these results are not under significant influence (or variability) of seasonal environmental conditions like temperature, wind or rain. Dose values over the three years period, from Vila Carrao district, exclusively an urban location with mostly no green areas, present the highest values, while the lower values were always obtained for Tucuruvi district, near the biggest urban forest, Parque Estadual da Cantareira. Over the assessed period, the mean of the average annual effective doses was 1.3 {+-} 0.1 mSv.y{sup -1}. For the same period, the average annual background from nuclear and radioactive facility at IPEN was 0.75 {+-} 0.12 mSv.y{sup -1}. (author)

Automated size-specific CT dose monitoring program: Assessing variability in CT dose

International Nuclear Information System (INIS)

Christianson, Olav; Li Xiang; Frush, Donald; Samei, Ehsan

2012-01-01

Purpose: The potential health risks associated with low levels of ionizing radiation have created a movement in the radiology community to optimize computed tomography (CT) imaging protocols to use the lowest radiation dose possible without compromising the diagnostic usefulness of the images. Despite efforts to use appropriate and consistent radiation doses, studies suggest that a great deal of variability in radiation dose exists both within and between institutions for CT imaging. In this context, the authors have developed an automated size-specific radiation dose monitoring program for CT and used this program to assess variability in size-adjusted effective dose from CT imaging. Methods: The authors radiation dose monitoring program operates on an independent health insurance portability and accountability act compliant dosimetry server. Digital imaging and communication in medicine routing software is used to isolate dose report screen captures and scout images for all incoming CT studies. Effective dose conversion factors (k-factors) are determined based on the protocol and optical character recognition is used to extract the CT dose index and dose-length product. The patient's thickness is obtained by applying an adaptive thresholding algorithm to the scout images and is used to calculate the size-adjusted effective dose (ED adj ). The radiation dose monitoring program was used to collect data on 6351 CT studies from three scanner models (GE Lightspeed Pro 16, GE Lightspeed VCT, and GE Definition CT750 HD) and two institutions over a one-month period and to analyze the variability in ED adj between scanner models and across institutions. Results: No significant difference was found between computer measurements of patient thickness and observer measurements (p= 0.17), and the average difference between the two methods was less than 4%. Applying the size correction resulted in ED adj that differed by up to 44% from effective dose estimates that were not

A Study on improvement of environmental assessment system in social, economic, and environmental sectors

Energy Technology Data Exchange (ETDEWEB)

Nam, Young Sook; Koo, Doh Wan; Keum, Kee Yong [Korea Environment Institute, Seoul (Korea)

1998-12-01

The environmental assessment system is assessed as a mechanism that can achieve the goal for environmental policy in 21st century. As it can evaluate social and economic feasibility of large-scale development program, this system can achieve a sustainable society by mitigating social conflicts arising from environmental problems. For making the environmental assessment system substantial, this study was implemented by the need of improvement of the system, by analyzing problems of social, economic, and environmental evaluation, which is implemented under the present system. 44 refs., 1 fig., 25 tabs.

Preliminary environmental site assessments in New York City

International Nuclear Information System (INIS)

Lundy, P.; Gasson, D.R.; Longendyke, S.T.

1991-01-01

Preliminary Environmental Site Assessments are often performed prior to real estate transactions or refinancing. These assessments are typically performed for real estate buyers, sellers and lending institutions. Undertaking a Preliminary Environmental Site Assessment in New York City can often be quite complex and time-consuming. This is due, in part, to the age and density of buildings in the city as well as the myriad of regulatory agencies with jurisdiction over environmental issues. This paper will discuss how environmental assessments are performed with a special emphasis on building in New York City. In includes hazardous wastes management for Radon, PCB's and asbestos

An airborne dispersion/dose assessment computer program. Phase 1

International Nuclear Information System (INIS)

Scott, C.K.; Kennedy, E.R.; Hughs, R.

1991-05-01

The Atomic Energy Control Board (AECB) staff have a need for an airborne dispersion-dose assessment computer programme for a microcomputer. The programme must be capable of analyzing the dispersion of both radioactive and non-radioactive materials. A further requirement of the programme is that it be implemented on the AECB complex of microcomputers and that it have an advanced graphical user interface. A survey of computer programs was conducted to determine which, if any, could meet the AECB's requirements in whole or in part. Ten programmes were selected for detailed review including programs for nuclear and non-radiological emergencies. None of the available programmes for radiation dose assessment meets all the requirements for reasons of user interaction, method of source term estimation or site specificity. It is concluded that the best option for meeting the AECB requirements is to adopt the CAMEO programme (specifically the ALOHA portion) which has a superior graphical user interface and add the necessary models for radiation dose assessment

Organ doses for foetuses, babies, children and adults from environmental gamma rays

International Nuclear Information System (INIS)

Petoussi, N.; Jacob, P.; Zankl, M.; Saito, K.

1991-01-01

Organ doses for babies, children and adults and doses to foetuses from environmental gamma rays were calculated using Monte Carlo codes. Firstly, gamma ray fields in the air-over-ground geometry were simulated, neglecting the disturbances of the radiation field by the human body. The exposure modes considered were semi-infinite homogeneous volume sources in the air, infinite plane sources at a depth of 0.5 g.cm -2 in the ground and homogeneous volume sources of natural radionuclides in the ground. The results of the simulation of the gamma ray transport in the air-over-ground geometry were used as sources irradiating the anthropomorphic phantoms: an 8 week old baby, a seven year old child and two 'reference' adult phantoms of a male and a female. The dose to foetuses were estimated from the dose to the uterus of the adult female. Dose conversion factors normalised to source intensity and air kerma were calculated for monoenergetic sources (15 keV to 10 MeV) and natural and artificial radionuclides. (author)

Environmental Impact Assessment and Space Activities

Science.gov (United States)

Viikari, L.

Environmental Impact Assessment (EIA) is a common tool for environment a l protection and management on Earth today, as prior assessment of the environmental consequences of planned activities. It is meant to provide the decision-makers with as comprehensive as possible information about the different environmental effects the proposed activity would entail, including alternative courses of action and the zero-alternative (i.e. the no action alternative). Additionally, plans for mitigation in respect of each alternative are to be outlined. The assessments take account of i.a. environmental impacts on ecosystems, diminution of aesthetic and scientific values, long-term or cumulative effects, as well as transfrontier implications. They also consider issues such as pollution control, environmental protection measures, reporting, post-project analysis, rehabilitation and so on. Also uncertainties in the assessment process are to be expressly presented. Most importantly, a common requirement also is that the results of the impact studies are presented in a way comprehensible to the g neral public,e too. Although the central aspect of the EIA is to provide the decision-makers with scientific information, the process also has other important implications. One of the most relevant of them is the involvement of those people potentially affected in some way by the proposed activity: most EIA systems require in some way the participation of the public, alongside with the relevant governmental authorities and other stake-holders. Such public involvement has various aims and goals: it may serve as a testimony to good governance in general, or be considered in more practical terms as improved planning, due to the concrete contribution of the public to the decision-making process. Obviously, it also is a tool for reducing conflict and developing wider support for the eventual decisions. In short, it enables the public to gain information about planned activities and influence

36 CFR 220.7 - Environmental assessment and decision notice.

Science.gov (United States)

2010-07-01

... 36 Parks, Forests, and Public Property 2 2010-07-01 2010-07-01 false Environmental assessment and decision notice. 220.7 Section 220.7 Parks, Forests, and Public Property FOREST SERVICE, DEPARTMENT OF AGRICULTURE NATIONAL ENVIRONMENTAL POLICY ACT (NEPA) COMPLIANCE § 220.7 Environmental assessment and decision notice. (a) Environmental assessment...

Development on Dose Assessment Model of Northeast Asia Nuclear Accident Simulator

Energy Technology Data Exchange (ETDEWEB)

Kim, Ju Yub; Kim, Ju Youl; Kim, Suk Hoon; Lee, Seung Hee; Yoon, Tae Bin [FNC Techology, Yongin (Korea, Republic of)

2016-05-15

In order to support the emergency response system, the simulator for overseas nuclear accident is under development including source-term estimation, atmospheric dispersion modeling and dose assessment. The simulator is named NANAS (Northeast Asia Nuclear Accident Simulator). For the source-term estimation, design characteristics of each reactor type should be reflected into the model. Since there are a lot of reactor types in neighboring countries, the representative reactors of China, Japan and Taiwan have been selected and the source-term estimation models for each reactor have been developed, respectively. For the atmospheric dispersion modeling, Lagrangian particle model will be integrated into the simulator for the long range dispersion modeling in Northeast Asia region. In this study, the dose assessment model has been developed considering external and internal exposure. The dose assessment model has been developed as a part of the overseas nuclear accidents simulator which is named NANAS. It addresses external and internal pathways including cloudshine, groundshine and inhalation. Also, it uses the output of atmospheric dispersion model (i.e. the average concentrations of radionuclides in air and ground) and various coefficients (e.g. dose conversion factor and breathing rate) as an input. Effective dose and thyroid dose for each grid in the Korean Peninsula region are printed out as a format of map projection and chart. Verification and validation on the dose assessment model will be conducted in further study by benchmarking with the measured data of Fukushima Daiichi Nuclear Accident.

Integrated Environmental Assessment Part III: ExposureAssessment

Energy Technology Data Exchange (ETDEWEB)

McKone, Thomas E.; Small, Mitchell J.

2006-06-01

Human exposure assessment is a key step in estimating the environmental and public health burdens that result chemical emissions in the life cycle of an industrial product or service. This column presents the third in a series of overviews of the state of the art in integrated environmental assessment - earlier columns described emissions estimation (Frey and Small, 2003) and fate and transport modeling (Ramaswami, et al., 2004). When combined, these first two assessment elements provide estimates of ambient concentrations in the environment. Here we discuss how both models and measurements are used to translate ambient concentrations into metrics of human and ecological exposure, the necessary precursors to impact assessment. Exposure assessment is the process of measuring and/or modeling the magnitude, frequency and duration of contact between a potentially harmful agent and a target population, including the size and characteristics of that population (IPCS, 2001; Zartarian, et al., 2005). Ideally the exposure assessment process should characterize the sources, routes, pathways, and uncertainties in the assessment. Route of exposure refers to the way that an agent enters the receptor during an exposure event. Humans contact pollutants through three routes--inhalation, ingestion, and dermal uptake. Inhalation occurs in both outdoor environments and indoor environments where most people spend the majority of their time. Ingestion includes both water and food, as well as soil and dust uptake due to hand-to-mouth activity. Dermal uptake occurs through contacts with consumer products; indoor and outdoor surfaces; the water supply during washing or bathing; ambient surface waters during swimming or boating; soil during activities such as work, gardening, and play; and, to a lesser extent, from the air that surrounds us. An exposure pathway is the course that a pollutant takes from an ambient environmental medium (air, soil, water, biota, etc), to an exposure medium

Environmental assessment of phosphogypsum stacks

International Nuclear Information System (INIS)

Odat, M.; Al-Attar, L.; Raja, G.; Abdul Ghany, B.

2008-03-01

Phosphogypsum is one of the most important by-products of phosphate fertilizer industry. It is kept in large stacks to the west of Homs city. Storing Phosphogypsum as open stacks exposed to various environmental effects, wind and rain, may cause pollution of the surrounding ecosystem (soil, plant, water and air). This study was carried out in order to assess the environmental impact of Phosphogypsum stacks on the surrounding ecosystem. The obtained results show that Phosphogypsum stacks did not increase the concentration of radionuclides, i.e. Radon-222 and Radium-226, the external exposed dose of gamma rays, as well as the concentration of heavy metals in the components of the ecosystem, soil, plant, water and air, as their concentrations did not exceed the permissible limits. However, the concentration of fluorine in the upper layer of soil, located to the east of the Phosphogypsum stacks, increased sufficiently, especially in the dry period of the year. Also, the concentration of fluoride in plants growing up near-by the Phosphogypsum stacks was too high, exceeded the permissible levels. This was reflected in poising plants and animals, feeding on the plants. Consequently, increasing the concentration of fluoride in soil and plants is the main impact of Phosphogypsum stacks on the surrounding ecosystem. Minimising this effect could be achieved by establishing a 50 meter wide protection zone surrounding the Phosphogypsum stacks, which has to be planted with non palatable trees, such as pine and cypress, forming wind barriers. Increasing the concentrations of heavy metals and fluoride in infiltrated water around the stacks was high; hence cautions must be taken to prevent its usage in any application or disposal in adjacent rivers and leaks.(author)

Environmental assessment of phosphogypsum stacks

International Nuclear Information System (INIS)

Odat, M.; Al-Attar, L.; Raja, G.; Abdul Ghany, B.

2009-01-01

Phosphogypsum is one of the most important by-products of phosphate fertilizer industry. It is kept in large stacks to the west of Homs city. Storing Phosphogypsum as open stacks exposed to various environmental effects, wind and rain, may cause pollution of the surrounding ecosystem (soil, plant, water and air). This study was carried out in order to assess the environmental impact of Phosphogypsum stacks on the surrounding ecosystem. The obtained results show that Phosphogypsum stacks did not increase the concentration of radionuclides, i.e. Radon-222 and Radium-226, the external exposed dose of gamma rays, as well as the concentration of heavy metals in the components of the ecosystem, soil, plant, water and air, as their concentrations did not exceed the permissible limits. However, the concentration of fluorine in the upper layer of soil, located to the east of the Phosphogypsum stacks, increased sufficiently, especially in the dry period of the year. Also, the concentration of fluoride in plants growing up near-by the Phosphogypsum stacks was too high, exceeded the permissible levels. This was reflected in poising plants and animals, feeding on the plants. Consequently, increasing the concentration of fluoride in soil and plants is the main impact of Phosphogypsum stacks on the surrounding ecosystem. Minimising this effect could be achieved by establishing a 50 meter wide protection zone surrounding the Phosphogypsum stacks, which has to be planted with non palatable trees, such as pine and cypress, forming wind barriers. Increasing the concentrations of heavy metals and fluoride in infiltrated water around the stacks was high; hence cautions must be taken to prevent its usage in any application or disposal in adjacent rivers and leaks.(author)

Study on the estimation of probabilistic effective dose. Committed effective dose from intake of marine products using Oceanic General Circulation Model

International Nuclear Information System (INIS)

Nakano, Masanao

2007-01-01

The worldwide environmental protection is required by the public. A long-term environmental assessment from nuclear fuel cycle facilities to the aquatic environment also becomes more important to utilize nuclear energy more efficiently. Evaluation of long-term risk including not only in Japan but also in neighboring countries is considered to be necessary in order to develop nuclear power industry. The author successfully simulated the distribution of radionuclides in seawater and seabed sediment produced by atmospheric nuclear tests using LAMER (Long-term Assessment ModEl for Radioactivity in the oceans). A part of the LAMER calculated the advection- diffusion-scavenging processes for radionuclides in the oceans and the Japan Sea in cooperate with Oceanic General Circulation Model (OGCM) and was validated. The author is challenging to calculate probabilistic effective dose suggested by ICRP from intake of marine products due to atmospheric nuclear tests using the Monte Carlo method in the other part of LAMER. Depending on the deviation of each parameter, the 95th percentile of the probabilistic effective dose was calculated about half of the 95th percentile of the deterministic effective dose in proforma calculation. The probabilistic assessment gives realistic value for the dose assessment of a nuclear fuel cycle facility. (author)

76 FR 44891 - Monsanto Co.; Availability of Petition, Plant Pest Risk Assessment, and Environmental Assessment...

Science.gov (United States)

2011-07-27

...] Monsanto Co.; Availability of Petition, Plant Pest Risk Assessment, and Environmental Assessment for... Monsanto petition, our plant pest risk assessment, and our draft environmental assessment for the proposed...-2817 before coming. The petition, draft environmental assessment, and plant pest risk assessment are...

Comparison of the regulatory models assessing off-site radiological dose due to the routine releases of tritium

International Nuclear Information System (INIS)

Hwang, W. T.; Kim, E. H.; Han, M. H.; Choi, Y. H.; Lee, H. S.; Lee, C. W.

2005-01-01

Methodologies of NEWTRIT model, NRC model and AIRDOS-EPA model, which are off-site dose assessment models for regulatory compliance from routine releases of tritium into the environment, were investigated. Using the domestic data, if available, the predictive results of the models were compared. Among them, recently developed NEWTRIT model considers only doses from organically bounded tritium (OBT) due to environmental releases of tritiated water (HTO). A total dose from all exposure pathways predicted from AIRDOS-EPA model was 1.03 and 2.46 times higher than that from NEWTRIT model and NRC model, respectively. From above result, readers should not have an understanding that a predictive dose from NRC model may be underestimated compared with a realistic dose. It is because of that both mathematical models and corresponding parameter values for regulatory compliance are based on the conservative assumptions. For a dose by food consumption predicted from NEWTRIT model, the contribution of OBT was nearly equivalent to that of HTO due to relatively high consumption of grains in Korean. Although a total dose predicted from NEWTRIT model is similar to that from AIRDOS-EPA model, NEWTRIT model may be have a meaning in the understanding of phenomena for the behavior of HTO released into the environment

Year 2006. GRNC's appreciation of the dose estimates presented in the annual environmental monitoring report of Areva-NC La Hague facility. Forth GRNC viewpoint. Detailed report

International Nuclear Information System (INIS)

2007-01-01

The 'Groupe Radioecologie Nord Cotentin' (GRNC) has carried out a very thorough evaluation of the assessment of doses due to discharges from the Cap de la Hague nuclear site carried out by Areva NC, the site operators. The group has looked at all aspects of the assessment methods and data to ensure that they agree with the results presented in the 2006 annual environmental report of the operator. The computer tool, ACADIE, developed to assess the doses, has been used by the GRNC members to carry out their own calculations. This document comprises the detailed report of the GRNC and its synthesis. The detailed report includes: 1 - a critical analysis of the 2006 source term; a note about the uranium content in liquid effluents; the data transmitted by Areva NC (status of atmospheric effluents, status of liquid effluents at sea, fuel data); the data transmitted by the IRSN - the French institute of radiation protection and nuclear safety (status of the radioactive effluents of Areva La Hague facility); the history of liquid and gaseous effluents between 1966 and 2006; 2 - detailed comparison between model and 2006 measurements; critical analysis of 14 C and tritium data available for the Nord Cotentin and the English Channel area; 3 - detail of the 2006 efficient dose calculations; presentation of the environmental dispersion of tritium and of its effects on living organisms. (J.S.)

Environmental dosimetry for normal operations at SRP. Revision 1

International Nuclear Information System (INIS)

Marter, W.L.

1984-01-01

The radiological effect of environmental releases from SRP during normal operations has been assessed annually since 1972 with a dosimetry model developed by SRL in 1971 to 1972, as implemented in the MREM code for atmospheric releases and RIVDOSE code for liquid releases. Starting in 1978, SRL started using environmental models and dose commitment factors developed by Nuclear Regulatory Commission (NRC) for all other environmental dose calculations. The NRC models are more flexible than the older SRL models, use more up-to-date methodologies, cover more exposure pathways, and permit more detailed analysis of effects of normal operations. It is recommended that the NRC models, as implemented in the computer codes X0QD0Q and GASPAR for atmospheric releases and LADTAP for liquid releases, and NRC dose commitment factors be used as the standard method at SRP for assessing offsite dose from normal operations in Health Protection Department annual environmental monitoring reports, and in National Environmental Policy Act documents and Safety Analysis Reports for SRP facilities. 23 references, 3 figures, 9 tables

Theory and Practice of Transboundary Environmental Impact Assessment

NARCIS (Netherlands)

Bastmeijer, C.J.; Koivurova, T.

2008-01-01

Environmental Impact Assessment (EIA) is a well-established instrument of environmental law and policy that aims to ensure that potential adverse environmental effects of human activities are assessed before decisions on such activities are made. The instrument is increasingly being applied in

Establishment of exposure dose assessment laboratory in National Radiation Emergency Medical Center (NREMC)

Energy Technology Data Exchange (ETDEWEB)

Yoo, Jae Ryong; Ha, Wi Ho; Yoon, Seok Won; Han, Eun Ae; Lee, Seung Sook [Korea Institute of Radiological and Medical Sciences, Seoul (Korea, Republic of)

2011-10-15

As unclear industry grown, 432 of the nuclear power plants are operating and 52 of NPPs are under construction currently. Increasing use of radiation or radioisotopes in the field of industry, medical purpose and research such as non-destructive examination, computed tomography and x-ray, etc. constantly. With use of nuclear or radiation has incidence possibility for example the Fukushima NPP incident, the Goiania accident and the Chernobyl Nuclear accident. Also the risk of terror by radioactive material such as Radiological Dispersal Device(RDD) etc. In Korea, since the 'Law on protection of nuclear facilities and countermeasure for radioactive preparedness was enacted in 2003, the Korean institute of Radiological and Medical Sciences(KIRAMS) was established for the radiation emergency medical response in radiological disaster due to nuclear accident, radioactive terror and so on. Especially National Radiation Emergency Medical Center(NREMC) has the duty that is protect citizens from nuclear, radiological accidents or radiological terrors through the emergency medical preparedness. The NREMC was established by the 39-article law on physical protection of nuclear material and facilities and measures for radiological emergencies. Dose assessment or contamination survey should be performed which provide the radiological information for medical response. For this reason, the NREMC establish and re-organized dose assessment system based on the existing dose assessment system of the NREMC recently. The exposure dose could be measured by physical and biological method. With these two methods, we can have conservative dose assessment result. Therefore the NREMC established the exposure dose assessment laboratory which was re-organized laboratory space and introduced specialized equipment for dose assessment. This paper will report the establishment and operation of exposure dose assessment laboratory for radiological emergency response and discuss how to enhance

Comparative study for environmental assessment by program characters

Energy Technology Data Exchange (ETDEWEB)

Kim, Suk Chul; Lee, Young Soo; Park, Young Min; Park, Suk Soon; Chung, Kyung Tae; Cho, Hong Yun; Chae, Jang Won; Lee, Sang Don; Lee, Chan Ho; Choi, Joon Kyu; Kim, Kang Joo; Chung, Won Moo; Jin, Jae Yool [Korea Environment Institute, Seoul (Korea)

1998-12-01

The level of environmental assessment in Korea was diagnosed by examining the situation of its model for the entire environmental assessment implemented. Also, it proposed an improvement scheme for its problems to be able to advance. It is expected to be utilized as developing optimum model for Korea and establishing a systematic and concrete guideline for environmental assessment modeling. 244 refs., 65 figs., 28 tabs.

Transfer factors for assessing the dose from radionuclides in agricultural products

International Nuclear Information System (INIS)

Ng, Y.C.; Colsher, C.S.; Thompson, S.E.

1979-01-01

Transfer factors to predict the environmental transport of radionuclides through terrestrial foodchains to man were derived from the literature for radionuclides associated with the nuclear fuel cycle. We present updated transfer coefficients to predict the concentration of a radionuclide in cow's milk and other animal products and concentration factors (CF) to predict the concentration in a food or feed crop from that in soil. Where possible we note the variation of the transfer factor with physical and chemical form of the radionuclide and environmental factors, and characterize the distribution and uncertainty in the estimate. The updated transfer factors are compared with those listed in regulatory guides. The new estimates lead to recommended changes (both increases and decreases) in the listed transfer coefficients for milk and meat and to the suggested practice of adopting multiple soil-to-plant CF's that vary with the type of crop and soil in the place of a single generic CF to predict the concentration of a radionuclide in a crop from that in soil. The updated transfer factors will be useful to assess the dose from radionuclides released from nuclear facilities and evaluating compliance with regulations governing the release of radionuclides

Local dose assessment for a contaminated wound