Laboratory of environmental radiological surveillance

International Nuclear Information System (INIS)

Mendez G, A.; Marcial M, F.; Giber F, J.; Montiel R, E.; Leon del V, E.; Rivas C, I.; Leon G, M.V.; Lagunas G, E.; Aragon S, R.; Juarez N, A.; Alfaro L, M.M.

1991-12-01

The department of radiological protection of the ININ requests the collaboration of the Engineering Unit for the elaboration of the work project of the laboratory of environmental radiological surveillance. The emission of radioactive substances to the atmosphere like consequence of the normal operation of the Nuclear Center, constitutes an exhibition source from the man to the radiations that it should be appropriately watched over and controlled to be able to determine the population's potential exhibition that it lives in the area of influence of the installation. (Author)

Follow-up radiological surveillance, Marshall Islands

International Nuclear Information System (INIS)

Greenhouse, N.A.

1978-01-01

The political approvals have been given for the return of Bikini and Enewetak Atolls to their original inhabitants. These two regions, which comprised the Pacific Nuclear Testing Areas from 1946 to 1958, are now being repopulated by their original inhabitants and their families. Recent assessments of internal and external exposure pathways at Bikini and Enewetak have indicated that doses and dose commitments in excess of current radiation protection guidelines are possible or even likely for persons living in these areas. Rongelap and Utirik Atolls, which were downwind of the 1954 Bravo event, also received significant fallout; potential radiological problems exist in these areas as well. In view of this prospect, follow-up environmental monitoring and personnel monitoring programs are being established to maintain our cognizance of radiological conditions, and to make corrective action where necessary. The unexpected finding of detectable amounts (above background) of plutonium in the urine of individuals at Bikini and Rongelap Atolls also raises the possibility of radiological problems in the long term from environmentally-derived plutonium via pathways which are not completely understood. This finding adds further impetus to the surveillance programs for an area where real radiological concerns for the general public are already known to exist. The continuing environmental and personnel monitoring programs which this paper describes are a necessary part of the BNL radiological safety program in the Marshall Islands, which is designed to do the following: (1) elucidate the internal exposure pathways; (2) define the external radiation environment; (3) assess the doses and dose commitments from radioactivity in the environment; (4) provide the feedback necessary to improve existing predictive modelling of radiological trends; and (5) suggest actions which will minimize doses via the more significant pathways. (author)

Environmental Tools and Radiological Assessment

Science.gov (United States)

This presentation details two tools (SADA and FRAMES) available for use in environmental assessments of chemicals that can also be used for radiological assessments of the environment. Spatial Analysis and Decision Assistance (SADA) is a Windows freeware program that incorporate...

Manual for environmental radiological surveillance

International Nuclear Information System (INIS)

Sumiya, Shuichi; Matsuura, Kenichi; Nakano, Masanao; Takeyasu, Masanori; Morisawa, Masato; Onuma, Toshimitsu; Fujita, Hiroki; Mizutani, Tomoko; Watanabe, Hajime; Sugai, Masamitsu

2010-03-01

Environmental radiation monitoring around the Tokai Reprocessing Plant has been conducted by the Nuclear Fuel Cycle Engineering Laboratories, based on 'Safety Regulations for the Reprocessing Plant of JAEA, Chapter IV - Environmental monitoring' and Environmental Radiation Monitoring Program decided by the Ibaraki prefectural government. The radiation monitoring installations and equipments were also prepared for emergency. This manual describes; (1) the installations of radiological measurement, (2) the installations of meteorological observation, and (3) environmental data processing system for executing the terrestrial environmental monitoring by Environmental Protection Section, Radiation Protection Department. The environmental monitoring has been operated through the manual published in 1993 (PNC TN8520 93-001). Then the whole articles were revised because the partially of installations and equipments having been updated in recent years. (author)

Radiological protection and environmental management

International Nuclear Information System (INIS)

Perez Fonseca, A.

2010-01-01

From the beginning of its industrial activity twenty five years ago, the Juzbado Factory of Enusa Group has always upheld a strong commitment with Radiological Protection and environmental respect and protection. Consequently, the evolution of dose shows a downward trend over the years. Although production has been increased gradually, the average doses to workers have stayed below 1 mSv. In order to identify and prevent the potential environmental impacts of its industrial activity and minimize its impact on the surroundings, the facility develops and environmental management system according to UNE-EN-ISO 14001 since 1999. (Author)

Radiological environmental impacts from transportation of nuclear materials

International Nuclear Information System (INIS)

Shuai Zhengqing

1994-01-01

The author describes radiological impacts from transportation of nuclear materials. RADTRAN 4.0 supplied by IAEA was adopted to evaluate radiological consequence of incident-free transportation as well as the radiological risks from vehicular accidents occurring during transportation. The results of calculation show that the collective effective dose equivalent of incident-free transportation to the public and transportation workers is 7.94 x 10 -4 man·Sv. The calculated data suggest that the environmental impacts under normal and assumed accidental conditions are acceptable

Environmental and Radiological Protection Department - DEPRA

International Nuclear Information System (INIS)

1989-01-01

The activities and purposes of the Environmental and Radiological Protection Dept. of the Institute of Radioprotection and Dosimetry form Brazilian CNEN are presented. It is also presented an historical review of its activities, its personnel and its sections. (J.A.M.M.)

Radiochemical characterization and environmental radiological impact in tin and lead processing from cassiterite

International Nuclear Information System (INIS)

Garcia, Marcia Aparecida Antico

2009-01-01

The tin and lead industry located in Pirapora do Bom Jesus in the state of Sao Paulo, Brazil, is responsible for the production of about 7000 ton year-1 of tin and 350 ton year-1 of lead. The raw material used in this facility is cassiterite, which presents in its composition concentrations of natural radionuclides from the uranium and thorium series up to 660 kBq kg -1 and 450 kBq kg -1 , respectively. The smelting and refining processes may lead to concentrations of these radionuclides, mainly in the precipitated dust and in slag. In the operational process, intermediate refining and final slag are obtained and are stored in piles in open air. It is estimated that the amount of waste stored is about 600000 ton. This work aims to study the environmental radiological impact of the operation of this facility and to establish its Environmental Radiological Monitoring Program. In order to accomplish this task the content of radioactivity was determined in the raw material, products, byproducts, residue, deposition pond and exhausting systems. Although in the raw material the radionuclides from the uranium and thorium series are almost in equilibrium, during the processing this equilibrium is disrupted and the radionuclides migrate according to their chemical properties. Concentrations up to 31 kBq kg -1 for 238 U, 69 kBq kg -1 for 226 Ra, 2.5 kBq kg -1 for 210 Pb, 130 kBq kg -1 for 232 Th and 120 kBq kg -1 for 228 Ra were obtained in the slag. The environmental radiological impact was established by measuring the radionuclides in the critical compartments that is the ones that may cause exposure to the public. If the residue pile is considered, the critical pathways are the internal exposition from the dust inhalation and the water ingestion, due to re suspension and dispersion of the pile dust and groundwater contamination, respectively; and external exposure due to immersion in the radioactive cloud and soil contamination. For the emission of gaseous and particulate

Radiological and environmental surveillance in front-end fuel cycle facilities

International Nuclear Information System (INIS)

Khan, A.H.; Sahoo, S.K.; Tripathi, R.M.

2004-01-01

This paper describes the occupational and environmental radiological safety measures associated with the operations of front end nuclear fuel cycle. Radiological monitoring in the facilities is important to ensure safe working environment, protection of workers against exposure to radiation and comply with regulatory limits of exposure. The radiation exposure of workers in different units of the front end nuclear fuels cycle facilities operated by IREL, UCIL and NFC and environmental monitoring results are summarised

Environmental aspects at radiological protection in ArcelorMittal Monlevade

International Nuclear Information System (INIS)

Silva Filho, Cleber Marques; Soares Filho, Mauricio; Franco, Jose Otavio Andrade; Leite, Roberto Paulo; Goncalves, Breno Cunha; Costa, Jose Gustavo de Souza

2010-01-01

ArcelorMittal Monlevade Environmental Management of Radiological Protection is based on radiological protection team training, start up of radioactivity materials detection equipment in several steps of industrial processes and internal procedures according to CNEN - Nuclear Energy National Commission guidelines. At this way ArcelorMittal Monlevade seeks to guarantee the safety of employees, community, customers, equipment and the environment and their business. (author)

Application of improved topsis method to comprehensive assessment of radiological environmental quality

International Nuclear Information System (INIS)

Shi Dongsheng; Di Yuming; Zhou Chunlin

2007-01-01

TOPSIS is a method for multiobjective decision-making, which can be applied to comprehensive assessment of radiological environmental quality. This paper introduces the principle of TOPSIS method and sets up the model of improved TOPSIS method, discusses the application of improved TOPSIS method to comprehensive assessment of radiological environmental quality. This method sufficiently makes use of the information of the optimal matrix. Analysis of practical examples using MATLAB program shows that it is objectively reasonable and feasible to comprehensively assess radiological environmental quality by improved TOPSIS method. This paper also provides the result of optimum number of sites and compares it with optimal index method based on TOPSIS method and traditional method. (authors)

Results of the radiological environmental monitoring network in the Central Eastern region of Cuba

International Nuclear Information System (INIS)

Montalvan Estrada, O.; Brigido Flores, R.; Rosa Suarez, R.; Barreras Caballero, A.; Damera Martinez, A.

1998-01-01

The radiological environmental monitoring laboratory of Camaguey is a member of the Cuban radiological environmental network and it has been carried out a series of measures about radioactivity in the atmosphere: gamma-dose rate, gross-beta activities in fallout and in aerosols. The results show that this region has a low radiological background and it has been exposure contamination

National automatic network of environmental radiological monitoring (RENAMORA)

International Nuclear Information System (INIS)

Gonzalez M, J.L.; Sanchez H, L.

2003-01-01

Inside the programs of Environmental Radiological Surveillance that it carries out the National Commission of Nuclear Security and Safeguards (CNSNS), it develops an National Automatic Network of Environmental Radiological Monitoring (RENAMORA), where it is carried out a registration of speed of environmental dose in continuous and simultaneous forms with the same moment of the measurement. This net allows to account with the meticulous and opportune information that will help to characterize, in dynamics form, the radiological conditions of diverse geographical zones of the country, including the sites that by normative require bigger surveillance, like its are the Laguna Verde Nuclear power station (CNLV), the Nuclear Center of Mexico (ININ) and the Radioactive waste storage center (CADER). This net is in its first development stage; three points inside the state of Veracruz, in the surroundings of the CNLV, already its are operating; the obtained data of rapidity of environmental dose are being stored in a database inside a primary data center located in the facilities of the CNSNS in Mexico city and its will be analyzed according to the project advances. At the moment, its are installing the first ten teams corresponding to the first phase of the RENAMORA (three stages); its are carried out operation tests, transmission, reception and administration of data. The obtained data will be interpreted, analyzed and inter compared to evaluate the risk levels to that it would be hold the population and to determine thresholds that allow to integrate the alarm systems that its had considered for emergency situations. (Author)

Development of an integrated system for evaluation of environmental radiologic impact during emergency situations

International Nuclear Information System (INIS)

Conti, Luiz Fernando de Carvalho

2002-03-01

An integrated system for performing environmental dose assessment after nuclear or radiological emergencies has been developed, as a tool for decision making process. The system includes databases such as those describing radionuclide decay, dose conversion factors for several environmental geometries and radionuclides with emitted radiation and energies. It includes several models for predicting environmental behaviour at the short,medium and long terms, for both rural and urban environments and is flexible enough for simulating the exposure of members of the public due to small accidents involving individual sources up to large scale nuclear accidents with complex source terms to the environment. The model has been built in a way that can perform assessment of actual exposures or make forecasts for future exposure based on dynamic simulation of the fate of radionuclides in environmental and potential exposure pathways to members of the public, taking into account he kind of contaminated environment and the age groups of exposed persons. Input data may come from a predicted source term or information on environmental concentration based on dispersion models or on environmental measurements, including on line monitoring systems, environmental surveys, direct measurements by in situ gamma spectrometry or analysis of environmental samples. Outputs of the model are dose estimates to members of the public as a function of the exposure pathway, time after the contamination and age group, for different groups of members of the public and kind of use of the environment. Time dependent kerma rates in air and concentrations in environmental compartments such as soil and foodstuff are also available, including the simulation of the effect of protective measures, to support the decision making process. (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)

Radiological Protection and Environmental Monitoring in Bolivia

International Nuclear Information System (INIS)

MartInez Pacheco, J.

1979-01-01

The paper describes the main activities of the Department of Radiological Protection, Nuclear Energy Commission of Bolivia. The following topics are covered: organization, environmental control of air, water, milk and plants, personal dosimetry, instrumentation and calibration, protection in uranium mines. Standard setting and international cooperation aspects are also presented

Parameters used in the environmental pathways and radiological dose modules of the Phase I air pathway code

International Nuclear Information System (INIS)

Shindle, S.F.; Ikenberry, T.A.; Napier, B.A.

1992-05-01

This report is a description of work performed for the Hanford Environmental Dose Reconstruction (HEDR) Project. The HEDR Project was established to estimate radiation doses to individuals resulting from releases of radionuclides from the Hanford Site since 1944, when facilities there first began operating. An independent Technical Steering Panel directs the project, which is conducted by Battelle staff from the Pacific Northwest Laboratory. The objective of Phase 1 of the HEDR Project was to demonstrate through calculation that adequate models and support data existed or could be developed to allow estimation of realistic doses to individuals from historical Hanford Site radionuclide releases. The HEDR Phase 1 computer code was used to model the transport of iodine-131 released to the atmosphere from the Hanford Site facilities, through environmental pathways to points of human exposure. Output from the code was preliminary estimates of doses received by members of the public living in the vicinity of the Hanford Site. Later project work continues to build upon Phase 1 progress in order to refine dose estimates

Annual Radiological Environmental Monitoring Program Report for the Three Mile Island, Unit 2, Independent Spent Fuel Storage Installation

International Nuclear Information System (INIS)

Hall, Gregory Graham

2002-01-01

This report presents the results of the 2001 Radiological Environmental Monitoring Program conducted in accordance with 10 CFR 72.44 for the Three Mile Island, Unit 2, Independent Spent Fuel Storage Installation. A description of the facility and the monitoring program is provided. The results of monitoring the two predominant radiation exposure pathways, potential airborne radioactivity releases and direct radiation exposure, indicate the facility operation has not contributed to any increase in the estimated maximum potential dose commitment to the general public.

A probabilistic approach to Radiological Environmental Impact Assessment

International Nuclear Information System (INIS)

Avila, Rodolfo; Larsson, Carl-Magnus

2001-01-01

Since a radiological environmental impact assessment typically relies on limited data and poorly based extrapolation methods, point estimations, as implied by a deterministic approach, do not suffice. To be of practical use for risk management, it is necessary to quantify the uncertainty margins of the estimates as well. In this paper we discuss how to work out a probabilistic approach for dealing with uncertainties in assessments of the radiological risks to non-human biota of a radioactive contamination. Possible strategies for deriving the relevant probability distribution functions from available empirical data and theoretical knowledge are outlined

Radiological and environmental safety in front-end fuel cycle facilities

International Nuclear Information System (INIS)

Puranik, V.D.

2011-01-01

The front end nuclear fuel cycle comprises of mining and processing of beach mineral sands along the southern coast of Kerala, Tamilnadu and Orissa, mining and processing of uranium ore in Singhbhum-East in Jharkhand and refining and fuel fabrication at Hyderabad. The Health Physics Units (HPUs)/Environmental Survey Laboratories (ESLs) set up at each site from inception of operation to carry out regular in-plant, personnel monitoring and environmental surveillance to ensure safe working conditions, evaluate radiation exposure of workers, ensure compliance with statutory norms, help in keeping the environmental releases well within the limits and advise appropriate control measures. This paper describes the occupational and environmental radiological safety measures associated with the operations of front end of nuclear fuel cycle. Radiological monitoring in these facilities is important to ensure safe working environment, protection of workers against exposure to radiation and comply with regulatory limits of exposure. The radiation exposure of workers in different units of the front end nuclear fuels cycle facilities operated by IREL, UCIL and NFC and environmental monitoring results are summarised in this paper

Recommended protocol for standardization in collecting and interpreting radiological environmental data

International Nuclear Information System (INIS)

Denham, D.H.; Kathren, R.L.

1989-02-01

Current reductions in ''allowable'' levels of radiation and radioactive materials in the environment and an increased public awareness of naturally occurring radioactive materials have reinforced the need for consistency in evaluating the radiological environment. A key concern is the identification and interpretation of environmental levels of radiation and radioactive materials resulting from nuclear facility operations. If these levels can be detected and their source(s) identified, then corrective actions can be taken to eliminate or greatly reduce the environmental impacts of the facility operations. In this paper we address the lack of definitive guidance necessary to determine incremental levels of significance (or insignificance), and we propose a series of protocols to achieve more consistent collection and interpretation of radiological environmental data. 8 refs

The Mobile Surface Contamination Monitor II environmental radiological characterization utilizing GPS/GIS technologies

International Nuclear Information System (INIS)

Wendling, M.A.

1993-05-01

Time, cost, and most importantly quality of data are the three factors to measure the success of field radiological characterizations. The application of coupling radiation detection instrumentation to a GPS receiver has dramatically increased the data quality achievable compared to traditional environmental radiological survey methods. Improvements in verifying adequate spatial coverage of an area while collecting data and at,the same time reducing field time requirements can be realized. Data acquired during the recent implementation of the Mobile Surface Contamination Monitor 11 (MSCM-11) will be presented to demonstrate the advantages of this system over traditional radiological survey methods. The comparison will include time and manpower requirements. Linking the complimentary GPS, GIS and radiation detection technologies on a mobile tractor based platform has provided a tool to provide radiological characterization data faster, cheaper, and better to assist in the Environmental Restoration Mission of the Hanford Site

Monitoring of the radiological environmental impact of the AREVA site of Tricastin

International Nuclear Information System (INIS)

Mercat, C.; Brun, F.; Florens, P.; Petit, J.; Garnier, F.; Devin, P.

2010-01-01

Set up at the beginning of the site's operations, in 1962, the monitoring of the radiological environmental impact of the AREVA site of Tricastin has evolved over time to meet more specifically the multiple objectives of environmental monitoring: to prove the respect of the commitments required by the authorities, to be able to detect a dysfunction in the observed levels, to enable the assessment of impacts of industrial activities, to ensure the balance between environmental quality and the use made by the local population and to inform the public of the radiological state of the environment. Thousands of data were acquired on the radioactivity of all environmental compartments as well as on the functioning of local ecosystems. Today, the Network of Environmental Monitoring of AREVA Tricastin goes beyond the requirements of routine monitoring to provide innovative solutions for monitoring the radioactivity (especially for uranium) in the environment. (author)

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

Laboratory of environmental radiological surveillance; Laboratorio de vigilancia radiologica ambiental

Energy Technology Data Exchange (ETDEWEB)

Mendez G, A; Marcial M, F; Giber F, J; Montiel R, E; Leon del V, E; Rivas C, I; Leon G, M V; Lagunas G, E; Aragon S, R; Juarez N, A; Alfaro L, M M

1991-12-15

The department of radiological protection of the ININ requests the collaboration of the Engineering Unit for the elaboration of the work project of the laboratory of environmental radiological surveillance. The emission of radioactive substances to the atmosphere like consequence of the normal operation of the Nuclear Center, constitutes an exhibition source from the man to the radiations that it should be appropriately watched over and controlled to be able to determine the population's potential exhibition that it lives in the area of influence of the installation. (Author)

Environmental protection: Researches in National Inst. of Radiological Sciences

International Nuclear Information System (INIS)

Fuma, S.; Ban-nai, T.; Doi, M.; Fujimori, A.; Ishii, N.; Ishikawa, Y.; Kawaguchi, I.; Kubota, Y.; Maruyama, K.; Miyamoto, K.; Nakamori, T.; Takeda, H.; Watanabe, Y.; Yanagisawa, K.; Yasuda, T.; Yoshida, S.

2011-01-01

Some studies for radiological protection of the environment have been made at the National Inst. of Radiological Sciences (NIRS). Transfer of radionuclides and related elements has been investigated for dose estimation of non-human biota. A parameter database and radionuclide transfer models have been also developed for the Japanese environments. Dose (rate)-effect relationships for survival, growth and reproduction have been investigated in conifers, Arabidopsis, fungi, earthworms, springtails, algae, duckweeds, daphnia and medaka. Also genome-wide gene expression analysis has been carried out by high coverage expression profiling (HiCEP). Effects on aquatic microbial communities have been studied in experimental ecosystem models, i.e., microcosms. Some effects were detected at a dose rate of 1 Gy day -1 and were likely to arise from inter-species interactions. The results obtained at NIRS have been used in development of frameworks for environmental protection by some international bodies, and will contribute to environmental protection in Japan and other Asian countries. (authors)

Evaluation of the non-radiological environmental problems relating to the WIPP

International Nuclear Information System (INIS)

Baca, T.E.

1983-02-01

The major non-radiological environmental problems addressed are: air pollution, water pollution and sanitary waste, solid waste, domestic drinking water, occupational health and safety and toxic chemicals

Laboratory of environmental radiological surveillance; Laboratorio de vigilancia radiologica ambiental

Energy Technology Data Exchange (ETDEWEB)

Mendez G, A.; Marcial M, F.; Giber F, J.; Montiel R, E.; Leon del V, E.; Rivas C, I.; Leon G, M.V.; Lagunas G, E.; Aragon S, R.; Juarez N, A.; Alfaro L, M.M

1991-12-15

The department of radiological protection of the ININ requests the collaboration of the Engineering Unit for the elaboration of the work project of the laboratory of environmental radiological surveillance. The emission of radioactive substances to the atmosphere like consequence of the normal operation of the Nuclear Center, constitutes an exhibition source from the man to the radiations that it should be appropriately watched over and controlled to be able to determine the population's potential exhibition that it lives in the area of influence of the installation. (Author)

Environmental Radiological Impact of Nuclear Power. Monitoring and Control Programs

International Nuclear Information System (INIS)

Ramos, L. M.

2000-01-01

Radioactive contamination of the environment and public exposure to ionizing radiation may result from releases from programmed or accidental operations in regulated activities, or they may be due to preexisting situations such as contamination caused by past accidents, radioactive rain caused by nuclear tests, or increased natural radioactivity resulting from human activities. In many cases, both the emission sources and the environment should be monitored to determine the risk to the population and verify to what extent the limits and conditions established by competent authorities are being observed. Monitoring can be divided into three categories: monitoring of the emission source, of the receiving medium and of members of the public; individual monitoring of the population is extremely rare and would only be considered when estimated doses substantially exceed the annual public dose limit. In practices likely to produce significant radioactive releases, as is the case of nuclear fuel cycle facilities, the limits and conditions for monitoring and controlling them and the requirements for environmental radiological monitoring are established in the licensing process. Programs implemented during normal operation of the facilities form the basis for monitoring in the event of accidents. in addition to environmental radiological monitoring associated with facilities, different countries have monitoring programs outside the facilities zones of influence, in order to ascertain the nationwide radiological fund and determine possible increases in this fund. In Spain, the facilities that generate radioactive waste have effluent storage, treatment and removal systems and radiological monitoring programs based on site and discharge characteristics. The environmental radiological monitoring system is composed of the network implemented by the owners in the nuclear fuel cycle facilities zones of influence, and by nationwide monitoring networks managed by the Consejo de

Guide for environmental radiological surveillance at ERDA installations

International Nuclear Information System (INIS)

Corley, J.P.; Denham, D.H.; Michels, D.E.; Olsen, A.R.; Waite, D.A.

1977-03-01

This Guide is intended to: Provide recommended methods, procedures, and performance criteria to bring greater comparability to ERDA environmental monitoring and reporting systems; provide ERDA management, particularly the Headquarters' Division of Safety, Standards, and Compliance (SSC) and field offices, with a broad review of accepted radiological surveillance practices for use in the evaluation of environmental surveillance programs at ERDA facilities; and delineate the capabilities and limitations of the various environmental monitoring systems for radioactivity currently used at ERDA sites, including technical areas where there is either an inadequate basis for procedural selection or where further developmental work may be warranted. The discussion of equipment, measurement techniques, and quality control procedures, although believed to represent current technology, is subject to continuing change as technological improvements become available

Quarterly environmental radiological survey summary - second quarter 1997 100, 200, 300, and 600 areas

International Nuclear Information System (INIS)

McKinney, S.M.; Marks, B.M.

1997-01-01

This report provides a summary of the radiological surveys performed in support of near-facility environmental monitoring at the Hanford Site. The Second Quarter 1997 survey results and the status of actions required are summarized below: All of the routine environmental radiological surveys scheduled during April, May, and June 1997, were performed as planned with the exception of UN-216-E-9. This site was not surveyed as stabilization activities were in progress. The sites scheduled for the Environmental Restorations Contractor (ERC) team were switched with those identified for the third quarter as there was a conflict with vegetation management activities

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.

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

Age dependent food consumption data provided for the computation of the radiological impact via the ingestion pathway

International Nuclear Information System (INIS)

Kalckbrenner, R.; Bayer, A.

1979-08-01

Averaged age dependent food consumption data are compiled and evaluated to provide input data for the computation of the radiological impact via the ingestion pathway. For special population groups (self-suppliers e.g.) factors are provided, by which the consumption for special foods may be exceeded. The evaluated data are compared with those of the 'USNRC-Regulatory Guide 1.109 (revised 1977)' and those of the 'Recommendation of the German Commission on Radiological Protection (Draft 1977)'. (orig.) [de

RENDAC: Integrated System Data for the Information Control the Environmental Radiological Surveillance the National Network in Cuban Republic

International Nuclear Information System (INIS)

Valdes Ramos, M.; Prendes Alonso, M.

1998-01-01

With the objective to evaluate, process, control and to store the information that is generated in the National Environmental Radiological Surveillance Network, it is designed and I program the on-line RENDAC system that allows to capture and evaluate the parameters that characterize the environmental radiological situation

RI Mapping System for Identification of Radiological Contamination in Environmental Water Supply System

Energy Technology Data Exchange (ETDEWEB)

Na, Teresa W.; Ha, Jang Ho; Kim, Han Soo; Lee, Seung Hyun [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Na, Teresa W.; Lee, Rena [Ewha Womans Univ., Hospital, Seoul (Korea, Republic of)

2012-03-15

The interest of radiation protection has risen due to accidents of the Nuclear Power Plant, nuclear terrorism, and the radiological contamination in the city, In this respect, the development of environmental radiation monitoring for the radiological contaminants has been studied. In this study, the experiment for the radiological contamination in the water supply pipe line system has been simulated and preliminarily tested. The CsI(Tl)-PIN diode detectors were used and the preliminary test of radiation monitoring system was performed as multi detection system. The 2D image reconstruction algorithm was also developed for feasibility of the constructed multi-detection system.

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

Model for the elaboration of program of environmental radiological monitoring reports

International Nuclear Information System (INIS)

2005-11-01

This Regulation refers to the requirements of the Regulation CNEN-NN.3.01 'Basic Guidelines for Radiation Protection', expressed in the section 5.14, and its application related to the emission of reports of Environmental Radiological Monitoring Program to be submitted to CNEN evaluation

Radiological analyses of Marshall Islands environmental samples, 1974--1976

International Nuclear Information System (INIS)

Greenhouse, N.A.; Miltenberger, R.P.; Cua, F.T.

1977-01-01

Results are reported from the radiological analysis of environmental samples collected in the Marshall Islands during 1974 through 1976. Most of the samples were collected on or near the Bikini Atoll and included plants, soil, fish, catchment water, and sediments, with emphasis on local marine and terrestrial food items. Data are presented from γ spectral analysis and the content of 90 Sr and transuranic elements in the samples

Application of radiological protection measures to meet different environmental protection criteria

International Nuclear Information System (INIS)

Copplestone, D.

2012-01-01

The International Commission on Radiological Protection (ICRP) recognises that there is no simple or single universal definition of ‘environmental protection’, and that the concept differs from country to country and from one circumstance to another. However, there is an increasing need to be able to demonstrate that the environment is protected from radioactive substances released under authorisation for various reasons, such as for wildlife conservation requirements, or wildlife management for commercial reasons, or simply as part of pollution control. The Commission is developing the concept of Representative Organisms, which may be identified from any specific legal requirements or from more general requirements to protect local habitats or ecosystems. Such organisms may be the actual objects of protection or they may be hypothetical, depending on the objectives of the assessment. They may be similar to, or even congruent with, one or more of the Reference Animals and Plants (RAPs). Where this is not the case, attempts can be made to consider the extent to which the Representative Organisms differ from the nearest RAP in terms of known radiation effects upon it, basic biology, radiation dosimetry, and pathways of exposure. This paper discusses the practical implications of such an approach.

Environmental radioactivity in Canada 1988. Radiological monitoring annual report

Energy Technology Data Exchange (ETDEWEB)

1992-12-31

The radiological surveillance program of the Department of National Health and Welfare is conducted for the purpose of determining levels of environmental radioactivity in Canada and assessing the resulting population exposures. Following major changes to the CAMECO Port Hope operations to reduce uranium emissions, a study was initiated to measure uranium levels in air in the community. Studies continued on lung cancer and domestic exposure to radon, and current levels of cesium-137 in caribou, a major source of food in northern communities. The movement of tritium on the Ottawa and St. Lawrence rivers was studied following an accidental release into the Ottawa River. Monitoring continued of fallout contamination from Chernobyl in imported foods. All measurements recorded during 1988 were below the limits recommended by the International Commission on Radiological Protection. (14 refs., 14 figs., 15 tabs.).

Technological and operational structure of the National Automatic Network for Environmental Radiological Monitoring (RENAMORA)

International Nuclear Information System (INIS)

Martinez G, E.; Lopez G, M.; Aguirre G, J.; Fabian O, R.; Hernandez A, Y.

2015-09-01

The Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) in Mexico is a decentralized body, under the Secretaria de Energia whose main mission is to ensure that activities involving nuclear and radioactive materials as well as ionizing radiation sources are carried out with maximum security, considering the current technological developments. In order to monitor the levels of environmental radiation to which the population is exposed, the CNSNS has established a series of radiological monitoring programs that allow characterize the environmental radiation levels in each zone or region in the country; to identify the occurrence of natural or artificial radiological events, such as nuclear tests and accidents in radioactive or nuclear facilities. The National Automatic Network for Environmental Radiological Monitoring (RENAMORA) project was initiated with the support of the IAEA through MEX9/049 project and its purpose is to have a network of instruments that automatically and in real time, transmit information of the gamma radiological environmental status of the national territory and changes occurring in it. This network provides data such as the speed of ambient dose equivalent, temperature and humidity in different regions of the country. The network is composed of 92 stations that are distributed throughout the national territory. The structure of the stations has evolved since its inception, now allowing detection tasks, data transmission and managing them remotely from the main server, which is located in the CNSNS, which is performed a statistical dose for each monitoring station. Each monitoring station is formed in its current structure by a probe detection of gamma radiation, a communication module and associated electronics, a mini Web server DataGATE, a cellular modem and an interface converter. (Author)

Using the model release ARTM associated with resources for simulation geoprocessing radiological environmental impact of atmospheric emissions from a research reactor

International Nuclear Information System (INIS)

Alves, Simone Fonseca

2013-01-01

The knowledge of the dispersion of radionuclides emissions into the atmosphere arising from a nuclear reactor, in normal operation, is an important step in the process of the nuclear and environmental assessment study. These processes require an assessment study of the radiological environmental impact. However, to estimate this impact a simulation of the transport mechanisms and deposition of pollutants released into the atmosphere is required. The present study aimed at the application of the dispersion model ARTM (Atmospheric Radionuclide Transport Model), together with the powerful tools of the GIS (Geographic Information System) for the environmental impact assessment of a radiological nuclear reactor under typically routine and conditions. Therefore some important information from the national project for a research reactor known as Brazilian Multipurpose Reactor (RMB) was considered. The information of the atmospheric emissions of the reactor, needed for the simulation of this project, was based on data of the Open Pool Australian Light Water (OPAL).Other important data that had to be collected and analyzed were the source term, the topography, the meteorology and the environmental data. The radionuclides analyzed as pollutants were 41 Ar; 140 Ba; 51 Cr; 137 Cs; 131 I; 133 I; 85m Kr; 87 Kr; 88 Kr; 140 La; 133 Xe; 135 Xe; 3 H; 90 Sr. The model was run for two chronological scenarios according to their meteorological data for the years 2009 and 2010, respectively. The adoption of GIS techniques was relevant in planning, data preprocessing and in the post-processing of results as well. After pre-processing, the input data were processed by the ARTM dispersion model. Maps, charts, and tables were then produced and evaluated. According to the simulated and evaluated scenarios it could be concluded that exposure pathways that mostly contributed to the dose for individual public were 41 Ar, for immersion in the plume, and 133 I, for inhalation. Nevertheless, even

Environmental and radiological remediation under Canada's global partnership program 2004-11 - 59185

International Nuclear Information System (INIS)

Washer, Michael J.

2012-01-01

Following the '911' attack on the USA in 2001 the international community under Canada's G8 leadership established a $20 billion Global Partnership initiative in 2002 to collaboratively address threats to global security posed by the proliferation and potential terrorist use of Weapons and Materials of Mass Destruction (WMMD) and related materials and knowledge. This major international initiative addressed four priority areas: (1) Chemical Weapon Destruction (2) Nuclear powered submarine eliminations (3) Nuclear and radiological security; and (4) Employment for former weapon scientists. Additionally the initiative has addressed Biological Non- Proliferation. Canada's execution of all these program areas has resulted in substantial environmental benefits aside from the eradication and securing of WMMD. This paper reviews the environmental and radiological remediation achievements of the four primary Global Partnership program areas addressed under Canadian funding 2004 through 2011. (author)

Quality control activities in the environmental radiology laboratory

International Nuclear Information System (INIS)

Llaurado, M.; Quesada, D.; Rauret, G.; Tent, J.; Zapata, D.

2006-01-01

During the last twenty years many analytical laboratories have implemented quality assurance systems. A quality system implementation requires documentation of all activities (technical and management), evaluation of these activities and its continual improvement. Implementation and adequate management of all the elements a quality system includes are not enough to guarantee quality of the analytical results generated at a time. That is the aim of a group of specific activities labelled as quality control activities. The Laboratori de Radiologia Ambiental (Environmental Radiology Laboratory; LRA) at the University of Barcelona was created in 1984 to carry out part of the quality control assays of the Environmental Radiology Monitoring Programs around some of the Spanish nuclear power plants, which are developed by the Servei Catala d'Activitats Energetiques (SCAR) and the Consejo de Seguridad Nuclear (CSN), organisations responsible for nuclear security and radiological protection. In these kind of laboratories, given the importance of the results they give, quality control activities become an essential aspect. In order to guarantee the quality of its analytical results, the LRA Direction decided to adopt the international standard UNE-EN ISO/IEC 17025 for its internal quality system and to accreditate some of the assays it carries out. In such as system, it is established, the laboratory shall monitor the validity of tests undertaken and data shall be recorded in such a way that trends are detectable. The present work shows the activities carried out in this way by the LRA, which are: Equipment control activities which in the special case of radiochemical techniques include measurement of backgrounds and blanks as well as periodical control of efficiency and resolution. Activities to assure the specifications settled by method validation, which are testing of reference materials and periodical analysis of control samples. Evaluation of the laboratory work quality

Uranium mining and milling sites in Argentina: environmental radiological monitoring (1980-1994)

International Nuclear Information System (INIS)

Bomben, A.M.; Gomez, J.C.; Oliveira, A.A.

1995-01-01

Environmental radiological monitoring in the vicinity of uranium mining and milling plants in Argentina is performed on a routine basis, in order to assess the possibility of significant environmental contamination due to uranium mill wastes and mill tailings of plants still operating or those where the exploitation have concluded. Dissolved natural uranium and 226 Ra concentrations in surface waters are measured in samples taken from rivers near the mills, according to a special monitoring plan set up for each facility. In addition, 222 Rn emanation rates from ore tailings are measured at times. In this paper the environmental radiological monitoring program results obtained for the 1980-1994 period are shown. From the data analyses it can be concluded that there are not significant differences for the concentrations of the radionuclides of interest, between the surface water samples taken from river location above and below the plants discharge points. Besides, no significant exposure results for the population living in the surrounding areas due to the uranium mining and milling plants operation or their wastes. (author). 2 refs., 5 figs

Radioactive Waste Management Complex low-level waste radiological performance assessment

Energy Technology Data Exchange (ETDEWEB)

Maheras, S.J.; Rood, A.S.; Magnuson, S.O.; Sussman, M.E.; Bhatt, R.N.

1994-04-01

This report documents the projected radiological dose impacts associated with the disposal of radioactive low-level waste at the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory. This radiological performance assessment was conducted to evaluate compliance with applicable radiological criteria of the US Department of Energy and the US Environmental Protection Agency for protection of the public and the environment. The calculations involved modeling the transport of radionuclides from buried waste, to surface soil and subsurface media, and eventually to members of the public via air, groundwater, and food chain pathways. Projections of doses were made for both offsite receptors and individuals inadvertently intruding onto the site after closure. In addition, uncertainty and sensitivity analyses were performed. The results of the analyses indicate compliance with established radiological criteria and provide reasonable assurance that public health and safety will be protected.

Radioactive Waste Management Complex low-level waste radiological performance assessment

International Nuclear Information System (INIS)

Maheras, S.J.; Rood, A.S.; Magnuson, S.O.; Sussman, M.E.; Bhatt, R.N.

1994-04-01

This report documents the projected radiological dose impacts associated with the disposal of radioactive low-level waste at the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory. This radiological performance assessment was conducted to evaluate compliance with applicable radiological criteria of the US Department of Energy and the US Environmental Protection Agency for protection of the public and the environment. The calculations involved modeling the transport of radionuclides from buried waste, to surface soil and subsurface media, and eventually to members of the public via air, groundwater, and food chain pathways. Projections of doses were made for both offsite receptors and individuals inadvertently intruding onto the site after closure. In addition, uncertainty and sensitivity analyses were performed. The results of the analyses indicate compliance with established radiological criteria and provide reasonable assurance that public health and safety will be protected

Quarterly environmental radiological survey summary: First quarter 1995 100, 200, 300, and 600 Areas

International Nuclear Information System (INIS)

McKinney, S.M.

1995-04-01

This report provides a summary of the radiological surveys performed in support of the operational environmental monitoring program at the Hanford Site. The surveys included in this program consist of inactive waste sites; outdoor radiological control areas; tank farm perimeters and associated diversion boxes, lift stations, and vent stations; perimeters of active or uncovered waste sites such as burial grounds, retention basins, ponds, process trenches, and ditches; and road and rail surfaces. This report provides a summary of the radiological surveys performed during the First Quarter of 1995. The status of corrective actions required from current and past reports are also discussed

Transfer of radionuclides to man through environmental pathways

International Nuclear Information System (INIS)

Mitchell, N.T.

1974-01-01

The most widely accepted method in current use for the evaluation of environmental impact from releases of radioactivity that may cause human radiation exposure used an environmental pathway model. The more important aspects of the model involve the use of critical pathway techniques to set controls on the releases of radioactive material to the environment and to assess the human radiation exposure arising as a consequence. The basic concepts of the environmental pathway model and its application are discussed. The model depends on achieving an understanding of radionuclide behavior in the environment, from the moment of release up to the time when contamination results in radiation exposure to the public. Exposure may be as a result of contaminated material entering the body-as air, water or a foodstuff; alternatively, it may be due to radiation whose source is external to the body. For each of these types of exposure pathway the sequence of events can be divided up into a number of compartments, between which transfer takes place. Transfer along the pathway is a dynamic process and can be described mathematically in terms of transfer functions between interacting compartments. Alternatively, for the situation of a regular discharge resulting in a steady-state condition the relationship between compartments can be expressed as a 'concentration factor'. The derivation of both of these terms is described and some aspects of their use are discussed. The paper then goes on to discuss the types of environmental pathway that are encountered as a result of release of radionuclides to the atmospheric and aquatic environments. Disposal to the ground is regarded as a special case of release to the aquatic environment. Some ot the literature on the subject is reviewed in discussingthe better known pathways showing what, to date, have been the most important mechanisms of transfer of radionuclides to man. (author)

The Multimedia Environmental Pollutant Assessment System (MEPAS reg-sign): Completely-Stirred Tank Reactor (CSTR) formulations for the wetland pathway

International Nuclear Information System (INIS)

McDonald, J.P.; van der Aa, N.G.F.M.; Whelan, G.

1997-06-01

The Multimedia Environmental Pollutant Assessment System (MEPAS) is a physics-based environmental analysis code integrating source-term, fate, and exposure models for concentration, dose, or risk endpoints. Developed by Pacific Northwest National Laboratory for the US Department of Energy, MEPAS is designed for site-specific assessments using readily available information. Endpoints are computed for chemical and radioactive pollutants. For human health impacts, risks are computed for radioactive and hazardous carcinogens, and hazard quotients for noncarcinogens. This system has wide applicability to environmental problems using air, groundwater, surface-water, overland, wetland, and exposure models. MEPAS enables users to simulate release of contaminants from a source; transport of contaminants through the air, groundwater, surface-water, overland, or wetland pathways; and transfer of contaminants through food chains and exposure pathways to the exposed individual or population. Whenever available and appropriate, guidance and/or models from the US Environmental Protection Agency, International Commission on Radiological Protection, and National Council on Radiation Protection and Measurements were used to facilitate compatibility and acceptance. Although based on relatively standard transport and exposure computation approaches, MEPAS uniquely integrated these approaches into a single system, providing a consistent basis for evaluating health impacts for a large number of problems and sites. Implemented on a desktop computer, a user-friendly platform allows the user to define the problem, input the required data, and execute the appropriate models. This document describes the mathematical formulations for the Completely-Stirred Tank Reactor (CSTR) component of MEPAS as applied to the wetland pathway

Radiological and environmental studies at uranium mills: a comparison of theoretical and experimental data

International Nuclear Information System (INIS)

Momeni, M.H.; Kisieleski, W.E.; Yuan, Y.; Roberts, C.J.

1978-01-01

Evaluation of radiological risk of uranium milling is based on identification and quantification of sources of release and consideration of dynamic coupling among the meteorological, physiographical, hydrological environments and the affected individuals. Dispersion pathways of radionuclides are through air, soil, and water, each demanding locally tailored procedures for estimation of the rate of release of radioactivity and the pattern of biological uptake and exposure. The Uranium Dispersion and Dosimetry Code (UDAD), a comprehensive method for estimating the concentrations of the released radionuclides, dose rates, doses, and radiological health effects, is described. Predicted concentrations and exposure rates are compared with experimental data obtained from field research at active mills and abandoned tailings

Radiological Medical Device Innovation: Approvals via the Premarket Approval Pathway From 2000 to 2015.

Science.gov (United States)

Ghobadi, Comeron W; Hayman, Emily L; Finkle, Joshua H; Walter, Jessica R; Xu, Shuai

2017-01-01

The aim of this study was to critically assess the clinical evidence leading to radiologic medical device approvals via the premarket approval pathway from 2000 to 2015. This study used the publically available FDA premarket database for radiologic device approvals over the past 15 years (September 1, 2000, to August 31, 2015). Approval characteristics were collected for each device, and statistical analysis was performed on the data for each pivotal trial. Additionally, methodological quality of the pivotal trial was determined using the Quality Assessment of Diagnostic Accuracy Studies tool. Twenty-three class III radiologic device approvals were identified, with breast imaging accounting for 16 (70%) and computer-aided detection software accounting for 9 (39%) approvals. The median premarket approval time was 475 days (range, 180-1,116). Twenty-one devices were approved on the basis of multireader, multicenter studies, one on the basis of a randomized controlled trial, and one on the basis of a preclinical technical equivalence trial. The median number of patients per pivotal trial was 201 (range, 25-3,946). Twenty-six of the 34 pivotal trials (76%) had at least one methodologic bias. Breast imaging devices had a greater number of patients per pivotal trial (P = .009) and more prospective studies. With regard to all modalities, increased time to device approval correlated with weaker trial quality (r = 0.600, P assessing diagnostic technologies. Given that radiologic devices play a key role in modern medicine, further efforts should be made to increase transparency of clinical data leading to approval. Copyright © 2016 American College of Radiology. Published by Elsevier Inc. All rights reserved.

Radiological protection and environmental management; La proteccion radiologica y la gestion ambiental

Energy Technology Data Exchange (ETDEWEB)

Perez Fonseca, A.

2010-07-01

From the beginning of its industrial activity twenty five years ago, the Juzbado Factory of Enusa Group has always upheld a strong commitment with Radiological Protection and environmental respect and protection. Consequently, the evolution of dose shows a downward trend over the years. Although production has been increased gradually, the average doses to workers have stayed below 1 mSv. In order to identify and prevent the potential environmental impacts of its industrial activity and minimize its impact on the surroundings, the facility develops and environmental management system according to UNE-EN-ISO 14001 since 1999. (Author)

Quarterly Environmental Radiological Survey Summary Third Quarter 1998, 100, 200, 300, and 600 Areas; TOPICAL

International Nuclear Information System (INIS)

MCKINNEY, S.M.

1998-01-01

This report provides a summary of the radiological surveys performed in support of near-facility environmental monitoring at the Hanford Site. The Third Quarter 1998 survey results and the status of actions required are summarized: (1) All of the eighty-five environmental radiological surveys scheduled during July, August and September were performed as planned. Fifty-one of the surveys were conducted at Project Hanford Management Contractors (PHMC) sites and thirty-four at Environmental Restoration Contractor (ERC) sites. Contamination above background levels was found at seventeen of the PHMC waste sites and two of the ERC waste sites. Contamination levels as high and gt;1,000,000 disintegrations per minute (dpm) per 100 cm(sup 2) were reported. Of these contaminated surveys nine were in Underground Radioactive Material (URM) areas, three were in unposted areas and seven were in contamination areas. The contamination found within four of the URM and three of the CA areas was immediately cleaned up and no further action was required. The remaining five URM and two unposted sites were posted and along with the five CA sites will require remediation. Radiological Problem Reports (RPR's) were issued and the sites were turned over to the landlord for further action as required. (2) During the second quarter of 1998, 1.2 hectares (3.0 acres) were stabilized and radiologically down posted from Contamination Area (CA)/Soil Contamination (SC) to URM. (3) Four hectares (10 acres) located south and west of B-Plant were posted as a radiological buffer area as a result of a contamination spread. This off-normal occurrence is currently being investigated. (4) Four Surveillance Compliance Inspection Reports (SCIRs) remained open and had not been resolved. Tank Farms Operations has responsibility for the unresolved SCIRs

Environmental impact assessment for energy pathways: an integrated methodology

International Nuclear Information System (INIS)

Sommereux-Blanc, Isabelle

2010-01-01

This document presents the synthesis of my research work contributing to the development of an integrated methodology of environmental impact assessment for energy pathways. In the context of world globalization, environmental impact assessments issues are highly linked with the following questioning: Which environmental impacts? for which demand? at which location? at which temporal scale? My work is built upon the definition of a conceptual framework able to handle these issues and upon its progressive implementation. The integration of the spatial and temporal issues within the methodology are key elements. Fundamental cornerstones of this framework are presented along the DPSIR concept (Driving forces, Pressures, State, Impacts, Responses). They cover a comprehensive analysis of the limits and the relevance of life cycle analysis and the development of a geo-spatialized environmental performance approach for an electrical production pathway. Perspectives linked with the development of this integrated methodology are detailed for energy pathways. (author)

Monitoring activities review of the Radiological Environmental Surveillance Program

International Nuclear Information System (INIS)

Ritter, P.D.

1992-03-01

The 1992 Monitoring Activities Review (MAR) is directed at the Radiological Environment Surveillance Program (RESP) activities at the Radioactive Waste Management Complex (RWMC) of Idaho Engineering Laboratory (INEL). MAR panelists studied RESP documents and discussed their concerns with Environmental Monitoring Unit (EMU) staff and other panel members. These concerns were subsequently consolidated into a collection of recommendations with supporting discussions. Recommendations focus on specific monitoring activities, as well as the overall program. The MAR report also contains pertinent comments that should not require further action

Quarterly environmental radiological survey summary - first quarter 1997 100, 200, 300, and 600 areas

International Nuclear Information System (INIS)

Mckinney, S.M.

1997-01-01

This report provides a summary of the radiological surveys performed in support of near-facility environmental monitoring at the Hanford Site. The First Quarter 1997 survey results and the status of actions required are summarized below: (1) All of the routine environmental radiological surveys scheduled during January, February, and March 1997, were performed as planned. (2) One hundred four environmental radiological surveys were performed during the first quarter 1997, twenty-nine at the active waste sites and seventy-five at the inactive waste sites. Contamination above background levels was found at eight of the active waste sites and seven of the inactive waste sites. Contamination levels as high as >1,000,000 disintegrations per minute (dpm) were reported. Of these contaminated surveys twelve were in Underground Radioactive Material (URM) areas and three were in contamination areas. The contamination found within ten of the URM areas was immediately cleaned up and no further action was required. In the remaining five sites the areas were posted and will require decontamination. Radiological Problem Reports (RPR's) were issued and the sites were turned over to the landlord for further action if required. (3) During the first quarter of 1997, 5.6 hectares (13.8 acres) were stabilized and radiologically down posted from Contamination Area (CA)/Soil Contamination (SC) to URM. (4) During the first quarter of 1997, the size of 216-A-25 Gable Mountain Pond was increased from 30.4 to 34.5 hectares (75.0 to 85.2 acres). This increase in size was due to the correction of the original boundary area by using the advanced technology of a global positioning system (GPS). An area, 1.6 hectares (4.0 acres), east of and adjacent to the 241-S/SX/SY tank farm complex was posted as a contamination/soil contamination area. (5) Five open Surveillance Compliance Inspection Reports (SCIRs) had not been resolved

Environmental and ground-water surveillance at Hanford

Energy Technology Data Exchange (ETDEWEB)

Dirkes, R.L.; Luttrell, S.P.

1995-06-01

Environmental and ground-water surveillance of the Hanford Site and surrounding region is conducted to demonstrate compliance with environmental regulations, confirm adherence to DOE environmental protection policies, support DOE environmental management decisions, and provide information to the public. Environmental surveillance encompasses sampling and analyzing for potential radiological and nonradiological chemical contaminants on and off the Hanford Site. Emphasis is placed on surveillance of exposure pathways and chemical constituents that pose the greatest risk to human health and the environment.

Environmental and ground-water surveillance at Hanford

International Nuclear Information System (INIS)

Dirkes, R.L.; Luttrell, S.P.

1995-01-01

Environmental and ground-water surveillance of the Hanford Site and surrounding region is conducted to demonstrate compliance with environmental regulations, confirm adherence to DOE environmental protection policies, support DOE environmental management decisions, and provide information to the public. Environmental surveillance encompasses sampling and analyzing for potential radiological and nonradiological chemical contaminants on and off the Hanford Site. Emphasis is placed on surveillance of exposure pathways and chemical constituents that pose the greatest risk to human health and the environment

The Clinician-Educator Pathway in Radiology: An Analysis of Institutional Promotion Criteria.

Science.gov (United States)

Jhala, Khushboo; Kim, Jisoo; Chetlen, Alison; Nickerson, Joshua P; Lewis, Petra J

2017-12-01

To provide radiology departmental promotional committees and vice chairs of education with a more global perspective on the types of academic activity valued by institutions to aid in their faculty mentoring and standardizing of the Clinician-Educator (ClinEd) pathway. Ninety-two research schools were ranked into three tiers. Ranking was correlated with the presence of a ClinEd track. Thirty promotion documents (ten from each tier) were analyzed to identify common criteria. Differences in guidelines between tiers were assessed by the frequency distribution of criteria. Tier 1 had a significantly greater proportion of schools with a ClinEd track than tier 2 (73% versus 44%, p < 0.05). Thirty-nine criteria were identified and organized into four categories teaching (13), scholarship (12), service/clinical excellence (7), and research (7). The top five included meeting presentations, trainee evaluations, leadership in committees, development of teaching methodologies and materials, and publication of book chapters. First and second tier schools were most similar in frequency distribution. The criteria for the ClinEd promotion track still vary across institutions, though many commonalities exist. A handful of innovative criteria reflect the changing structure of modern health care systems, such as incorporation of online teaching modules and quality improvement efforts. As health care changes, guidelines and incentive structures for faculty should change as well. The information gathered may provide promotion committees with a more global perspective on the types of academic activity valued by modern-day institutions to aid in the national standardization of this pathway and to assist in faculty mentoring. Copyright © 2017 American College of Radiology. Published by Elsevier Inc. All rights reserved.

Upgrading environmental radiation data: health physics society committee report HPSR-1 (1980)

International Nuclear Information System (INIS)

1980-08-01

This report is a collection of nine individual Health Physics Society subcommittee reports on different aspects of environmental radiation data associated with nuclear power plants. The subcommittee reports include: Environmental Radiation Monitoring Objectives, Definition of Critical Pathways and Radionuclides for Population Radiation Exposure at Nuclear Power Stations, Propagation of Uncertainties in Environmental Pathway Dose Models, Detection of Changes in Environmental Levels Due to Nuclear Power Plants, Quality Assurance for Environmental Monitoring Programs, Reporting of Environmental Radiation Measurements Data, Statistical Methods for Environmental Radiation Data Interpretation, Effective Communication with the Public, Environmental Radiological Surveillance-Mechanisms for Information Exchange

Management of spent oxide fuel from thermal reactors: the environmental and radiological effects of alternative approaches

International Nuclear Information System (INIS)

Martin, A.; Fry, T.M.; Edmunds, J.

1983-07-01

The report presents the results of a study of the environmental and radiological effects of alternative approaches to the management of spent oxide fuel from the UK nuclear power programme. The two main alternatives are extended storage of the fuel, pending decisions on fissile material recycle, and reprocessing of the fuel commencing in the early 1990s. A review is made of experience in spent fuel storage, of the technical issues in long-term storage and of the possible needs of the UK nuclear programme. The main environmental and radiological effects of reprocessing considered in the study are the generation of radioactive wastes, the release of radioactivity in effluents with the resulting radiation exposure of the public, and occupational radiation exposure. The influence of the delay between reprocessing and fabrication of mixed oxide fuel on the environmental and radiological effects of plutonium recycle is investigated and it is shown that the effects would be minimised if reprocessing were delayed until there was a requirement for recycle. Strategies for the management of heavy elements other than plutonium are discussed and results are presented illustrating aspects of actinide management. (author)

Uncertainties in environmental radiological assessment models and their implications

International Nuclear Information System (INIS)

Hoffman, F.O.; Miller, C.W.

1983-01-01

Environmental radiological assessments rely heavily on the use of mathematical models. The predictions of these models are inherently uncertain because these models are inexact representations of real systems. The major sources of this uncertainty are related to biases in model formulation and parameter estimation. The best approach for estimating the actual extent of over- or underprediction is model validation, a procedure that requires testing over the range of the intended realm of model application. Other approaches discussed are the use of screening procedures, sensitivity and stochastic analyses, and model comparison. The magnitude of uncertainty in model predictions is a function of the questions asked of the model and the specific radionuclides and exposure pathways of dominant importance. Estimates are made of the relative magnitude of uncertainty for situations requiring predictions of individual and collective risks for both chronic and acute releases of radionuclides. It is concluded that models developed as research tools should be distinguished from models developed for assessment applications. Furthermore, increased model complexity does not necessarily guarantee increased accuracy. To improve the realism of assessment modeling, stochastic procedures are recommended that translate uncertain parameter estimates into a distribution of predicted values. These procedures also permit the importance of model parameters to be ranked according to their relative contribution to the overall predicted uncertainty. Although confidence in model predictions can be improved through site-specific parameter estimation and increased model validation, risk factors and internal dosimetry models will probably remain important contributors to the amount of uncertainty that is irreducible

Quarterly environmental radiological survey summary: Third quarter 1994--100, 200, 300, and 600 Areas

International Nuclear Information System (INIS)

McKinney, S.M.

1994-11-01

This report provides a summary of the radiological surveys performed on waste disposal sites located at the Hanford Site. The Third Quarter 1994 survey results and the status of actions required from current and past reports and are summarized below: (1) All the routine environmental radiological surveys scheduled during July, August, and September 1994 were completed except for the D Island vent riser area. The surveys for the 200-W railways, spurs, and sidings were completed during this period after being delayed by equipment problems during the second quarter. (2) No Compliance Assessment Reports (CARs) were issued for sites found out of compliance with standards identified in WHC-CM-7-5, Environmental Compliance. (3) Two Surveillance Compliance/Inspection Reports (SCIRs) were closed during the Third Quarter of 1994. (4) Eleven open SCIRs had not been resolved

Program of radiological monitoring environmental a nuclear facility in latency

International Nuclear Information System (INIS)

Blas, A. de; Riego, A.; Batalla, E.; Tapia, C.; Garcia, R.; Sanchez, J.; Toral, J.

2013-01-01

This paper presents the Radiological Environmental Monitoring program of the Vandellos I nuclear power plant in the latency period. This facility was dismantled to level 2, as defined by the International Atomic Energy Agency. The program is an adaptation of the implanted one during the dismantling, taking into account the isotopes that may be present, as well as the main transfer routes. Along with the description of the program the results obtained in the latent period from 2005 until 2012 are presented.

Radiological and Environmental Research Division annual report, July 1979-June 1980. [Lead abstract

Energy Technology Data Exchange (ETDEWEB)

Rowland, R.E.; Stehney, A.F.

1981-05-01

Separate abstracts were prepared for 19 of the 33 papers presented by the Center for Human Radiobiology for the Radiological and Environmental Research Division Annual Report. The 14 items not included are abstracts only and deal with the mechanisms and dosimetry for induction of malignancies by radium. (KRM)

Guide for: environmental radiological surveillance at US Department of Energy installations

International Nuclear Information System (INIS)

Corley, J.P.; Denham, D.H.; Jaquish, R.E.; Michels, D.E.; Olsen, A.R.; Waite, D.A.

1981-07-01

This second edition of the Guide, originally published in 1977, is presented as an interim revision and does not contain major changes in content. The original objectives and scope of the Guide have not changed. The Guide is intended to: provide recommended methods, procedures, and performance criteria to bring greater comparability to DOE environmental monitoring and reporting systems; provide DOE management, particularly the Headquarters' Operational and Environmental Safety Division (OESD) and field offices, with a broad review of accepted radiological surveillance practices for use in the evaluation of environmental surveillance programs at DOE facilities; and delineate the capabilities and limitations of the various environmental monitoring systems for radioactivity currently used at DOE sites, including technical areas where there is either an inadequate basis for procedural selection or where further development work may be warranted. The document is intended as a guide, not a manual of detailed mandatory procedure

Radiological interpretation: The 'step-child' in radiology

International Nuclear Information System (INIS)

Heilmann, H.P.

1981-01-01

Radiology has a highly developed technique, an extensive scientific literature and is excellent for acquiring information; one must contrast with this the difficulties in interpreting the information. In an attempt to find the reason for this, the process of radiological interpretation has been scrutinised. Critical consideration has been given to errors in the interpretation of the findings and to problems arising from the use of the available data. An attempt is made, with the help of diagrams, to determine a pathway for further development of information handling in X-ray diagnosis. (orig.) [de

Quarterly environmental radiological survey summary: Second Quarter 1995 100, 200, 300, and 600 Areas

International Nuclear Information System (INIS)

McKinney, S.M.

1995-01-01

This report provides a summary of the radiological surveys performed in support of the operational environmental monitoring program at the Hanford Site. The Second Quarter 1995 survey results and the status of actions required from current and past reports are summarized

Quarterly environmental radiological survey summary. Fourth quarter, 1995 100, 200, 300, and 600 Areas

International Nuclear Information System (INIS)

McKinney, S.M.; Markes, B.M.

1996-01-01

This report provides a summary of the radiological surveys performed in support of the operational environmental monitoring program at the Hanford Site. The Fourth Quarter 1995 survey results and the status of actions required from current and past reports are described

Environmental radiological protection of Bariloche Atomic Center

International Nuclear Information System (INIS)

Andres, Pablo A.; Levanon, Izhar S.

2013-01-01

This plan of monitoring radiological environmental routine fits on environmental policy of CNEA, satisfying national and international recommendations for licensed facilities. Sampling matrices are related to direct routes of exposure: air and water (river, lake, sediments, drinking water). Soil samples are also analyzed for having integrated matrices. They are considered as minimum three points of measurement: a white point (water or winds up), a point of maximum (water or winds down) and a point corresponding to the location of the individual representative or a point of public interest. Measurements in air estimate KERMA rate with thermoluminescent dosimeters, bi-monthly, and concentrations of particulate material and aerosols. For water samples (monthly), soil and sediments (quarterly), radionuclides that have download limits are analyzed, according to its importance in the dosages produced in the representative individual. In these cases artificial radionuclides using gamma spectrometry, beta total and Sr-90 by radiochemical techniques if the value of total screening (1 Bq/L) is exceeded. Foods are not included because no possible matrices were detected, either by their distance. by located not predominant wind direction. They are however still looking for milk producers that fulfills the minimum requirements.The data collected are compared with environmental baselines to set trends that might point to future significant changes in the environment during the life of the facilities. So far it was not observed significant differences with respect to baseline values

Radiological safety methodology in radioactive tracer applications for hydrodynamics and environmental studies

International Nuclear Information System (INIS)

Suarez, R.; Badano, A.; Dellepere, A.; Artucio, G.; Bertolotti, A.

1995-01-01

The use of radioactive tracer techniques as control sewage disposal contamination in Montevideo Estuarine and Carrasco beach has been studied for the Nuclear Technology National Direction. Hydrodynamic models simulation has been introduced as work methodology. As well as radiological safety and radioactive material applications in the environmental studies has been evaluated mainly in the conclusions and recommendations in this report. maps

Preliminary radiological assessments of near-surface low-level radioactive waste repositories

International Nuclear Information System (INIS)

Sumerling, T.J.; Nancarrow, D.J.

1988-08-01

This report summarises preliminary assessments of post-closure radiological impact of LLW repositories at four sites previously under investigation by UK Nirex Ltd. The objectives of the assessments were: to demonstrate a methodology for site specific assessments, to identify important information requirements for detailed assessments; to identify methodological and research requirements. Doses and risks due to groundwater pathways, human intrusion, gaseous release and natural environmental change are estimated. (author)

Hazardous radiological waste-dental and environmental perspective

International Nuclear Information System (INIS)

Tripathi, Anurag

2014-01-01

Dental radiology is concerned with maxillo-facial radiological diagnostic procedure. It is meant for patient welfare and to generate diagnostically useful information, which can be utilized for patient welfare. If injudiciously used, it can become a source of harmful effluents and solid waste, which may pose risk to health and environment. Professionals of dental radiology should be aware about their responsibility to dispose such waste in the rightful manner to fulfil their medical pledge and ethics of doing no harm. (author)

Sizewell nuclear power station: investigation of radiation exposure pathways from liquid effluents. Local habits survey 1981

International Nuclear Information System (INIS)

Leonard, D.R.P.; Smith, B.D.

1982-01-01

A habits and consumption survey to review radiation exposure pathways due to liquid effluents released from the CEGB Sizewell site is described. It is relevant to both the Sizewell A and proposed Sizewell B nuclear power stations. The main objectives are to provide input data to a radiological assessment by means of identifying critical groups and to provide data for guidance in a review of environmental monitoring programmes. The way in which data for the different pathways should be combined in order to aid the subsequent radiological assessment is discussed. Recommendations are made for adjustments to the present monitoring programmes. (U.K.)

Radiological health review of the final environmental impact statement. Waste Isolation Pilot Plant. Volumes 1 and 2

International Nuclear Information System (INIS)

1981-01-01

Pursuant to the requirements of the National Environmental Policy Act of 1969, the Department of Energy has provided in the Final Environmental Impact Statement (FEIS) a comprehensive review of the potential radiological impact of the proposed Waste Isolation Pilot Plant, referred to in the FEIS as, the authorized alternative. The EEG has reviewed this document to determine (a) the changes made in comparison with the Draft Environmental Impact Statement (DEIS); (b) the adequacy of the DOE's evaluation of the potential radiological impact; (c) the thoroughness of the DOE's response to the comments of the EEG on the DEIS; and (d) other issues which should be addressed by DOE more fully prior to beginning construction of the WIPP. Based on our review of the FEIS, the Department of Energy has incorporated and addressed the majority of the concerns, questions and recommendations that the EEG provided to them in our August 1979 review of the Draft Environmental Impact Statement on WIPP and the FEIS provides a generally satisfactory evaluation of the potential radiological impact. There are, however, a number of areas that have yet to be adequately treated by DOE and should be acted upon and resolved prior to beginning construction of the WIPP. The more important issues are included and are discussed in more detail in our December 8, 1980 and January 15, 1981 comments on the FEIS

Radiological environmental risk associated with different water management systems in amang processing in Malaysia

International Nuclear Information System (INIS)

Ismail, B.; Yasir, M.S.; Redzuwan, Y.; Amran, A.M.

2003-01-01

The processing of amang (tin-tailing) for its valuable minerals have shown that it technologically enhanced naturally occurring radioactive materials, and has a potential of impacting the environment. Large volume of water is used to extract these valuable minerals from amang. Three types of water management systems are used by amang plants, i.e. Open Water System (OWS), Close Water System Man-made (CWS mm) and Close Water System Natural (CWSn). A study was carried out to determine the radiological environmental risk associated with these different water management systems in amang processing in Malaysia. The parameters studied were pH of water, Water Quality Indices, and uranium ad thorium concentrations in water and sediments. Three different sampling locations were selected for each water management system, i.e. the source, the receiver and related reference water bodies. Results obtained showed that amang reduces the pH and contaminates the water. However, OWS appears have the least radiological environmental impact. On the contrary both CWS (man-made and natural) pose a potential environmental risk if great care are not given to the treatment of accumulated sediment and contaminated water before discharge into the environment

Models and parameters for environmental radiological assessments

International Nuclear Information System (INIS)

Miller, C.W.

1983-01-01

This article reviews the forthcoming book Models and Parameters for Environmental Radiological Assessments, which presents a unified compilation of models and parameters for assessing the impact on man of radioactive discharges, both routine and accidental, into the environment. Models presented in this book include those developed for the prediction of atmospheric and hydrologic transport and deposition, for terrestrial and aquatic food-chain bioaccumulation, and for internal and external dosimetry. Summaries are presented for each of the transport and dosimetry areas previously for each of the transport and dosimetry areas previously mentioned, and details are available in the literature cited. A chapter of example problems illustrates many of the methodologies presented throughout the text. Models and parameters presented are based on the results of extensive literature reviews and evaluations performed primarily by the staff of the Health and Safety Research Division of Oak Ridge National Laboratory

Evaluation of environmental change and its effects on the radiological performance of a hypothetical shallow engineered disposal facility at Elstow, Bedfordshire

International Nuclear Information System (INIS)

1988-03-01

The results of a project designed to evaluate aspects of a hypothetical facility for disposal of radioactive wastes at Elstow, Bedfordshire, are described. The project included modelling of environmental change using the TIME2 code, groundwater flow modelling, biosphere modelling and risk analysis using the SYVAC A/C code. The aims of the work were to demonstrate use of TIME2, investigate the evolution of the facility's environment and to evaluate the influence of environmental change on estimates of radiological risk. Risk analysis of several time-independent environmental system states, using data obtained from the other tasks, indicated that environmental changes significantly influence estimates of radiological risk. (author)

National automatic network of environmental radiological monitoring (RENAMORA); Red Nacional automatica de monitoreo radiologico ambiental (RENAMORA)

Energy Technology Data Exchange (ETDEWEB)

Gonzalez M, J.L.; Sanchez H, L. [CNSNS, Dr. Barragan 779, Col. Narvarte, 03020 Mexico D.F. (Mexico)]. e-mail: jlgonzalez@cnsns.gob.mx

2003-07-01

Inside the programs of Environmental Radiological Surveillance that it carries out the National Commission of Nuclear Security and Safeguards (CNSNS), it develops an National Automatic Network of Environmental Radiological Monitoring (RENAMORA), where it is carried out a registration of speed of environmental dose in continuous and simultaneous forms with the same moment of the measurement. This net allows to account with the meticulous and opportune information that will help to characterize, in dynamics form, the radiological conditions of diverse geographical zones of the country, including the sites that by normative require bigger surveillance, like its are the Laguna Verde Nuclear power station (CNLV), the Nuclear Center of Mexico (ININ) and the Radioactive waste storage center (CADER). This net is in its first development stage; three points inside the state of Veracruz, in the surroundings of the CNLV, already its are operating; the obtained data of rapidity of environmental dose are being stored in a database inside a primary data center located in the facilities of the CNSNS in Mexico city and its will be analyzed according to the project advances. At the moment, its are installing the first ten teams corresponding to the first phase of the RENAMORA (three stages); its are carried out operation tests, transmission, reception and administration of data. The obtained data will be interpreted, analyzed and inter compared to evaluate the risk levels to that it would be hold the population and to determine thresholds that allow to integrate the alarm systems that its had considered for emergency situations. (Author)

2002 WIPP Environmental Monitoring Plan

Energy Technology Data Exchange (ETDEWEB)

Washington TRU Solutions LLC

2002-09-30

DOE Order 5400.1, General Environmental Protection Program, requires each DOE | facility to prepare an environmental management plan (EMP). This document is | prepared for WIPP in accordance with the guidance contained in DOE Order 5400.1; DOE Order 5400.5, Radiation Protection of the Public and Environment; applicable sections of Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance (DOE/EH-0173T; DOE, 1991); and the Title 10 Code of Federal Regulations (CFR) Part 834, ''Radiation Protection of the Public and Environment'' (draft). Many sections of DOE Order 5400.1 have been replaced by DOE Order 231.1, which is the driver for the annual Site Environmental Report (SER) and the guidance source for preparing many environmental program documents. The WIPP Project is operated by Westinghouse TRU Solutions (WTS) for the DOE. This plan defines the extent and scope of WIPP's effluent and environmental | monitoring programs during the facility's operational life and also discusses WIPP's quality assurance/quality control (QA/QC) program as it relates to environmental monitoring. In addition, this plan provides a comprehensive description of environmental activities at WIPP including: A summary of environmental programs, including the status of environmental monitoring activities A description of the WIPP Project and its mission A description of the local environment, including demographics An overview of the methodology used to assess radiological consequences to the public, including brief discussions of potential exposure pathways, routine and accidental releases, and their consequences Responses to the requirements described in the Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance.

Environmental and emergency response capabilities of Los Alamos Scientific Laboratory's radiological air sampling program

International Nuclear Information System (INIS)

Gunderson, T.C.

1980-05-01

Environmental and emergency response radiological air sampling capabilities of the Environmental Surveillance Group at Los Alamos Scientific Laboratory are described. The air sampling program provides a supplementary check on the adequacy of containment and effluent controls, determines compliance with applicable protection guides and standards, and assesses potential environmental impacts on site environs. It also allows evaluation of potential individual and total population doses from airborne radionuclides that may be inhaled or serve as a source of external radiation. The environmental program is sufficient in scope to detect fluctuations and long-term trends in atmospheric levels of radioactivity originating onsite. The emergency response capabilities are designed to respond to both onsite unplanned releases and atmospheric nuclear tests

A study on the environmental aspects of hydrogen pathways in Korea

International Nuclear Information System (INIS)

Lee, Ji-Yong; Yu, Moo-Sang; Cha, Kyoung-Hoon; Lee, Soo-Yeon; Hur, Tak; Lim, Tae Won

2009-01-01

In this study, the environmental aspects of H 2 pathways are analyzed according to plausible H 2 production methods, production capacity, and distribution options in Korea, using life cycle assessment (LCA) methodology. The target H 2 pathways analyzed are H 2 via naphtha steam reforming (Naphtha SR), H 2 via natural gas steam reforming (NG SR), H 2 via liquefied petroleum gas steam reforming (LPG SR), H 2 via water electrolysis with wind power (WE[Wind]), and H 2 via water electrolysis with Korea electricity mix (WE[KEM]). The results are then compared with those of conventional fuels (gasoline, diesel, and LPG) to identify which H 2 pathway has less environmental impact than the conventional fuels. Global warming (GW) impact, fossil fuel consumption (FFC) and regulated air emissions are studied to examine the environmental aspects of each fuel pathway. Given that H 2 technologies and infrastructures have yet to be fully commercialized, the environmental aspects of each pathway are analyzed in both their present status and a future scenario in 2015. LCA results show that WE[Wind] is superior regarding global warming potential (GWP), FFC and regulated air emissions. When gasoline is replaced with H 2 from WE[Wind], 99.8% and 99.9% of GWP and FFC can be reduced, respectively. Among the H 2 pathways based on fossil fuels, Naphtha SR[C] has the lowest values of GWP since the CO 2 capture equipment is attached to it. On the other hand, Naphtha SR[S] which is the station-type H 2 pathway does not have the CO 2 capture equipment. Naphtha SR[C] can reduce CO 2 emissions by 23.60 tons compared to gasoline over the entire life cycle of a vehicle. At present, Naphtha SR[C] appears to be environmentally efficient as H 2 conversion and infrastructure technologies have already been commercialized and are suitably developed in Korea. In 2015, however, among the H 2 pathways based on fossil fuels LPG SR[S] is expected to be the best pathway in terms of FFC and regulated air

Involvement of local stakeholders in the development of new information schemes for the displaying of environmental radiological monitoring results

International Nuclear Information System (INIS)

Rollinger, Francoise; Lebeau, Audrey; Petitfrere, Michael; Eimer, Michel; Ganay, Claude de; Gadbois, Serge; Leprieur, Fabrice; Vaillant, Ludovic

2008-01-01

process has allowed identifying the local expectations regarding the radiological quality of their environment. Identified key questions deal with the evolution with time of radionuclides concentration in the Loire river (mainly 3 H, 14 C and α-emitters), the issue of radionuclides accumulation in sediments, radionuclides pathways from the environment to human and the evolution of the environmental monitoring strategy. Such a project is also an opportunity for developing a scientific culture among local population representatives, which is needed to understand the evolution of radioactivity in the environment, its causes and consequences. A first report bringing together all the measurements made in the Loire Valley was produced by IRSN. A second report, prepared by LLC representatives and IRSN with the support of the facilitators, detail and explain the selected measurements. This presentation will detail the objectives, methodology and results of this project after having presented the Loire Valley context. (author)

Rancho Seco liquid effluent pathway aquatic and terrestrial dietary survey report

International Nuclear Information System (INIS)

Eagle, R.J.; Wong, K.M.; Noshkin, V.E.

1984-01-01

This report is a detailed summary of a survey conducted to identify all environmental pathways that may lead to any potential radiological dose to individuals utilizing aquatic and terrestrial components possibly contaminated with radionuclides contained in the liquid effluents that have been routinely discharged since 1980 to Clay Creek from the Rancho Seco Nuclear Generating Station. All land users and identified residents who obtain food from the creeks or use the creek water for irrigation or recreation were interviewed. Site specific usage parameters for the consumption of different food products and for direct exposure to individuals at downstream locations were identified and are discussed in this report. These usage parameters will be used with appropriate radionuclide concentration data to estimate radiological dose to man from the identified liquid effluent pathways

Secondary electron interactions in materials with environmental and radiological interest

International Nuclear Information System (INIS)

Garcia, G.; Blanco, F.; Pablos, J.L. de; Perez, J.M.; Williart, A.

2003-01-01

Important environmental and radiological applications require energy deposition models including the interactions between secondary electrons and the atoms or molecules of the medium. In this work we propose a method to obtain reliable cross-section data to be used in these models by combining total and ionization cross-section measurements with simple calculations of the differential and integral elastic cross-sections. The energy loss spectra obtained in this experiment have been also used to drive stopping power of the considered materials for electrons. Some examples of results for atomic (Xe) and molecular (CF 4 ) targets are presented and discussed in this paper. (author)

Emergency radiological monitoring and analysis United States Federal Radiological Monitoring and Assessment Center

International Nuclear Information System (INIS)

Thome, D.J.

1994-01-01

The United States Federal Radiological Emergency Response Plan (FRERP) provides the framework for integrating the various Federal agencies responding to a major radiological emergency. Following a major radiological incident the FRERP authorizes the creation of the Federal Radiological Monitoring and Assessment Center (FRMAC). The FRMAC is established to coordinate all Federal agencies involved in the monitoring and assessment of the off-site radiological conditions in support of the impacted states and the Lead Federal Agency (LFA). Within the FRMAC, the Monitoring and Analysis Division is responsible for coordinating all FRMAC assets involved in conducting a comprehensive program of environmental monitoring, sampling, radioanalysis and quality assurance. This program includes: (1) Aerial Radiological Monitoring - Fixed Wing and Helicopter, (2) Field Monitoring and Sampling, (3) Radioanalysis - Mobile and Fixed Laboratories, (4) Radiation Detection Instrumentation - Calibration and Maintenance, (5) Environmental Dosimetry, and (6) An integrated program of Quality Assurance. To assure consistency, completeness and the quality of the data produced, a methodology and procedures handbook is being developed. This paper discusses the structure, assets and operations of FRMAC monitoring and analysis and the content and preparation of this handbook

Nanoscopic designs of radiological protection in environmental scale for the Fukushima nuclear accident: Strategy by dispersion, dissolution, and filtration

International Nuclear Information System (INIS)

Woo, Tae Ho

2016-01-01

Highlights: • New kind of radiological protection concept is introduced. • The shielding concept is accompanied with the water spray system. • The solubility of radioactive material could be used for protection. • Practical method is suggested. • The system is variable by the random number quantities. - Abstract: The environmental defense system in the nuclear power plants (NPPs) is investigated in the aspect of the environmental scale incorporated with atmospheric and marine sectors. The object is to find the radiological protection protocol in the environmental scale which is different from the conventional three kinds of radiological protection principles. Conventional laboratory based principles are not applicable in the mass failure accident such as the case of Fukushima disaster. This newly introduced protocol has many useful applications for the nature treatment oriented methods where the atmospheric protection of dispersion and dissolution is performed first and the filtration of seawater would follow. The maximum and minimum values in fan velocity are about 7.5 m/s and 5.3 m/s respectively. For the spray system, the mole fractions by the water spray are shown where maximum and minimum values are 6.57 × 10 −17 and 8.84 × 10 −19 moles respectively. The maximum and minimum values of discharged values in filtration are 99.4 and 1.3 square velocity (m/s), respectively. The total and general radiological protection concept is suggested in the nanoscopic molecular scale performance.

Trends in radiological and environmental protection at high energy accelerator laboratories

International Nuclear Information System (INIS)

Perry, D.R.; Shaw, K.B.; Stapleton, G.B.; Thomas, R.H.

1991-03-01

The serious study of high-energy particle accelerator radiological protection began in the early 1950s and has continued since then. This paper treats the subject in seven stages, and begins by briefly reviewing the work done until the 80s, which comprises the first five stages. These are, observation of high radiation levels, shielding studies, dosimetry, induced activity and the environmental effects. The sixth stage, control by legislation and regulation, is discussed in detail. Over the past twenty years there have been significant additions to radiological protection standards: from a scientifically based estimate of risk to a social desire to reduce exposure to levels determined only by the ''best practical means (BPM)'' or as it is currently understood in the United States of America ''best available technology (BAT)''. The implications of this trend are explored, and the success with which changing standards have been followed is studied with the aid of data derived from personnel doses. The last stage is the decommissioning or disposal of high energy accelerators. (author)

Environmental standard review plan for ES Section 7.1.1. Environmental impacts of postulated accidents involving releases of radioactive materials to groundwater

International Nuclear Information System (INIS)

1985-11-01

Environmental Standard Review Plan (ESRP) 7.1.1 provides guidance to the staff for preparation of environmental assessments of ''Radiological Impacts - Releases to Groundwater,'' an input to the staff's environmental statement which addresses the groundwater pathway consequences from postulated reactor core-melt accidents. The ESRP lists the type of information which should be collected, references that may be useful, and provides a procedure for uniform staff review of applicant analyses. The ESRP is applicable to both Construction Permit and Operating License Stage reviews

Annual radiological environmental monitoring report: Watts Bar Nuclear Plant, 1991

International Nuclear Information System (INIS)

1992-04-01

This report describes the preoperational environmental radiological monitoring program conducted by TVA in the vicinity of the Watts Bar Nuclear Plant (WBN) in 1991. The program includes the collection of samples from the environment and the determination of the concentrations of radioactive materials in the samples. Samples are taken from stations in the general area of the plant and from areas that will not be influenced by plant operations. Material sampled includes air, water, milk, foods, vegetation, soil, fish, sediment, and direct radiation levels. During plant operations, results from stations near the plant will be compared with concentrations from control stations and with preoperational measurements to determine potential impacts to the public. Exposures calculated from environmental samples were contributed by naturally occurring radioactive materials, from materials commonly found in the environment a a result of atmospheric fallout, or from the operation of other nuclear facilities in the area. Since WBN has not operated, there has been no contribution of radioactivity from the plant to the environment

Annual radiological environmental monitoring report: Watts Bar Nuclear Plant, 1992

International Nuclear Information System (INIS)

1993-04-01

This report describes the preoperational environmental radiological monitoring program conducted by TVA in the vicinity of the Watts Bar Nuclear Plant (WBN) in 1992. The program includes the collection of samples from the environment and the determination of the concentrations of radioactive materials in the samples. Samples are taken from stations in the general area of the plant and from areas that will not be influenced by plant operations. Material sampled includes air, water, milk, foods, vegetation, soil, fish, sediment, and direct radiation levels. During plant operations, results from stations near the plant will be compared with concentrations from control stations and with preoperational measurements to determine potential impacts to the public. Exposures calculated from environmental samples were contributed by naturally occurring radioactive materials, from materials commonly found in the environment as a result of atmospheric fallout, or from the operation of other nuclear facilities in the area. Since WBN has not operated, there has been no contribution of radioactivity from the plant to the environment

Environmental income as a pathway out of poverty?

DEFF Research Database (Denmark)

Walelign, Solomon Zena; Nielsen, Martin Reinhardt; Larsen, Helle Overgaard

2017-01-01

environmental resources on average contribute 16 per cent of the total household income, the contribution to asset accumulation is limited. Hence, environmental income does not constitute a pathway out of poverty in Nepal under the current set of regulations and tenure regimes. Asset accumulation was instead......Using unique, environmentally augmented household panel data reflecting households’ annual cash and subsistence income portfolios, we model change over time in the value of four assets – livestock, implements, savings, and jewellery. A seemingly unrelated regression model reveals that although...... associated (both negatively and positively) with agricultural income (particularly as subsistence income), wage and business income. Most environmental income was obtained as subsistence income indicating that the environmental resources that households have access to present little opportunity for cash...

Annual Site Environmental Report

Energy Technology Data Exchange (ETDEWEB)

Holden, Gene

1999-09-23

This report provides information about environmental programs and compliance with environmental regulations in calendar year 1998 (CY98) at the Stanford Linear Accelerator Center (SLAC). The most significant information in this report is summarized in the following sections: (1) Environmental Compliance--Section 2 contains the complete Environmental Compliance information; (2) Environmental Non-Radiological Program--Section 3 contains the complete Environmental Non-Radiological information; and (3) Environmental Radiological Program--Section 4 contains the complete Environmental Radiological information.

Quantifying environmental adaptation of metabolic pathways in metagenomics

DEFF Research Database (Denmark)

Gianoulis, Tara A; Raes, Jeroen; Patel, Prianka V

2009-01-01

of particular pathways and subnetworks reflects the adaptation of microbial communities across environments and habitats-i.e., how network dynamics relates to environmental features. Previous research has treated environments as discrete, somewhat simplified classes (e.g., terrestrial vs. marine), and searched...... multiple, continuously varying factors defining an environment to the extent of particular microbial pathways present in a geographic site. Moreover, rather than looking only at individual correlations (one-to-one), we adapted canonical correlation analysis and related techniques to define an ensemble...

2002 Waste Isolation Pilot Plant Environmental Monitoring Plan

International Nuclear Information System (INIS)

Washington TRU Solutions LLC

2002-01-01

DOE Order 5400.1, General Environmental Protection Program, requires each DOE | facility to prepare an environmental management plan (EMP). This document is | prepared for WIPP in accordance with the guidance contained in DOE Order 5400.1; DOE Order 5400.5, Radiation Protection of the Public and Environment; applicable sections of Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance (DOE/EH-0173T; DOE, 1991); and the Title 10 Code of Federal Regulations (CFR) Part 834, ''Radiation Protection of the Public and Environment'' (draft). Many sections of DOE Order 5400.1 have been replaced by DOE Order 231.1, which is the driver for the annual Site Environmental Report (SER) and the guidance source for preparing many environmental program documents. The WIPP Project is operated by Westinghouse TRU Solutions (WTS) for the DOE. This plan defines the extent and scope of WIPP's effluent and environmental | monitoring programs during the facility's operational life and also discusses WIPP's quality assurance/quality control (QA/QC) program as it relates to environmental monitoring. In addition, this plan provides a comprehensive description of environmental activities at WIPP including: A summary of environmental programs, including the status of environmental monitoring activities A description of the WIPP Project and its mission A description of the local environment, including demographics An overview of the methodology used to assess radiological consequences to the public, including brief discussions of potential exposure pathways, routine and accidental releases, and their consequences Responses to the requirements described in the Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance

Evidence given by the National Radiological Protection Board to the Royal Commission on Environmental Pollution

International Nuclear Information System (INIS)

1976-09-01

In March of 1976 The Royal Commission on Environmental Pollution informed the Board that they had decided to enquire into the organisation for radiological safety in this country, with particular regard to the environmental hazards from radioactivity that might arise from the increasing use of nuclear energy for the generation of electrical power. The Board was invited to submit evidence on any aspects with which it was concerned and, in particular, on its powers and responsibilities and relationships with other bodies; the Board was also asked to discuss the assessment of radiation hazards and the application in practice of the recommendations of the International Commission on Radiological Protection. This is the Board's response. The constitution, functions and responsibilities of the Board are discussed in Chapter 1 as is the involvement of its staff in national and international affairs in the field of radiological protection. Chapter consists of a short statement of the various sources of radiation to which the people of the UK are exposed. The Board does not claim any special experience or expertise in one of the matters referred to in the third area of concern, namely, the criteria used for the siting of nuclear power stations. But in the related field of assessing the environmental consequences of reactor accidents, the Board has been actively involved with the Medical Research Council in their latest review of Emergency Reference Levels - a report on which is shortly to be published. This subject is referred to in Chapter 3 which deals with the methods by which the basic recommendations of the International Commission on Radiological Protection are translated into values that can be applied to particular forms of practice. Chapter 4 discusses the current position of gaseous, liquid and solid wastes arising from nuclear power cycles. It also briefly discusses the way in which this position may change in future and touches on the problems of decommissioning

Annual radiological environmental operating report: Sequoyah Nuclear Plant, 1987

International Nuclear Information System (INIS)

1988-04-01

This report describes the environmental radiological monitoring program conducted by TVA in the vicinity of the Sequoyah Nuclear Plant in 1987. The program includes the collection of samples from the environment and the determination of the concentrations of radioactive materials in the samples. Samples are taken from stations in the general area of the plant and from areas not influenced by plant operations. Station locations are selected after careful consideration of the weather patterns and projected radiation doses to the various areas around the plant. Material sampled includes air, water, milk, foods, vegetation, soil, fish, sediment, and direct radiation levels. Results from stations near the plant are compared with concentrations from control stations and with preoperational measurements to determine potential impacts of plant operations. 2 figs., 2 tabs

Annual radiological environmental monitoring report, Watts Bar Nuclear Plant

International Nuclear Information System (INIS)

1988-05-01

This report describes the preoperational environmental radiological monitoring program conducted by TVA in the vicinity of the Watts Bar Nuclear Plant (WBN) in 1988. The program includes the collection of samples from the environment and the determination of the concentrations of radioactive materials in the samples. Samples are taken from stations in the general area of the plant and from areas that will not be influenced by plant operations. Station locations are selected after careful consideration of the weather patterns and projected radiation doses to the various areas around the plant. Material sampled includes air, water, milk, foods, vegetation, soil, fish, sediment, and direct radiation levels. During plant operations, results from stations near the plant will be compared with concentrations from control stations and with preoperational measurements to determine potential impacts to the public. The exposures calculated from environmental samples were contributed by naturally occurring radioactive materials, from materials commonly found in the environment as a result of atmospheric fallout, or from the operation of other nuclear facilities in the area. Since WBN has not operated, there has been no contribution of radioactivity from the plant to the environment. 4 refs., 2 figs., 1 tab

Development of a statewide hospital plan for radiologic emergencies

International Nuclear Information System (INIS)

Dainiak, Nicholas; Delli Carpini, Domenico; Bohan, Michael; Werdmann, Michael; Wilds, Edward; Barlow, Agnus; Beck, Charles; Cheng, David; Daly, Nancy; Glazer, Peter; Mas, Peter; Nath, Ravinder; Piontek, Gregory; Price, Kenneth; Albanese, Joseph; Roberts, Kenneth; Salner, Andrew L.; Rockwell, Sara

2006-01-01

Although general guidelines have been developed for triage of victims in the field and for hospitals to plan for a radiologic event, specific information for clinicians and administrators is not available for guidance in efficient management of radiation victims during their early encounter in the hospital. A consensus document was developed by staff members of four Connecticut hospitals, two institutions of higher learning, and the State of Connecticut Department of Environmental Protection and Office of Emergency Preparedness, with assistance of the American Society for Therapeutic Radiology and Oncology. The objective was to write a practical manual for clinicians (including radiation oncologists, emergency room physicians, and nursing staff), hospital administrators, radiation safety officers, and other individuals knowledgeable in radiation monitoring that would be useful for evaluation and management of radiation injury. The rationale for and process by which the radiation response plan was developed and implemented in the State of Connecticut are reviewed. Hospital admission pathways are described, based on classification of victims as exposed, contaminated, and/or physically injured. This manual will be of value to those involved in planning the health care response to a radiologic event

Directory of personnel responsible for radiological health programs

International Nuclear Information System (INIS)

1977-01-01

This is a directory of professional personnel who administer the radiological health program activities in state and local governmental agencies. Included in the directory is a listing of each state health officer or the head of the agency responsible for the radiological health program. The name, address, and telephone number of the radiological health personnel are listed, followed by the alternate contact who, in many instances, may be chief of a larger administrative unit of which the radiological health program is a subunit. The address for the program is also included if it differs from the official health department or agency. Generally, the titles of the personnel listed will indicate the administrative status of the radiological health program. The directory also includes a list of key professional personnel in the Bureau of Radiological Health, Radiation Operations Staff, Regional Radiological Health Representatives, Winchester Engineering and Analytical Center, Food and Drug Administration; Office of Radiation Programs, Regional Radiation Representatives, National Environmental Research Center, and Eastern Environmental Radiation Laboratory, Environmental Protection Agency; selected personnel in the U.S. Nuclear Regulatory Commission; and selected personnel in the National Bureau of Standards

Enviromental sampling at remote sites based on radiological screening assessments

International Nuclear Information System (INIS)

Ebinger, M.H.; Hansen, W.R.; Wenz, G.; Oxenberg, T.P.

1996-01-01

Environmental radiation monitoring (ERM) data from remote sites on the White Sands Missile Range, New Mexico, were used to estimate doses to humans and terrestrial mammals from residual radiation deposited during testing of components containing depleted uranium (DU) and thorium (Th). ERM data were used with the DOE code RESRAD and a simple steady-state pathway code to estimate the potential adverse effects from DU and Th to workers in the contaminated zones, to hunters consuming animals from the contaminated zones, and to terrestrial mammals that inhabit the contaminated zones. Assessments of zones contaminated with DU and Th and DU alone were conducted. Radiological doses from Th and DU in soils were largest with a maximum of about 3.5 mrem y -1 in humans and maximum of about 0.1 mrad d -1 in deer. Dose estimates from DU alone in soils were significantly less with a maximum of about 1 mrem y -1 in humans and about 0.04 mrad d -1 in deer. The results of the dose estimates suggest strongly that environmental sampling in these affected areas can be infrequent and still provide adequate assessments of radiological doses to workers, hunters, and terrestrial mammals

Overview of environmental radiological monitoring program of Institute of Radiation Protection And Dosimetry - IRD

Energy Technology Data Exchange (ETDEWEB)

Gomes, Sarah Barreto Oliveira de Christo; Peres, Sueli da Silva, E-mail: suelip@ird.gov.br, E-mail: sarah.barreto1@gmail.com [Instituto de Radioproteção e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil). Div. de Radioproteção

2017-07-01

As a branch of the Brazilian Nuclear Energy Commission (CNEN), the Institute of Radiation Protection and Dosimetry (IRD) performs extensive activities in the fields of radiation protection, metrology, and dosimetry, as well as specific education, onto a wide operational scope that includes the technical support to national regulatory authorities in the licensing process for nationwide nuclear and radioactive facilities. IRD has several laboratories where are performed radiometric and radiochemical analyses and others radioactivity evaluation procedures in different types of samples obtained in the inspection activities, production of radioactivity metrological standards and reference material by National Laboratory of Metrology of Ionizing Radiation (LMNRI), besides others research activities. In this laboratories can be used sealed or unsealed radioactive sources and radiation-producing devices and are classified with radioactive installations in accordance to national regulations. This way, radioactive liquid effluents can be eventually produced and released into the environment in the course of such activities and an effluent monitoring program to control and reduce the releases to environment is carried out. Additionally, IRD maintains the Radioactive Waste Management Program and Environmental Radiological Monitoring Program (ERMP) in accordance to national regulations requirements. The primary focus of ERMP comprises the validation of the dose prognostics for the public members due to effluents discharge and the provision of consistent projections of the radiation levels at the monitoring sites. In this study, a long term ERMP data survey is discussed, spanning the last thirteen years of activities. On the basis of such discussions and prognostics, it could be observed that the radiological environmental radiological impact due to operation of IRD installations is negligible. (author)

Overview of environmental radiological monitoring program of Institute of Radiation Protection And Dosimetry - IRD

International Nuclear Information System (INIS)

Gomes, Sarah Barreto Oliveira de Christo; Peres, Sueli da Silva

2017-01-01

As a branch of the Brazilian Nuclear Energy Commission (CNEN), the Institute of Radiation Protection and Dosimetry (IRD) performs extensive activities in the fields of radiation protection, metrology, and dosimetry, as well as specific education, onto a wide operational scope that includes the technical support to national regulatory authorities in the licensing process for nationwide nuclear and radioactive facilities. IRD has several laboratories where are performed radiometric and radiochemical analyses and others radioactivity evaluation procedures in different types of samples obtained in the inspection activities, production of radioactivity metrological standards and reference material by National Laboratory of Metrology of Ionizing Radiation (LMNRI), besides others research activities. In this laboratories can be used sealed or unsealed radioactive sources and radiation-producing devices and are classified with radioactive installations in accordance to national regulations. This way, radioactive liquid effluents can be eventually produced and released into the environment in the course of such activities and an effluent monitoring program to control and reduce the releases to environment is carried out. Additionally, IRD maintains the Radioactive Waste Management Program and Environmental Radiological Monitoring Program (ERMP) in accordance to national regulations requirements. The primary focus of ERMP comprises the validation of the dose prognostics for the public members due to effluents discharge and the provision of consistent projections of the radiation levels at the monitoring sites. In this study, a long term ERMP data survey is discussed, spanning the last thirteen years of activities. On the basis of such discussions and prognostics, it could be observed that the radiological environmental radiological impact due to operation of IRD installations is negligible. (author)

Objectives, Extent and Organization of Radiological and Environmental Protection in Relation to the Nature and Size of Nuclear Facilities

International Nuclear Information System (INIS)

Kathren, R.L.

1979-01-01

Radiological and environmental protection programs for nuclear facilities have similar goals and objectives, which are basically to protect people and the environment from adverse effects. To be effective, the programs must have organizational independence and a strong commitment from management. In return, the programs should ensure that the facility is operating in full compliance with law and good practice. The scope and elements of radiological environmental protection programs will vary according to facility type and size, with the larger and more complex facilities having a diversity of staff and functions. Examples of good and poor organization charts are given and discussed from the standpoint of program effectiveness along with a discussion of the role of the radiation protection committee. (author)

Potential effects of climatic change on radiological doses from disposal of Canadian nuclear fuel waste

International Nuclear Information System (INIS)

Amiro, B.D.

1997-01-01

The environmental assessment of deep geologic disposal of Canadian nuclear fuel waste considers many processes that could affect radionuclide transport to humans over thousands of years. Climatic change is an important feature that will occur over these long times. Glaciation will likely occur within the next 100,000 years over much of Canada, and its impact on radiological doses has been assessed previously. In the present study, we investigate the potential effect of short- term climatic change, usually associated with global warming caused by increases in atmospheric trace gases. We study the main biosphere transport pathways causing a radiological dose to humans from 129 I, which is the most important radionuclide in disposal of Canadian used nuclear fuel. Irrigation of a garden with contaminated well water is the main pathway and it can be affected by changes in temperature and precipitation. A cold, wet climate decreases the need for irrigation, and this decreases the radiological dose. A drastic climatic change, such as an increase in temperature from 10 to 20 degrees C and decrease in precipitation from 0.3 to 0.2 m during the growing season, is estimated to increase the dose by a factor of four. This is a relatively small change compared to the range of doses that arise from the variability and uncertainty in many of the parameters used in the environmental assessment models. Therefore, it is likely that the results of probabilistic dose assessment models can include the consequences of short-term climatic change. 39 refs., 3 figs

The environmental restoration in the management of radiological accidents with off site consequences

International Nuclear Information System (INIS)

Vazquez, C.; Montero, M.; Moraleda, M.; Diaz, J.; Claver, F.; Valles, O.; Rodriguez, N.; Gutierrez, J.

1998-01-01

Radiological accidents are among the potential cases of environmental contamination that could have consequences on the health of the population. These accidents, associated with an increase in the level of radiological exposure surpassing the natural background, have been investigated in greater depth than other conventional accidents. This investigation has included the evaluation of their probability, magnitude and consequences in order to establish safety norms. Nevertheless, the social perception of this type of risk appears to be disproportionately high. The development of a comprehensible and adequate standardized system for the evaluation of the radiological risk and the applicability of corrective actions to reduce this type of risk at local level, will undoubtedly contribute to increase the public confidence in the advised options for the restoration of environments contaminated with the long lived radionuclides. This system should consider the local specificity of each contaminated place, and take into account the associated unwanted consequences for each option. This paper presents the first results of a system to help the decision makers in the quantitative evaluation of the radiological risk produced by long lived radionuclides Cs 137, Cs 134 and Sr 90 spread over urban, agricultural and semi-natural environments and the applicable options to reduce it. The evaluation of these applicable options is made considering the reduction of dose that can be reached, the monetary costs and the significant associated secondary effects if there are any. All these factors are integrated for a time period depending on the half-life of the contaminants and on their strength and distribution on the scenario when intervention is being planned. (authors)

The Ability of the United States Federal Radiological Monitoring and Assessment Center to Collect and Disseminate Environmental Measurements during Radiological Emergencies

International Nuclear Information System (INIS)

Marianno, Craig; Essex, James

2007-01-01

The Federal Radiological Monitoring and Assessment Center (FRMAC) is the United States response organization for radiological emergencies. The FRMAC is structured as an operations center and employs the combined resources of several federal agencies to respond to any disaster resulting in the release of radioactivity. The mission of the FRMAC is to support state and local authorities in the gathering of environmental data using an array of survey equipment ranging from alpha probes, beta/gamma probes, and high-purity germanium (HPGe) spectroscopy to the gathering of physical samples. Once collected, the data are projected on maps to assist public officials make protective action decisions. In addition to the accumulation of data, it is the legal obligation of the FRMAC to keep archival records of all data points and their actions. During an event, it is conceivable that hundreds to thousands of sample points will be recorded over a relatively short time. It is in the interest of the federal government and public that the information collected be put to the best use as fast as possible. Toward this end, the Remote Sensing Laboratory, working under the direction of the United States Department of Energy's National Nuclear Security Administration, is investigating the use of several technologies that will accelerate data flow from field teams to the FRMAC and, finally, distribution of data to decision makers and the public. Not only can finished data products be viewed through the internet, but the actual collection of data via 'real-time' telemetry can be viewed using this same method. Data from the field will be transferred directly to the FRMAC using the MCPD (multi-path communication device). This base station receives the survey information from the field teams via Bluetooth and instantly investigates the best communication pathway to transfer data to the FRMAC. Possible paths include standalone radio, commercial cellular networks (GPRS and CDMA) and satellite

Environmental and radiological pollution in creeks sediment and water from Duhok, Iraq

International Nuclear Information System (INIS)

Abdullah, K.M.S.

2012-01-01

is 17 people from 10000. The chemical analysis of the surface water samples showed compatibility with radiological results in terms of the solubility of isotopes. The radiological impact due to exposure pathways, as analyzed by RESRAD software and from other results indicated that the environment of the governorate was clean and suitable for living. (author)

ASSET RECOVERY OF HAZARDOUS MATERIALS BENEFICIAL REUSE OF RADIOLOGICALLY ENCUMBERED LEAD STOCKS

International Nuclear Information System (INIS)

Lloyd, E.R.; Meehan, R.W.

2003-01-01

Underutilized and surplus lead stocks and leaded components are a common legacy environmental problem across much of the Department of Energy (DOE) Complex. While seeking to dispose of these items through its Environmental Management Program, DOE operational programs continue to pursue contemporary mission requirements such as managing and/or storing radioactive isotopes that require lead materials for shielding. This paradox was identified in late 1999 when DOE's policies for managing scrap metal were assessed. In January 2000, the Secretary of Energy directed the National Center of Excellence for Materials Recycle (NMR) to develop and implement a comprehensive lead reuse program for all of DOE. Fluor Hanford, contractor for DOE Richland Operations, subsequently contacted NMR to pilot lead reclamation and reuse at the Hanford Site. This relationship resulted in the development of a beneficial reuse pathway for lead reclaimed from spent fuel transport railcars being stored at Hanford. The 1.3 million pounds of lead in the railcars is considered radiologically encumbered due to its prior use. Further, the material was considered a mixed Resource Conservation and Recovery Act (RCRA) low-level radioactive waste that would require expensive storage or macro encapsulation to meet land disposal restrictions prior to burial. Working closely with Flour Hanford and the Office of Air, Water, and Radiation (EH-412), NMR developed a directed reuse pathway for this and other radiologically encumbered lead. When derived supplemental release limits were used, the lead recovered from these railcars became eligible for reuse in shielding products to support DOE and commercial nuclear industry operations. Using this disposition pathway has saved Hanford one third of the cost of disposing of the lead and the cost of acquiring additional lead for nuclear shielding applications. Furthermore, the environmental costs associated with mining and producing new lead for shielding products a

Environmental radiological studies downstream from Rancho Seco Nuclear Power Generating Station

International Nuclear Information System (INIS)

Noshkin, V.E.; Wong, K.M.; Eagle, R.J.; Dawson, J.W.; Brunk, J.L.; Jokela, T.A.

1985-01-01

This report summarizes the information compiled in 1984 while assessing the environmental impact of radionuclides in aquatic releases from the Rancho Seco Nuclear Power Generating Station. Gamma-emitting radionuclides discharged since 1981 are found in many of the dietary components derived from the creeks receiving the effluent wastewater. Some soils and crops are found to contain radionuclides that originate from the contaminated water that was transferred to land during the irrigation season. 134 Cs and 137 Cs are the primary gamma-emitting radionuclides detected in the edible flesh of fish from the creeks. Concentrations in the flesh of fish decreased exponentially with distance from the plant. No significant differences in the 137 Cs activity were found between male and female fish of equal size, but concentrations may vary in fish of different size, with the season and diet. 21% of the total 137 Cs and 134 Cs discharged between 1981 and 1984 is associated with the creek sediments to a distance of 27 km from the plant. Fractions of the missing inventory have been transferred to land during the irrigation season or to downstream regions more distant than 27 km from the plant. The radiocesium content of the sediments in 1984 decreased significantly in a downstream direction, much in the same manner as concentrations decreased in fish. Radioactivity originating from the plant was not above detection limits in any terrestrial food item sampled beyond 6.5 km from the plant. Based on the usage factors provided by individuals interviewed in a 1984 survey, the fish and aquatic-organism ingestion pathway contributed the largest radiological dose to humans utilizing products contaminated with the radionuclides in the liquid wastes discharged from the Rancho Seco Nuclear Power Generating Station in 1984

Annual radiological environmental operating report, Browns Ferry Nuclear Plant, 1988

International Nuclear Information System (INIS)

1989-04-01

This report describes the environmental radiological monitoring program conducted by TVA in the vicinity of Browns Ferry Nuclear Plant in 1988. The program includes the collection of samples from the environment and the determination of the concentrations of radioactive materials in the samples. Samples are taken from stations in the general area of the plant and from areas not influenced by plant operations. Station locations are selected after careful consideration of the weather patterns and projected radiation doses to the various areas around the plant. Material sampled includes air, water, milk, foods, vegetation, soil, fish, sediment, and direct radiation levels. Results from stations near the plant are compared with concentrations from control stations and with preoperational measurements to determine potential impacts of plant operations. The vast majority of the exposures calculated from environmental samples were contributed by naturally occurring radioactive materials or from materials commonly found in the environment as a result of atmospheric nuclear weapons fallout. Small amounts of Co-60 were found in sediment samples downstream from the plant. This activity in stream sediment would result in no measurable increase over background in the dose to the general public. 3 refs., 2 figs., 2 tabs

Radiological Protection Miscellaneous Provisions Act 2014

International Nuclear Information System (INIS)

Irish Legislation

2014-07-01

This Act provides for the dissolution of the Radiological Protection Institute of Ireland and the transfer of all its functions, assets, liabilities and staff to the Environmental Protection Agency, to give effect to the Amendment to the Convention on the Physical Protection of Nuclear Material done at Vienna on 8 July 2005, to amend the Radiological Protection Act 1991, the Environmental Protection Agency Act 1992 and certain other enactments, and to provide for matters connected therewith

Emergency radiological monitoring and analysis: Federal Radiological Monitoring and Assessment Center

International Nuclear Information System (INIS)

Thome, D.J.

1995-01-01

The US Federal Radiological Emergency Response Plan (FRERP) provides the framework for integrating the various Federal agencies responding to a major radiological emergency. The FRERP authorizes the creation of the Federal Radiological Monitoring and Assessment Center (FRMAC), which is established to coordinate all Federal agencies involved in the monitoring and assessment of the off-site radiological conditions in support of the impacted State(s) and the Lead Federal Agency (LFA). Within the FRMAC, the Monitoring and Analysis Division (M ampersand A) is responsible for coordinating all FRMAC assets involved in conducting a comprehensive program of environmental monitoring, sampling, radioanalysis, and quality assurance. To assure consistency, completeness, and the quality of the data produced, a methodology and procedures manual is being developed. This paper discusses the structure, assets, and operations of the FRMAC M ampersand A and the content and preparation of the manual

Statistical data treatment of environmental radiological measurements extracted by the CSN and submitted to a lower limit of detection

International Nuclear Information System (INIS)

Felipe, A.; Martin, M.; Valdes, T.

1992-01-01

The quantification of radiological environmental contamination is usually carried out by mean of sample measurements around the emission points. These data are submitted to the so called Lower Limit of Detection which makes data to be statistically censored. The following topics have been included in our work: (a) Correction of mean values of the radiological contamination levels by the estimation of its distribution. (b) Development of the computer programs to carry out the former correction of estimators. (c) Estimation of the existing correlation among the different types of measurements. (author)

The Emergency Radiological Monitoring and Analysis Division of the United States Federal Radiological Monitoring and Assessment Center

International Nuclear Information System (INIS)

Thome, D.J.

2000-01-01

The U.S. Federal Radiological Emergency Response Plan (FRERP) provides the framework for integrating the various Federal agencies responding to a major radiological emergency. The FRERP authorises the creation of the Federal Radiological Monitoring and Assessment Center (FRMAC), which is established to co-ordinate all Federal agencies involved in the monitoring and assessment of the off-site radiological conditions in support of the impacted States and the Lead Federal Agency (LFA). Within the FRMAC, the Monitoring and Analysis Division is responsible for co-ordinating all FRMAC assets involved in conducting a comprehensive program of environmental monitoring, sampling, radioanalysis, and quality assurance. This program includes: 1. Aerial Radiological Monitoring - Fixed-Wing and Helicopter; 2. Field Monitoring and Sampling; 3. Radioanalysis - Mobile and Fixed Laboratories; 4. Radiation Detection Instrumentation - Calibration and Maintenance; 5. Environmental Dosimetry; 6. Integrated program of Quality Assurance. To assure consistency, completeness, and the quality of the data produced, a methodology and procedures manual is being developed. This paper discusses the structure, assets, and operations of the FRMAC Monitoring and Analysis Division and the content and preparation of the manual. (author)

Radiological impact assessment in Bagjata uranium deposit: a case study

International Nuclear Information System (INIS)

Sarangi, A.K.; Bhowmik, S.C.; Jha, V.N.

2007-01-01

The uranium ore mining facility, in addition to the desirable product, produces wastes in the form of environmental releases or effluents to air, water and soil. The toxicological and other (non-radiological) effects are generally addressed in EIA/EMP studies as per MOEF guidelines. Since the uranium ore is radioactive, it is desirable to conduct a study on radiological effects considering the impacts of radiological releases to the environment. Before undertaking the commercial mining operations at Bagjata uranium deposit in the Singhbhum east district of Jharkhand, pre-operational radiological base line data were generated and a separate study on radiological impact on various environmental matrices was conducted in line with the International Atomic Energy Agency's laid out guidelines. The paper describes the philosophy of such studies and the findings that helped in formulating a separate environmental management plan. (author)

Implementing the new radiological protection criteria into the decision support system for environmental restoration after nuclear accidents, TEMAS

International Nuclear Information System (INIS)

Montero, M.; Vazquez, C.; Moraleda, M.

2003-01-01

Full text: A conceptual decision system implemented as help decision tool that can contribute to the management and rehabilitation of contaminated areas is presented. The first version of the tool was developed in the TEMAS PROJECT. The TEMAS project (Techniques and Management Strategies for Environmental Restoration and Their Ecological Consequences), was assembled into an Association Contract (FI4PCT95-0021 with the European Atomic Energy Community in the frame of 4 o FP of the UE, and whose objectives were concentrated on the development of techniques and management strategies for environmental remediation after contamination of landscapes or sites with radioactive substances. The main result of the project was the development of a user-friendly decision-aiding computerized system (TEMAS DSS) able to select the best local strategy of restoration when a post-accidental environmental contamination with long lived radionuclides (caesium and strontium) must be faced. TEMAS provides answer for complex scenarios including urban, agricultural and forest ecosystems in the frame of the European Community with different levels of contamination, uses and dimensions. The TEMAS system is organized in two modules, the first to evaluate the radiological impact from the scenario on the affected population, the second to decide the best strategy to control the risk sources. The evaluation methodology breaks down the contaminated scenario into a set of elemental units for restoration taken into account the applicability of the intervention options in terms of practicability, radiological efficiency, cost and secondary effects. Each unit is considered as an individual source of risk and is associated to different applicable countermeasures. Radiecological models describing fluxes of radioactivity from each elemental unit through its associated pathways (e.g. soil, plant, animals to consumption products) and dose models evaluating radiological impact to the population from external

Marshall Islands radiological followup

International Nuclear Information System (INIS)

Greenhouse, N.A.; McGraw, T.F.

1976-01-01

In August, 1968, President Johnson announced that the people of Bikini Atoll would be able to return to their homeland. Thereafter, similar approval was given for the return of the peoples of Enewetak. These two regions, which comprised the Pacific Nuclear Testing Areas from 1946 to 1958, will probably be repopulated by the original inhabitants and their families within the next year. As part of its continuing responsibility to insure the pulbic health and safety in connection with the nuclear program under its sponsorship, ERDA (formerly AEC) has contracted Brookhaven National Laboratory to establish radiological safety and environmental monitoring programs for the returning Bikini and Enewetak peoples. These programs are designed to define the external radiation environment, assess radiation doses from internal emitters in the human food chain, make long range predictions of total doses and dose commitments to individuals an to each population group, and to suggest actions which will minimize doses via the more significant pathways

Marshall Islands radiological followup

International Nuclear Information System (INIS)

Greenhouse, N.A.; McCraw, T.F.

In August, 1968, President Johnson announced that the people of Bikini Atoll would be able to return to their homeland. Thereafter, similar approval was given for the return of the peoples of Enewetak. These two regions, which comprised the Pacific Nuclear Testing Areas from 1946 to 1958, will probably be repopulated by the original inhabitants and their families within the next year. As part of its continuing responsibility to insure the public health and safety in connection with the nuclear programs under its sponsorship, ERDA (formerly AEC) has contracted Brookhaven National Laboratory to establish radiological safety and environmental monitoring programs for the returning Bikini and Enewetak peoples. These programs are described in the following paper. They are designed to define the external radiation environment, assess radiation doses from internal emitters in the human food chain, make long range predictions of total doses and dose commitments to individuals and to each population group, and to suggest actions which will minimize doses via the more significant pathways

Radionuclide content in laundry detergents commercially available on the Serbian market and assessment of radiological environmental hazards

Directory of Open Access Journals (Sweden)

Vukanac Ivana S.

2017-01-01

Full Text Available Laundry detergents are chemicals widely used in everyday life, and in numerous industry branches. In order to perceive the radiological aspect of environmental pollution by wastewater, the analysis of laundry detergents available on the Serbian market was undertaken. Laundry detergent samples were measured by means of gamma spectrometry and the results are presented in this paper. Analysis of the obtained activity concentrations showed that laundry detergents in Serbia mostly fulfill the international recommendation and requirements regarding the phosphate content. Besides that, the content of the detected radionuclides in laundry detergent samples indicates the minor radiological risk to the environment via wastewaters. [Project of the Serbian Ministry of Education, Science and Technological Development, Grant no. 171018

Proceedings of the 3. Regional Meeting on Radiological and Nuclear Safety. Radiological protection in Latin America and the Caribbean. Vol. 1,2

International Nuclear Information System (INIS)

1996-08-01

Two volumes contain more than 183 complete papers presented during the Third Regional Meeting on Radiological Protection and Nuclear Safety held on 23-27 October, 1995 in Cusco-Peru. Latin american specialist talk about nuclear safety and radiological protection, radiation natural exposure, biological effect of radiation, radiotherapy and medical radiological safety, radiological safety in industry and research. Also we deal with subjects related to radiological safety of nuclear and radioactive facilities, radioactive waste management, radioactive material transport, environmental radiological monitoring program, radiological emergency and accidents, instruments and dosimetry, basic safety standards of protection against radiation

Radiological Emergency Response Data

Data.gov (United States)

U.S. Environmental Protection Agency — Quality Data Asset includes all current and historical emergency radiological response event and incident of national significance data and surveillance, monitoring,...

Radiation dose assessments to support evaluations of radiological control levels for recycling or reuse of materials and equipment

Energy Technology Data Exchange (ETDEWEB)

Hill, R.L.; Aaberg, R.L.; Baker, D.A.; Kennedy, W.E. Jr.

1995-07-01

Pacific Northwest Laboratory is providing Environmental Protection Support and Assistance to the USDOE, Office of Environmental Guidance. Air, Water, and Radiation Division. As part of this effort, PNL is collecting data and conducting technical evaluations to support DOE analyses of the feasibility of developing radiological control levels for recycling or reuse of metals, concrete, or equipment containing residual radioactive contamination from DOE operations. The radiological control levels will be risk-based, as developed through a radiation exposure scenario and pathway analysis. The analysis will include evaluation of relevant radionuclides, potential mechanisms of exposure, and both health and non-health-related impacts. The main objective of this report is to develop a methodology for establishing radiological control levels for recycle or reuse. This report provides the results of the radiation exposure scenario and pathway analyses for 42 key radionuclides generated during DOE operations that may be contained in metals or equipment considered for either recycling or reuse. The scenarios and information developed by the IAEA. Application of Exemption Principles to the Recycle and Reuse of Materials from Nuclear Facilities, are used as the initial basis for this study. The analyses were performed for both selected worker populations at metal smelters and for the public downwind of a smelter facility. Doses to the public downwind were estimated using the US (EPA) CAP88-PC computer code with generic data on atmospheric dispersion and population density. Potential non-health-related effects of residual activity on electronics and on film were also analyzed.

Radiation dose assessments to support evaluations of radiological control levels for recycling or reuse of materials and equipment

International Nuclear Information System (INIS)

Hill, R.L.; Aaberg, R.L.; Baker, D.A.; Kennedy, W.E. Jr.

1995-07-01

Pacific Northwest Laboratory is providing Environmental Protection Support and Assistance to the USDOE, Office of Environmental Guidance. Air, Water, and Radiation Division. As part of this effort, PNL is collecting data and conducting technical evaluations to support DOE analyses of the feasibility of developing radiological control levels for recycling or reuse of metals, concrete, or equipment containing residual radioactive contamination from DOE operations. The radiological control levels will be risk-based, as developed through a radiation exposure scenario and pathway analysis. The analysis will include evaluation of relevant radionuclides, potential mechanisms of exposure, and both health and non-health-related impacts. The main objective of this report is to develop a methodology for establishing radiological control levels for recycle or reuse. This report provides the results of the radiation exposure scenario and pathway analyses for 42 key radionuclides generated during DOE operations that may be contained in metals or equipment considered for either recycling or reuse. The scenarios and information developed by the IAEA. Application of Exemption Principles to the Recycle and Reuse of Materials from Nuclear Facilities, are used as the initial basis for this study. The analyses were performed for both selected worker populations at metal smelters and for the public downwind of a smelter facility. Doses to the public downwind were estimated using the US (EPA) CAP88-PC computer code with generic data on atmospheric dispersion and population density. Potential non-health-related effects of residual activity on electronics and on film were also analyzed

Generic environmental impact statement in support of rulemaking on radiological criteria for license termination of NRC-licensed nuclear facilities. Final report, main report

International Nuclear Information System (INIS)

1997-07-01

The action being considered in this Final Generic Environmental Impact Statement (GEIS) is an amendment to the Nuclear Regulatory Commission's (NRC) regulations in 10 CFR Part 20 to include radiological criteria for decommissioning of lands and structures at nuclear facilities. Under the National Environmental Policy Act (NEPA), all Federal agencies must consider the effect of their actions on the environment. To fulfill NRC's responsibilities under NEPA, the Commission is preparing this GEIS which analyzes alternative courses of action and the costs and impacts associated with those alternatives. In preparing the final GEIS, the following approach was taken: (1) a listing was developed of regulatory alternatives for establishing radiological criteria for decommissioning; (2) for each alternative, a detailed analysis and comparison of incremental impacts, both radiological and nonradiological, to workers, members of the public, and the environment, and costs, were performed; and (3) based on the analysis of impacts and costs, conclusions on radiological criteria for decommissioning were provided. Contained in the GEIS are results and conclusions related to achieving, as an objective of decommissioning ALARA, reduction to preexisting background, the radiological criterion for unrestricted use, decommissioning ALARA analysis for soils and structures containing contamination, restricted use and alternative analysis for special site specific situations, and groundwater cleanup. In its analyses, the final GEIS includes consideration of comments made on the draft GEIS during the public comment period

Plan of routine environmental radiological monitoring in the vicinity of nuclear and radioactive facilities of the Country

International Nuclear Information System (INIS)

Czerniczyniec, M.A; Bonetto, J.P.; Giustina, Daniel

2009-01-01

The Nuclear Regulatory Authority (ARN) carries out the monitoring of the environment surrounding Argentina nuclear power plants, independently from the operators' own monitoring programmes. Recently, there has been a review of the criteria used for selecting target radionuclides, sampling matrix, sampling location, and sampling frequency. This revision was based on ARN objectives for an environmental radiological monitoring programme, which are: verification of discharge monitoring results and detection of unadverted/unauthorized emissions; verification of models assumptions and checking that doses to the critical groups are not exceeded; detection of radionuclides presence in the environment and trend analysis; and to provide information to the public. The criteria proposed for adoption implies the monitoring of the relevant radionuclides mentioned in the discharge authorization license, using specific analysis for those considered indicators and screening techniques for the others. The matrix to be sampled must be related with the different exposure pathways, from those related with direct exposure, which require higher sampling frequencies, to accumulating/concentrating matrices, which imply lower sampling frequencies. At least, three points should be sampled, related to both airborne and liquid emissions: a background location, the representative person location, and that where the concentration of a target radionuclide is expected to be maximum. Available modeling software was used for positioning the sampling points. (author)

Reevaluation of environmental monitoring program for radiological emergency at Almirante Alvaro Alberto Nuclear Power Plant, Angra dos Reis, Rio de Janeiro - Brazil

International Nuclear Information System (INIS)

Ferreira, Lilia M.J. Belem; Ramos Junior, Anthenor C.; Gomes, Carlos A.; Carvalho, Zenildo L.; Gouveia, Vandir; Estrada, Julio; Ney, Cezar

1996-01-01

In order to respond to a major radiological emergency at the Almirante Alvaro Alberto Nuclear Power Plant, located in Angra dos Reis, Rio de Janeiro, the Emergency Response Team of the Institute for Radiation Protection and Dosimetry (IRD/CNEN) established a program of environmental monitoring. The purpose of this program is to define a monitoring trend to assess the off-site radiological conditions and give support to decision making for implementing protective measures in case of a radiological accident, taking into account atmospheric diffusion, population conglomerates and their habits, water and land use, contemplating the entire Emergency Planning Zone of 15 km radius. This program has been reevaluated recently, aiming to optimize it and keep it up to date to assure adequacy of environmental surveillance data in support to a prompt response in case of an emergency situation in the nuclear power plant. It has been organized in the form of a handbook to facilitate handling by field teams. Future revisions will be necessary to incorporate additional pertinent information and keep the handbook up to date, since Angra dos Reis is a summer resort region, subject to constant changes. This paper discusses the structure of the environmental monitoring program and describes the content and preparation of this handbook. (author)

Radiological field survey problems and solutions

International Nuclear Information System (INIS)

Deming, E.J.; Boerner, A.J.

1986-01-01

Situations often arise during radiological field surveys which require the health physicist to improvise and/or make spot decisions. At times these situations can be humorous, but they can also present hazards more serious than normal radiological considerations. This presentation will depict various problematic situations encountered by Oak Ridge Associated Universities Radiological Site Assessment Program in the course of performing field environmental surveys. Detailing these potential hazards can alert other field survey groups to problems they may encounter

A review of plutonium environmental data with a bibliography for use in risk assessments

International Nuclear Information System (INIS)

Bartram, B.W.; Wilkinson, M.J.

1983-01-01

Plutonium fueled radioisotopic heat sources find space, terrestrial, and undersea applications to generate electrical power. Such systems under postulated accident conditions could release radioactivity into the environment resulting in risks to the general population in the form of radiological doses and associated health effects. The evaluation of the radiological impact of postulated scenarios involving releases of activity into the environment includes identification of postulated accident release modes, including the probability of release and the release location; source term definition, including the activity of each radionuclide released and the corresponding chemical form and particle size distribution; analysis of the environmental behavior of the released radioactivity to determine the concentrations in environmental media (air, soil, and water) as a function of time; and analysis of the interaction between the environmental concentrations and man, leading to ingestion, inhalation, and external doses through each environmental exposure pathway. 443 refs., 2 figs., 4 tabs

Evaluating the radiological health compliance of some beach ...

African Journals Online (AJOL)

Journal of Applied Sciences and Environmental Management ... Evaluating the radiological health compliance of some beach environments in Delta State ... as well as specified members of the public (customers) are not at radiological risk.

Solid state nuclear track detectors and their application in industrial health, radiological and environmental protection

International Nuclear Information System (INIS)

Urban, M.

1993-09-01

Passive Solid State Nuclear Track Detectors are electrically non conductive solids, mainly used for the registration of α-particles and neutron induced recoils. The stability of the particle tracks in the solid allow longer integration periods, what is essential for the measurement of small, time variant radiation exposures. This report gives an overview on non-photographic track detectors, their processing, dosimetric properties and examples for their application in industrial health, radiological and environmental protection. (orig.) [de

Report on the pre-operational environmental radiological and micrometeorological studies around Kaiga Atomic Power Project site

International Nuclear Information System (INIS)

1999-08-01

This report presents a summary of the results of preoperational environmental radiological and micro- meteorological studies carried out during the year 1992, 1993, 1995, 1998 and 1999. Baseline radioactivity levels in Kaiga environment originating from 137 Cs, 90 Sr and natural radionuclides are given. Micro-meteorological data includes that from SODAR, tower and surface instruments. The data is compared with that observed at other NPP Sites in the country. (author)

Radiological protection of the environment from an NGO perspective

International Nuclear Information System (INIS)

Carroll, S.

2008-01-01

Non-governmental environmental organisations (environmental NGOs) may consider the issue of radiological protection of the environment differently to other interested parties such as regulators or industry. While environmental NGOs are broadly positive towards the current emphasis and engagement on radiological protection of the environment per se, there remain concerns about the precise meaning of the term and the ultimate objectives of the current initiatives. Various strategies are studied and discussed. The disposal of radioactive waste at sea is discussed and a case study presented. What the environmental NGOs are looking for is focused upon and various environmental protection systems are discussed (tk)

Evaluation of critical pathways, radionuclides, and remedial measures for reducing the radiological dose to returning populations at a former nuclear test site

Energy Technology Data Exchange (ETDEWEB)

Robison, W. L., LLNL

1997-11-01

Bikini Island, the major residence island at Bikini Atoll, was contaminated with radioactive fallout as a result of the BRAVO test conducted on March 1, 1954. We have identified the critical radionuclides and supplied radiological data needed to develop dose estimates for all possible exposure pathways. These estimates show that the major dose to returning populations would result from ingestion of cesium-137 (137 Cs) in locally grown terrestrial foods where the predicted population average effective dose exceeds current federal guidelines. Consequently, we designed several long-term field experiments to develop and evaluate methods to reduce the 137 Cs content in locally grown foods.This paper gives a general outline of the remediation experiments with a more detailed description of a preferred combined option. Our comparative evaluation on various remedial methods show that the combined option--potassium treatment of the entire islands with limited excavation of soil in village an d housing areas--will be effective in reducing the dose to about 10% of pretreatment levels, and offers very significant benefits with respect to adverse environmental impacts as well as savings in overall costs, time, and required expert resources.

Radiological environmental monitoring programs at Canadian nuclear facilities - a practical model for follow-up activities under the Canadian Environmental Assessment Act

International Nuclear Information System (INIS)

Tamm, J.A.; Zach, R.

2000-01-01

Under the Canadian Environmental Assessment Act (the Act), a federal authority, if it considers it appropriate, is to design a follow-up program for a project undergoing a federal environmental assessment and arrange for implementation of that program. Under the Act a follow-up program means a set of activities for verifying the accuracy of the environmental assessment (EA) of a project and for determining the effectiveness of any measures taken to mitigate any adverse environmental effects resulting from the project. The Act currently does not include regulations, guidelines, standards or procedures regarding the design, content and implementation requirements for follow-up programs (Canadian Environmental Assessment Agency [the Agency] 1999). Uncertainties also exist regarding the roles and responsibilities in designing, implementing, enforcing and auditing such activities. The Agency is presently specifying appropriate activities to address these issues. This paper considers the existing radiological environmental monitoring programs at nuclear facilities. Such programs consist of two types of monitoring-radioactivity releases from the facility via liquid and gaseous waste streams, and radioactivity in the environment at large, beyond the facility's immediate location. Such programs have been developed by AECL, Canadian nuclear utilities and uranium mining companies. Our analysis show that these programs can provide a good model for follow-up programs under the Act. (author)

Summaries of studies carried out in the NKS/BOK-2 project. Technical report[Radiological and environmental consequences

Energy Technology Data Exchange (ETDEWEB)

Palsson, S E [Icelandic Radiation Protection Inst., Reykjavik (Iceland)

2002-12-01

Summaries of studies carried out in the NKSBOK-2 project, Radiological and Environmental Consequences. The structure of the project as such is described in NKS-64, Radiological and Environmental Consequences - Final Report of the Nordic Nuclear Safety Research Project BOK-2. That report also includes compilations based on the summaries presented in this report. The project was carried out 1998-2001 with participants from all the Nordic countries. Representatives from the Baltic States were also invited to some of the meetings and seminars. The project consisted of work on terrestrial and marine radioecology and had a broad scope in order to enable participation of research groups with various fields of interest. The topics included improving assessment of old and recent fallout, use of radionuclides as tracers in Nordic marine areas, improving assessment of internal doses and use of mass spectrometry in radioecology. This report is a compilation of summaries from each research group, 32 papers in all, and gives references to papers published in scientific journals. Some of the studies have been described previously, at least to some degree, in NKS-70, Proceedings of the 8{sup th} Nordic Seminar on Radioecology, 25-28 February 2001, Rovaniemi, Finland. (au)

New Jersey's experience with implementing Protective Action Guides during the 1988 Salem ingestion pathway exercise

International Nuclear Information System (INIS)

White, Duncan

1989-01-01

On November 30 and December 1, 1988, the New Jersey Department of Environmental Protection (DEP) and three other State agencies (Health, Agriculture and State Police) participated in the ingestion pathway portion of the 1988 Salem Nuclear Generating Station Emergency Exercise. The purpose of this phase of the exercise was to demonstrate the ingestion pathway components of the State's Radiological Emergency Response Plan (RERP) to the Federal Emergency Management Agency (FEMA). The intent of this paper is to provide a summary of difficulties and some lessons learned in implementing the DEP's ingestion pathway Protective Action Guides (PAGs) during the exercise as well as during the preparation of a total population dose estimate (TPDE)

New Jersey's experience with implementing Protective Action Guides during the 1988 Salem ingestion pathway exercise

Energy Technology Data Exchange (ETDEWEB)

White, Duncan [New Jersey Department of Environmental Protection, Trenton, NJ (United States)

1989-09-01

On November 30 and December 1, 1988, the New Jersey Department of Environmental Protection (DEP) and three other State agencies (Health, Agriculture and State Police) participated in the ingestion pathway portion of the 1988 Salem Nuclear Generating Station Emergency Exercise. The purpose of this phase of the exercise was to demonstrate the ingestion pathway components of the State's Radiological Emergency Response Plan (RERP) to the Federal Emergency Management Agency (FEMA). The intent of this paper is to provide a summary of difficulties and some lessons learned in implementing the DEP's ingestion pathway Protective Action Guides (PAGs) during the exercise as well as during the preparation of a total population dose estimate (TPDE)

The Potential Pathways of Radionuclide Transformations On The Location Candidate of Nuclear Power Plants in Muria Peninsula

International Nuclear Information System (INIS)

Simandjuntak, A.G.; Syahrir

1998-01-01

The potential pathways of radionuclide transformations on the location candidate of nuclear power plants in Muria peninsula proposed to explain the potential of radionuclide pathways in the ecosystem to human based on annual effective dose calculations with elimination factor ≥ 1 of dose limit 50 mSv per year. The effective dose equivalent calculations used the program package Genll. The datum found from Bureau of Statistic Centre and NEWJEC was taken into calculations. The result of this study is very useful for radiological impact and environmental impact analysis. (author)

Radiological Control Technician: Phase 1, Site academic training lesson plans

International Nuclear Information System (INIS)

1992-10-01

This volume provides lesson plans for training radiological control technicians. Covered here is basic radiological documentation, counting errors, dosimetry, environmental monitoring, and radiation instruments

Assessment of the radiological control at the IPEN radioisotope production facility

International Nuclear Information System (INIS)

Carneiro, Janete C.G.G.; Sanches, Matias P.; Rodrigues, Demerval L.; Campos, Daniela; Nogueira, Paulo R.; Damato, Sandra R.; Pecequilo, Brigitte R.

2014-01-01

The main objective of this work is to evaluate the 2013 annual radiological control results in the radiopharmaceuticals areas of the Instituto de Pesquisas Energeticas e Nucleares, IPEN/SP, and the environmental radiological impact, resulting from the practices there performed. The current evaluation was performed through the analysis of the results obtained from occupational and environmental monitoring with air samplers and TL dosimeters. All monitoring results were compared with the limits established by national standards. The radionuclides detected by air sampling (in charcoal and paper filters) at the workplace during radioisotope production were 131 I, 99m Tc and 99 Mo, with activities concentrations values below the annual limits values. For the radioactive gaseous releases (Bq/m 3 ), the activities concentrations also remained below the maximum permissible values, excepting to 125 I release due to an unusual event occurred in a researcher laboratory, but the radiological impact to environmental was no significant. The occupational monitoring assessment was confirmed by the Environmental Radiological Monitoring Program results with air samplers and TL dosimeters. The mean annual background radiation at IPEN in 2013, according to the Environmental Radiological Monitoring Program results was 1.06 mSv. y -1 , below the ICRP 103 recommended limit of 20 mSv.y -1 for workers. (author)

Monitoring of the radiological environmental impact of the AREVA site of Tricastin; Suivi de l'impact radiologique environnemental des activites du site AREVA du Tricastin

Energy Technology Data Exchange (ETDEWEB)

Mercat, C.; Brun, F.; Florens, P.; Petit, J. [AREVA NC Pierrelatte, Direction surete environnement du site du Tricastin, 26 (France); Garnier, F. [EURODIF Production, Direction qualite securite surete environnement, 26 (France); Devin, P. [AREVA NC Pierrelatte, Direction surete, sante, securite, environnement, 26 (France)

2010-06-15

Set up at the beginning of the site's operations, in 1962, the monitoring of the radiological environmental impact of the AREVA site of Tricastin has evolved over time to meet more specifically the multiple objectives of environmental monitoring: to prove the respect of the commitments required by the authorities, to be able to detect a dysfunction in the observed levels, to enable the assessment of impacts of industrial activities, to ensure the balance between environmental quality and the use made by the local population and to inform the public of the radiological state of the environment. Thousands of data were acquired on the radioactivity of all environmental compartments as well as on the functioning of local ecosystems. Today, the Network of Environmental Monitoring of AREVA Tricastin goes beyond the requirements of routine monitoring to provide innovative solutions for monitoring the radioactivity (especially for uranium) in the environment. (author)

Annual radiological environmental operating report: Browns Ferry Nuclear Plant, 1992

International Nuclear Information System (INIS)

1993-04-01

This report describes the environmental radiological monitoring program conducted by TVA in the vicinity of Browns Ferry Nuclear Plant (BFN) in 1992. The program includes the collection of samples from the environment and the determination of the concentrations of radioactive materials in the samples. Samples are taken from stations in the general area of the plant and from areas not influenced by plant operations. Station locations are selected after careful consideration of the weather patterns and projected radiation doses to the various areas around the plant. Material sampled includes air, water, milk, foods, vegetation, soil, fish, sediment, and direct radiation levels. Results from stations near the plant are compared with concentrations from control stations and with preoperational measurements to determine potential impacts of plant operations. Small amounts of Co-60 and Cs-134 were found in sediment samples downstream from the plant. This activity in stream sediment would result in no measurable increase over background in the dose to the general public

Results of the radiological environmental monitoring network in Cantabria, Spain

International Nuclear Information System (INIS)

Soto, J.; Rodenas, C.; Gomez, J.; Quindos, L.S.; Fernandez, P.L.

1997-01-01

The Medical Physics Department in the University of Cantabria, Spain as member belonging to the radiological environmental Monitoring Network has been carried out a series of measures about radioactive elements in air, rain water and soil. This report shows the methodology used and the results obtained in the measurement of the gross-alpha and gross beta activities. 90S r and gamma spectrometry in atmospheric aerosols; the activity of 131I in air; the gross-beta activity 90 Sr and gamma spectrometry in rain water and dry deposition: and the activity of 90S r gamma spectrometer in soils. The average values of the gross-alpha and gross beta activities in air has been 4 x 10 -5 and 32 x10 -5B q/m 3, respectively. The concentration of 131I has been inferior to the limit of detection in the whole of measurements. Finally, has been found small concentrations of 90S r and the 137C s in soils samples

Environmental-pathways analysis for evaluation of a low-level waste disposal site

International Nuclear Information System (INIS)

Lee, D.W.; Ketelle, R.H.; Pin, F.G.; Hill, G.S.

1983-01-01

The suitability of a site for the shallow land burial of low-level waste is evaluated by an environmental-pathways analysis. The environmental-pathways analysis considers the probable paths for the transport of contamination to man and models the long-term transport of contamination to determine the resulting dose-to-man. The model of the long-term transport of contamination is developed for a proposed site using data obtained from a comprehensive laboratory and field investigation. The proposed site is located at the US Department of Energy Portsmouth Reservation, Piketon, Ohio and is planned to accept low-level radioactive waste generated by the enrichment of uranium. Laboratory studies were performed to characterize the waste and determine the wastes' leaching and retardation characteristics with site soils and groundwater. Comprehensive drilling, sampling and laboratory investigations were performed to provide the necessary information for interpreting the site's geology and hydrology. Field tests were performed to further quantify the site's hydrology. The pathway of greatest concern is the migration of contaminated groundwater and subsequent consumption by man. This pathway was modeled using a numerical simulation of the long-term transport of contamination. Conservative scenarios were developed for leachate generation and migration through the geohydrologic system. The dose-to-man determined from the pathways analysis formed the basis for evaluating site acceptability and providing recommendations for site design and development

Environmental pathways analysis for evaluation of a low-level waste disposal site

International Nuclear Information System (INIS)

Lee, D.W.; Ketelle, R.H.; Pin, F.G.; Hill, G.S.

1984-01-01

The suitability of a site for the shallow land burial of low-level waste is evaluated by an environmental pathways analysis. The environmental pathways analysis considers the probable paths for the transport of contamination to man and models the long-term transport of contamination to determine the resulting dose to man. The model of the long-term transport of contamination is developed for a proposed site using data obtained from a comprehensive laboratory and field investigation. The proposed site is located at the US Department of Energy Portsmouth Reservation, Piketon, Ohio, and is planned to accept low-level radioactive waste generated by the enrichment of uranium. Laboratory studies were performed to characterize the waste and determine the wastes' leaching and retardation characteristics with site soils and groundwater. Comprehensive drilling, sampling and laboratory investigations were performed to provide the necessary information for interpreting the site's geology and hydrology. Field tests were performed to further quantify the site's hydrology. The pathway of greatest concern is the migration of contaminated groundwater and subsequent consumption by man. This pathway was modelled using a numerical simulation of the long-term transport of contamination. Conservative scenarios were developed for leachate generation and migration through the geohydrologic system. The dose to man determined from the pathways analysis formed the basis for evaluating site acceptability and providing recommendations for site design and development. (author)

Radiological Control Technician: Phase 1, Site academic training study guides

International Nuclear Information System (INIS)

1992-10-01

This volume is a study guide for training Radiological Control Technicians. Provided herein are support materials for learning radiological documentation, communication systems, counting errors and statistics, dosimetry, contamination control, airborne sampling program methods, respiratory protection, radiological source control, environmental monitoring, access control and work area setup, radiological work coverage, shipment and receipt for radioactive material, radiological incidents and emergencies, personnel decontamination, first aid, radiation survey instrumentation, contamination monitoring, air sampling, and counting room equipment

Environmental monitoring program for radiological emergencies at the Almirante Alvaro Alberto Nuclear Power Plant, Angra dos Reis, Rio de Janeiro, Brazil

Energy Technology Data Exchange (ETDEWEB)

Ferreira, Lilia M.J. Belem; Ramos Junior, Anthenor C.; Gomes, Carlos A.; Carvalho, Zenildo L.; Gouveia, Vandir; Estrada, Julio; Ney, Cezar [Instituto de Radioprotecao e Dosimetria (IRD), Rio de Janeiro, RJ (Brazil)

1997-12-31

In order to respond to a major radiological emergency at the Almirante Alvaro Alberto Nuclear Power Plant, located in Angra do Reis, Rio de Janeiro, the Emergency Response Team of the Institute of Radiation Protection and Dosimetry (IRD/CNEN) established a program of environmental monitoring. A monitoring trend to assess the off-site radiological conditions and give support to decision making for implementing protective measure in case of a radiological accident is presented. For the selection of the monitoring points, the program takes into account atmospheric diffusion, population conglomerates and their habits, water and land use; it includes the entire Emergency Planning Zone of 15 km radius. The program has been organized in the form of a handbook to facilitate handling by field teams 2 refs., 1 fig.; e-mail: lilia at ird.gov.br

Estimating environmental co-benefits of U.S. low-carbon pathways using an integrated assessment model with state-level resolution.

Science.gov (United States)

Ou, Yang; Shi, Wenjing; Smith, Steven J; Ledna, Catherine M; West, J Jason; Nolte, Christopher G; Loughlin, Daniel H

2018-04-15

There are many technological pathways that can lead to reduced carbon dioxide emissions. However, these pathways can have substantially different impacts on other environmental endpoints, such as air quality and energy-related water demand. This study uses an integrated assessment model with state-level resolution of the energy system to compare environmental impacts of alternative low-carbon pathways for the United States. One set of pathways emphasizes nuclear energy and carbon capture and storage, while another set emphasizes renewable energy, including wind, solar, geothermal power, and bioenergy. These are compared with pathways in which all technologies are available. Air pollutant emissions, mortality costs attributable to particulate matter smaller than 2.5 μm in diameter, and energy-related water demands are evaluated for 50% and 80% carbon dioxide reduction targets in 2050. The renewable low-carbon pathways require less water withdrawal and consumption than the nuclear and carbon capture pathways. However, the renewable low-carbon pathways modeled in this study produce higher particulate matter-related mortality costs due to greater use of biomass in residential heating. Environmental co-benefits differ among states because of factors such as existing technology stock, resource availability, and environmental and energy policies.

Generic environmental impact statement in support of rulemaking on radiological criteria for decommissioning of NRC-licensed nuclear facilities. Appendices; Draft report for comment -- Volume 2

International Nuclear Information System (INIS)

1994-08-01

The action being considered in this draft Generic Environmental Impact Statement (GEIS) is an amendment to the Nuclear Regulatory Commission's (NRC) regulations in 10 CFR Part 20 to include radiological criteria for decommissioning of lands and structures at nuclear facilities. Under the National Environmental Policy Act (NEPA), all Federal agencies must consider the effect of their actions on the environment. To fulfill NRC's responsibilities under NEPA, the Commission is preparing this GEIS which analyzes alternative courses of action and the costs and impacts associated with those alternatives. In preparing the GEIS, the following approach was taken: (1) a listing was developed of regulatory alternatives for establishing radiological criteria for decommissioning; (2) for each alternative, a detailed analysis and comparison of incremental impacts, both radiological and nonradiological, to workers, members of the public, and the environment, and costs, were performed; and (3) based on the analysis of impacts and costs, preliminary recommendations were provided. Contained in the GEIS are recommendations related to the definition of decommissioning, the scope of rulemaking, the radiological criteria, restrictions on use, citizen participation, use of the GEIS in site-specific cases, and minimization of contamination

Generic environmental impact statement in support of rulemaking on radiological criteria for license termination of NRC-licensed nuclear facilities. Final report, appendices A and B

International Nuclear Information System (INIS)

1997-07-01

The action being considered in this Final Generic Environmental Impact Statement (GEIS) is an amendment to the Nuclear Regulatory Commission''s (NRC) regulations in 10 CFR Part 20 to include radiological criteria for decommissioning of lands and structures at nuclear facilities. Under the National Environmental Policy Act (NEPA), all Federal agencies must consider the effect of their actions on the environment. To fulfill NRC''s responsibilities under NEPA, the Commission is preparing this GEIS which analyzes alternative courses of action and the costs and impacts associated with those alternatives. In preparing the final GEIS, the following approach was taken: (1) a listing was developed of regulatory alternatives for establishing radiological criteria for decommissioning; (2) for each alternative, a detailed analysis and comparison of incremental impacts, both radiological and nonradiological, to workers, members of the public, and the environment, and costs were performed; and (3) based on the analysis of impacts and costs, conclusions on radiological criteria for decommissioning were provided. Contained in the GEIS are results and conclusions related to achieving, as an objective of decommissioning ALARA, reduction to preexisting background, the radiological criterion for unrestricted use, decommissioning ALARA analysis for soils and structures containing contamination, restricted use and alternative analysis for special site-specific situations and groundwater cleanup. In its analyses, the final GEIS includes consideration of comments made on the draft GEIS during the public comment period

Assessment of the radiological control at the IPEN radioisotope production facility

Energy Technology Data Exchange (ETDEWEB)

Carneiro, J.C.G.G.; Sanches, M.P.; Rodrigues, D.L.; Campos, D.; Nogueira, P.R.; Damatto, S.R.; Pecequilo, B.R.S. [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

2015-07-01

The main objective of this work is to evaluate the 2013 annual radiological control results in the radiopharmaceuticals areas of the Nuclear and Energy Research Institute, IPEN/SP, Brazil and the environmental radiological impact, resulting from the practices there performed. The current evaluation was performed through the analysis of the results obtained from occupational and environmental monitoring with air samplers and TL dosimeters. All monitoring results were compared with the limits established by national standards. The radionuclides detected by air sampling (in activated carbon cartridges and filter paper) at the workplace during radioisotope production were {sup 131}I, {sup 99m}Tc and {sup 99}Mo, with activities concentrations values below the annual limits values. For the radioactive gaseous releases (Bq/m{sup 3} ), the activities concentrations also remained below the maximum admissible values, excepting to {sup 125}I release due to an unusual event occurred in a researcher laboratory, but the radiological impact to environmental was no significant. The occupational monitoring assessment was confirmed by the Environmental Radiological Monitoring Program results with air samplers and TL dosimeters. The mean annual background radiation at IPEN in 2013, according to the Environmental Radiological Monitoring Program results was 1.06 mSv. y{sup -1} , below the ICRP 103 recommended limit of 20 mSv.y{sup -1} for workers. (author)

National Radiological Fixed Lab Data

Data.gov (United States)

U.S. Environmental Protection Agency — The National Radiological Fixed Laboratory Data Asset includes data produced in support of various clients such as other EPA offices, EPA Regional programs, DOE,...

Clinic-Radiological Study of facial paralysis

International Nuclear Information System (INIS)

Olier, J.; Bacaicoa, M.C.; Guridi, J.; Gil, J.L.; Elcarte, F.; Delgado, G.

1992-01-01

We have gathered 159 cases of facial paralysis from recent records in our hospital, including paralyses of central as well as peripheral origin, and presenting as the only symptom or as one of several major symptoms of the discomfort of each patient. Sixty-four percent of them were studied by CT scan and/or MR, confirming the existence of alterations in the pathway of nerve pair VII in 50% of the patients who underwent radiological study. Idiopathic facial paralysis was the most common type (42% of the total); while tumors and post-traumatic findings were the most constant radiological findings. From the analysis of the data, the importance of the clinical criteria for selection of the patients in the study and the protocol for radiological diagnosis employed can be deduced. (author)

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

International Nuclear Information System (INIS)

Drozdovitch, V.V.

2001-01-01

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

Methodology for assessing the radiological impact on environment

International Nuclear Information System (INIS)

Zhang Yongxing

1988-01-01

During the 1940s, the early stages of nuclear programmes, the assessment of the radionuclides released to the environment was first initiated for the large nuclear facilities, with emphasis placed on environmental monitoring. The radiological assessment is a quantitative process of estimating the impact on human, resulting from the releases of the radionuclides to the environment. It is a multidisciplinary subject including identification of source terms, environmental transport and dispersion, health effect evaluation and so on. This paper briefly, but comprehensively, describes the methodology for the assessment of the environmental radiological consequence, and discusses the trend of various research fields related to the subject

GENII: The Hanford Environmental Radiation Dosimetry Software System: Volume 2, Users' manual: Hanford Environmental Dosimetry Upgrade Project

International Nuclear Information System (INIS)

Napier, B.A.; Peloquin, R.A.; Strenge, D.L.; Ramsdell, J.V.

1988-11-01

The Hanford Environmental Dosimetry Upgrade Project was undertaken to incorporate the internal dosimetry models recommended by the International Commission on Radiological Protection (ICRP) in updated versions of the environmental pathway analysis models used at Hanford. The resulting second generation of Hanford environmental dosimetry computer codes is compiled in the Hanford Environmental Dosimetry System (Generation II, or GENII). The purpose of this coupled system of computer codes is to analyze environmental contamination of, air, water, or soil. This is accomplished by calculating radiation doses to individuals or populations. GENII is described in three volumes of documentation. This second volume is a Users' Manual, providing code structure, users' instructions, required system configurations, and QA-related topics. The first volume describes the theoretical considerations of the system. The third volume is a Code Maintenance Manual for the user who requires knowledge of code detail. It includes logic diagrams, global dictionary, worksheets, example hand calculations, and listings of the code and its associated data libraries. 27 refs., 17 figs., 23 tabs

The Symbiose project: an integrated framework for performing environmental radiological risk assessment

International Nuclear Information System (INIS)

Gonze, M.A.; Mourlon, C.; Garcia-Sanchez, L.; Beaugelin, K.; Chen, T.; Le Dizes, S.

2004-01-01

Human health and ecological risk assessments usually require the integration of a wide range of environmental data and modelling approaches, with a varying level of detail dependent on the management objectives, the complexity of the site and the level of ignorance about the pollutant behaviour/toxicity. Like most scientists and assessors did it recently, we recognized the need for developing comprehensive, integrated and flexible approaches to risk assessment. To meet these needs, IRSN launched the Symbiose project (2002-2006) which aims first, at designing a framework for integrating and managing data, methods and knowledge of some relevance in radiological risk to humans/biota assessment studies, and second, at implementing this framework in an information management, modelling and calculation platform. Feasibility developments (currently completed) led to the specification of a fully integrated, object-oriented and hierarchical approach for describing the fate, transport and effect of radionuclides in spatially-distributed environmental systems. This innovative approach has then been implemented in a platform prototype, main components of which are a user-friendly and modular simulation environment (e.g. using GoldSim toolbox), and a hierarchical object-oriented biosphere database. Both conceptual and technical developments will be presented here. (author)

Preliminary study of the environmental radiological assessment for the Garigliano nuclear power plant decommissioning

International Nuclear Information System (INIS)

Esposito, A.M.; Sabbarese, C.; Sirignano, C.; Visciano, L.; D'Onofrio, A.D.; Lubritto, C.; Terrasi, F.

2002-01-01

In the last few years many nuclear installations in the world have been stopped either because they reached the end of production lifetime, or for operation problems or, like in Italy, for political decisions. This stop started the decommissioning procedure. It consists in the dismantling of the nuclear installation with appropriate controls and limitations of environmental and radiological impact which arises from these operations. The evaluation of risk and the actions needed for the population safeguard are generally inspired to the recommendations of the International Commission on Radiological Protection (ICRP), but each country faces the problem with different evaluation methodologies and calculations. That is due to different laws and environmental, social and economical context where nuclear installations are located. For this, the decommissioning operations must be separately evaluated for each nuclear installation. In this paper, we present the work carried out so far about the decommissioning of the Nuclear Power Plant of Garigliano (Caserta, Italy), which is managed by SoGIN (Societa di Gestione degli Impianti Nucleari). This Nuclear Power Plant began its activity in 1964 by using a boiling water reactor with a production of 160 MW electric power. In 1979 this nuclear installation was stopped for maintenance and operation has not been resumed until the referendum in 1986, after which all Italian nuclear plants were stopped. Now, the Nuclear Power Plant of Garigliano has the reactor isolated respect to the remaining part and all components and pipes have been drained and sealed. The underground tanks of radioactive wastes have been evacuated and decontaminated. The radioactive wastes have been completely conditioned with cementification in drums suitable to prevent outside release

Generic environmental impact statement in support of rulemaking on radiological criteria for decommissioning of NRC-licensed nuclear facilities. Main report; Draft report for comment: Volume 1

International Nuclear Information System (INIS)

1994-08-01

The action being considered in this draft Generic Environmental Impact Statement (GEIS) is an amendment to the Nuclear Regulatory Commission's (NRC) regulations in 10 CFR Part 20 to include radiological criteria for decommissioning of lands and structures at nuclear facilities. Under the National Environmental Policy Act (NEPA), all Federal agencies must consider the effect of their actions on the environment. To fulfill NRC's responsibilities under NEPA, the Commission is preparing this GEIS which analyzes alternative courses of action and the costs and impacts associated with those alternatives. In preparing the GEIS, the following approach was taken: (1) a listing was developed of regulatory alternatives for establishing radiological criteria for decommissioning; (2) for each alternative, a detailed analysis and comparison of incremental impacts, both radiological and nonradiological, to workers, members of the public, and the environment, and costs, were performed; and (3) based on the analysis of impacts and costs, preliminary recommendations were provided. Contained in the GEIS are recommendations related to the definition of decommissioning, the scope of rulemaking, the radiological criteria, restrictions on use, citizen participation, use of the GEIS in site-specific cases, and minimization of contamination

Proceedings of the 3. Regional Meeting on Radiological and Nuclear Safety, Regional Meeting on International Radiation Protection Association (IRPA)and 3. Peruvian Meeting on Radiological Protection

International Nuclear Information System (INIS)

1995-10-01

There we show works of the Third Regional Meeting on Radiological and Nuclear Safety held on 23-27 October, 1995 in Cusco-Peru. Latin americans specialists talk about nuclear safety and radiological protection, radiation natural exposure, biological effect of radiation, radiotherapy and medical radiological safety, radiological safety in industry and research. Also we deal with subjects related to radiological safety of nuclear and radioactive facilities, radioactive waste management, radioactive material transport, environmental radiological monitoring program, radiological emergency and accidents, instruments and dosimetry, basic safety standards of protection against radiation. More than 225 works were presented on the meeting

An overview of background environmental radiological surveillance around Kudankulam nuclear power project site

International Nuclear Information System (INIS)

Rajan, M.P.; Vijayakumar, B.; George, Thomas; Rajan, P.S.; Rana, B.K.; Kumar, M.; Hegde, A.G.; Chougaonkar, M.P.

2005-01-01

A modern Environmental Survey Laboratory (ESL) equipped with state-of-art nuclear counting, chemical and ecological equipment's has been set up at Kudankulam at the very beginning of construction activities to carry out pre operational and baseline radioactivity measurements. Construction activities for the two VVER type 1000 MWe reactors at the site are progressing ahead of schedule and the first unit is slated to be critical in the year 2007. This paper presents the results of environmental radiological surveillance carried out for the last one year in Kudankulam environs. General radiation background in the area varies in the range of 0.1 - 0.7 μGy/h and elevated levels as high as 20 μGy/h are noticed in beach areas. The major contribution to the background radiation in high background areas comes from 232 Th and its daughter products. The concentrations of 40 K are of normal order and comparable to other NPP sites and normal background areas. The concentrations of fallout nuclides are very low and are at global fallout levels. (author)

Radiological accidents: education for prevention and confrontation

International Nuclear Information System (INIS)

Cardenas Herrera, Juan; Fernandez Gomez, Isis Maria

2008-01-01

The purpose of this work is to train and inform on radiological accidents as a preventive measure to improve the people life quality. Radiological accidents are part of the events of technological origin which are composed of nuclear and radiological accidents. As a notable figure is determined that there have been 423 radiological accidents from 1944 to 2005 and among the causes prevail industrial accidents, by irradiations, medical accidents and of laboratories, among others. Latin American countries such as Argentina, Brazil, Mexico and Peru are some where most accidents have occurred by radioactivity. The radiological accidents can have sociological, environmental, economic, social and political consequences. In addition, there are scenarios of potential nuclear accidents and in them the potential human consequences. Also, the importance of the organization and planning in a nuclear emergency is highlighted. Finally, the experience that Cuba has lived on the subject of radiological accidents is described [es

A Comparative Study Environmental and Radiological Causes Of Cancer In River Nile State, Sudan

Science.gov (United States)

Hamid, Eyad; Khair, Hatim

The causes of cancer in River Nile state are differ between environmental and radiological, this paper tried to make comparison between the two causes, to determine the real cause behind the large rising of cancer cases in this state, considering the daily habits for the patients and the possible contamination in the natural resources around them. The noticeable thing that most of cancer cases are might be due to the high concentration of nitrate pollutant detected in natural resources such as drinking water; also by looking to the radioactive elements we see there's high concentration of some radioactive elements specially the K-40 which found in Portulaca Oleracea.

Annual site environmental report for calendar year 1990

International Nuclear Information System (INIS)

1991-09-01

This report presents the results of a comprehensive, year-round program to monitor the impact of the Weldon Spring site (WSS) on the surrounding region's groundwater, surface waters, and air quality through multiple pathways as well as monitoring for potential exposure to receptor human populations. Information is also presented on the environmental monitoring quality assurance program, waste management activities, audits, and reviews, and special environmental studies. The data reported have been collected from a growing complex of monitoring stations and a routine sampling program supplemented by the following: An air monitoring network of 22 stations located within and on the perimeters of the two operable remedial units of the site, and at critical receptor locations around the WSS: Six National Pollutant Discharge Elimination System (NPDES) locations and over 25 surface water sampling locations; twenty-two locations for measuring external gamma radiation; over 100 groundwater monitoring wells and piezometers; dozens of soil and ground surface scanning locations for potential direct contact exposure; and an on-site meteorological station. Comprehensive environmental monitoring data for 1990 show that emissions of radiological contamination from the WSS continue to decrease, and contaminant migration pathways and environmental variability are better understood. 26 figs., 34 tabs

Floral pathway integrator gene expression mediates gradual transmission of environmental and endogenous cues to flowering time.

Science.gov (United States)

van Dijk, Aalt D J; Molenaar, Jaap

2017-01-01

The appropriate timing of flowering is crucial for the reproductive success of plants. Hence, intricate genetic networks integrate various environmental and endogenous cues such as temperature or hormonal statues. These signals integrate into a network of floral pathway integrator genes. At a quantitative level, it is currently unclear how the impact of genetic variation in signaling pathways on flowering time is mediated by floral pathway integrator genes. Here, using datasets available from literature, we connect Arabidopsis thaliana flowering time in genetic backgrounds varying in upstream signalling components with the expression levels of floral pathway integrator genes in these genetic backgrounds. Our modelling results indicate that flowering time depends in a quite linear way on expression levels of floral pathway integrator genes. This gradual, proportional response of flowering time to upstream changes enables a gradual adaptation to changing environmental factors such as temperature and light.

Floral pathway integrator gene expression mediates gradual transmission of environmental and endogenous cues to flowering time

Directory of Open Access Journals (Sweden)

Aalt D.J. van Dijk

2017-04-01

Full Text Available The appropriate timing of flowering is crucial for the reproductive success of plants. Hence, intricate genetic networks integrate various environmental and endogenous cues such as temperature or hormonal statues. These signals integrate into a network of floral pathway integrator genes. At a quantitative level, it is currently unclear how the impact of genetic variation in signaling pathways on flowering time is mediated by floral pathway integrator genes. Here, using datasets available from literature, we connect Arabidopsis thaliana flowering time in genetic backgrounds varying in upstream signalling components with the expression levels of floral pathway integrator genes in these genetic backgrounds. Our modelling results indicate that flowering time depends in a quite linear way on expression levels of floral pathway integrator genes. This gradual, proportional response of flowering time to upstream changes enables a gradual adaptation to changing environmental factors such as temperature and light.

Thermoluminescent dosimetry in veterinary diagnostic radiology

International Nuclear Information System (INIS)

Hernández-Ruiz, L.; Jimenez-Flores, Y.; Rivera-Montalvo, T.; Arias-Cisneros, L.; Méndez-Aguilar, R.E.; Uribe-Izquierdo, P.

2012-01-01

This paper presents the results of Environmental and Personnel Dosimetry made in a radiology area of a veterinary hospital. Dosimetry was realized using thermoluminescent (TL) materials. Environmental Dosimetry results show that areas closer to the X-ray equipment are safe. Personnel Dosimetry shows important measurements of daily workday in some persons near to the limit established by ICRP. TL results of radiation measurement suggest TLDs are good candidates as a dosimeter to radiation dosimetry in veterinary radiology. - Highlights: ► Personnel dosimetry in laboratory veterinary diagnostic was determined. ► Student workplaces are safe against radiation. ► Efficiency value of apron lead was determined. ► X-ray beams distribution into veterinarian laboratory was measured.

Pathway analysis concepts for radiological impact assessment

International Nuclear Information System (INIS)

Moroney, J.R.

1992-06-01

The concepts underlying exposure pathways analysis are outlined with reference to the features of the two broad types of radionuclide transport models now in use - dynamic and steady-state - and the methods for constructing and developing them. By way of illustration, representative radiation doses are estimated for the four main exposure pathways likely to be involved in the land application of effluent water from Retention Pond 2 of Ranger Uranium Mines. These include: external irradiation by 226 Ra and natural uranium (Un at) in soil, ingestion of 226 Ra and Un at in food, inhalation of 222 Rn daughter products from 226 Rn in soil, and inhalation of 226 Ra and Un at in airborne dust resuspended from soil. Consideration has been given to local residents pursuing a traditional lifestyle on conclusion of the land application program. Because of the possible importance of the contribution from resuspended dust, currently available data are explored in refining the methodology for the pathway and developing a more appropriate model for it. 37 refs., 9 tabs., 6 figs

Environmental impacts of the transportation of radioactive materials in urban areas

International Nuclear Information System (INIS)

Finley, N.C.; Taylor, J.M.; Daniel, S.L.; Ericson, D.M. Jr.

1980-01-01

Radioactive material transport in urban areas is investigated and the specific urban features which influence environmental impacts are addressed. These features include the geographic and demographic make-up, and vehicular population and transportation patterns in the area. Previous efforts have not identified a most important population exposure pathway or group. This assessment examines several pathways and a number of urban specific population groups to evaluate their relative significance. In addition, because different causative events contribute to the overall environmental impacts, this assessment addresses four of these: incident free transport, vehicular accidents, human errors, and sabotage or malevolent acts. Not only does radioactive material transport produce radiological and economic consequences but also it can have social impacts. The objective of this study is to examine both the quantitative environmental impacts of radioactive material transport in urban areas and the more subjective social effects of this process. The social impacts assessment was performed by Battelle Human Affairs Research Centers, Seattle, Washington and their conclusions are only summarized here

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

Radiological assessment of depleted uranium migration offsite from an ordnance range

International Nuclear Information System (INIS)

Rynders, D.G.

1996-01-01

The military utilizes ordnance loaded with depleted uranium in order to maximize armor penetrating capabilities. These weapons are tested on open ranges where the weapons are fired through a cloth target and impact into the soil. This paper examines the potential environmental impact from use of depleted uranium in an open setting. A preliminary pathway analysis was performed to examine potential routes of exposure to nonhuman species in the vicinity and ultimately to man. Generic data was used in the study to estimate the isotopic mix and weight of the ordnance. Key factors in the analysis included analyzing the physics of weapon impact on soil, chemical changes in material upon impact, and mechanisms of offsite transport (including atmospheric and overland transport). Non-standard exposure scenarios were investigated, including the possibility of offsite contaminant transport due to range grassfires. Two radiological assessment codes, MEPAS (Multi media Environmental Pollutant Assessment System) and RESRAD were used to help analyze the scenarios

Program of environmental radiological surveillance of the radioactive wastes storage center of Maquixco in the period January-December 1991

International Nuclear Information System (INIS)

Gaso P, M.I.

1991-12-01

The primary objective of all program of environmental radiological surveillance (PVRA), it is to follow the evolution of the radioactive content of the links of the chains that constitute the different ways of transfer of the radioactivity toward the man, with the purpose of making a realistic evaluation of the environmental impact produced by the installation under surveillance. In the CADER in Mexico, only accidents or escapes of radioactivity of slow evolution can be detected. At the moment the radioactive wastes in this installation are not treated. In this report the results obtained during the year 1991 are presented. (Author)

Radiological-dose assessments of atolls in the northern Marshall Islands

International Nuclear Information System (INIS)

Robison, W.L.

1983-04-01

The Marshall Islands in the Equatorial Pacific, specifically Enewetak and Bikini Atolls, were the site of US nuclear testing from 1946 through 1958. In 1978, the Northern Marshall Islands Radiological Survey was conducted to evaluate the radiological conditions of two islands and ten atolls downwind of the proving grounds. The survey included aerial external gamma measurements and collection of soil, terrestrial, and marine samples for radionuclide analysis to determine the radiological dose from all exposure pathways. The methods and models used to estimate doses to a population in an environment where natural processes have acted on the source-term radionuclides for nearly 30 y, data bases developed for the models, and results of the radiological dose analyses are described

Environmental Monitoring Plan for the Oak Ridge Reservation, 2012

Energy Technology Data Exchange (ETDEWEB)

Thompson, Sharon D. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

2012-10-01

The purpose of Oak Ridge Reservation (ORR) environmental surveillance is to characterize radiological and nonradiological conditions of the off-site environs and estimate public doses related to these conditions, confirm estimations of public dose based on effluent monitoring data, and, where appropriate, provide supplemental data to support compliance monitoring for applicable environmental regulations. This environmental monitoring plan (EMP) is intended to document the rationale, frequency, parameters, and analytical methods for the ORR environmental surveillance program and provides information on ORR site characteristics, environmental pathways, dose assessment methods, and quality management. ORR-wide environmental monitoring activities include a variety of media including air, surface water, vegetation, biota, and wildlife. In addition to these activities, site-specific effluent, groundwater, and best management monitoring programs are conducted at the Oak Ridge National Laboratory (ORNL), the Y-12 National Security Complex (Y-12), and the East Tennessee Technology Park (ETTP). This is revision 5.

Review of radiological problems of floating nuclear power plants

International Nuclear Information System (INIS)

Rodd, T.

1982-01-01

Radiological problems associated with floating nuclear power plants under both normal operation and accident conditions are discussed. In the latter case, aspects of both the airborne and liquid pathways are reviewed

Estimating environmental co-benefits of U.S. low-carbon pathways using an integrated assessment model with state-level resolution

Energy Technology Data Exchange (ETDEWEB)

Ou, Yang; Shi, Wenjing; Smith, Steven J.; Ledna, Catherine M.; West, J. Jason; Nolte, Christopher G.; Loughlin, Daniel H.

2018-04-01

There are many technological pathways that can lead to reduced carbon dioxide (CO₂) emissions. However, these pathways can have substantially different impacts on other environmental endpoints, such as air quality and energy-related water demand. This study uses an integrated assessment model with state-level resolution of the U.S. energy system to compare environmental impacts of alternative low-carbon pathways. One set of pathways emphasizes nuclear energy and carbon capture and storage (NUC/CCS), while another set emphasizes renewable energy (RE). These are compared with pathways in which all technologies are available. Air pollutant emissions, mortality costs attributable to particulate matter less than 2.5 microns in diameter (PM2.5), and energy-related water demands are evaluated for 50% and 80% CO₂ reduction targets in the U.S. in 2050. The RE low-carbon pathways require less water withdrawal and consumption than the NUC/CCS pathways because of the large cooling demands of nuclear power and CCS. However, the NUC/CCS low-carbon pathways produce greater health benefits, mainly because the NUC/CCS assumptions result in less primary PM2.5 emissions from residential wood combustion. Environmental co-benefits differ among states because of factors such as existing technology stock, resource availability, and environmental and energy policies. An important finding is that biomass in the building sector can offset some of the health co-benefits of the low-carbon pathways even though it plays only a minor role in reducing CO₂ emissions.

Environmental impacts of radiological consequences during the anticipated transients without scram (ATWS) events in nuclear power reactors

International Nuclear Information System (INIS)

El-Kafas, A.A.

2011-01-01

Anticipated transients without scram (ATWS), is one of the (worst case) accidents could happen if the system that provides a highly reliable means of shutting down the reactor (scram system )fails to work during a reactor event (anticipated transient).It has two general characteristics: (1) Initiation by a transient anticipated to occur one or more times in the life of reactor and ,(2) Assumed to proceed without scram.The types of events considered are those used for designing the plant .The evaluation of the radiological consequences during the assessment of the nuclear events,especially ATWS in nuclear power reactors, is very essential for environmental studies and public safety. In this paper, the root cases for nuclear events and dose calculation are presented. Scenario of accident sequences together with radiological impacts is illustrated for loss of coolant accident (LOCA) for a typical pressurized water reactor nuclear power plant. Recommendations for mitigating or preventing the release of radiation and high radioactive materials to environment are presented.

Estimating environmental co-benefits of U.S. low-carbon pathways using the GCAM-USA integrated assessment model

Data.gov (United States)

U.S. Environmental Protection Agency — There are many technological pathways that can lead to reduced carbon dioxide (CO2) emissions. However, these pathways can have substantially different impacts on...

Radiological dose to man through the marine pathway from reactor operations at Humboldt Bay, California

International Nuclear Information System (INIS)

Noshkin, V.E.; Robison, W.L.; Harrison, F.L.

1976-01-01

Source-strength measurements and environmental samples taken at the Humboldt Bay Nuclear Reactor site near Eureka, California, since mid-1971 were used to evaluate the potential dose to man resulting from an aquatic release of radioactivity from the reactor. In this report, we provide an evaluation of individual and population dose through the marine pathways during 1972 and 1973 computed by the methods recommended by the U.S. Nuclear Regulatory Commission

Angra nuclear plant - environmental control program

International Nuclear Information System (INIS)

Kircher, E.; Cruz, E.S. da

1989-01-01

The pre-operational studies, that were elaborated before the beginning of Angra I Power Plant operation, are described in particular the environmental radiological safety area till the fuel loading in the core reactor. Several aspects are included, as socio-economic survey, seismological analysis, Meteorological Program, marine biology, water cooling system, exposure measures of natural radiation, marine sediments characterization in the effluent dispersion area and Environmental Radiological Monitoring Program. The main environmental programs developed for the operational phase of the Angra I Plant are also presented, citing some considerations about the Meteorological Program, Marine Biology Control Program, Temperature and Chlorine Control in Piraquara de Fora Bay, Radiological Environmental Monitoring Program, Sanitary Effluent Control Program and Radiological Emergency Program. (C.G.C.). 2 refs

F-Area Seepage Basins: Environmental information document

International Nuclear Information System (INIS)

Corbo, P.; Killian, T.H.; Kolb, N.L.; Marine, I.W.

1986-12-01

This document provides environmental information on postulated closure options for the F-Area Seepage Basins at the Savannah River Plant and was developed as background technical documentation for the Department of Energy's proposed Environmental Impact Statement (EIS) on waste management activities for groundwater protection at the plant. The results of groundwater and atmospheric pathway analyses, accident analysis, and other environmental assessments discussed in this document are based upon a conservative analysis of all foreseeable scenarios as defined by the National Environmental Policy Act (40 CFR 1502.22). The scenarios do not necessarily represent actual environmental conditions. This document is not meant to represent or be used as a regulatory closure plan or other regulatory sufficient document. Technical assistance in the environmental analyses of waste site closures was provided by Clemson University; GeoTrans, Inc.; JBF Associates, Inc.; S.S. Papadopulos and Associates Inc.; Radiological Assessments Corporation; Rogers and Associates Engineering Corporation; Science Applications International Corporation; C.B. Shedrow Environmental Consultants, Inc.; Exploration Software; and Verbatim Typing and Editing

Radiological impacts of uranium recovery in the phosphate industry

International Nuclear Information System (INIS)

Ryan, M.T.

1981-01-01

This article characterizes the occupational and public radiological health impacts associated with phosphate mining and milling. These impacts are related to the phosphate industry's uranium production potential and are compared with those associated with conventional uranium mining and milling. The radiological impacts resulting from occupational and nonoccupational exposures are assessed. Occupational exposures in phosphate facilities are compared to background exposures and radiological population dose assessments, which characterize important radionuclides and exposure pathways. The following conclusions were reached: (1) public consequences of phosphate mining will occur whether or not uranium is recovered as a by-product, (2) radiological consequences of phosphate mining may be comparable to those associated with uranium mining and milling per unit uranium production, (3) radiological impacts via surface waterways and crops fertilized with uranium-bearing phosphates are of minor consequence, and (4) major radiological public health problems associated with phosphate mining are related to radon and radon progeny exposures in structures built on reclaimed lands or with phosphate mining residues, although the magnitudes of these impacts are difficult to evaluate with current data

Technological and operational structure of the National Automatic Network for Environmental Radiological Monitoring (RENAMORA); Estructura tecnologica y operativa de la Red Nacional Automatica de Monitoreo Radiologico Ambiental RENAMORA

Energy Technology Data Exchange (ETDEWEB)

Martinez G, E.; Lopez G, M.; Aguirre G, J.; Fabian O, R.; Hernandez A, Y., E-mail: elias.martinez@cnsns.gob.mx [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Barragan 779, Col. Narvarte, 03020 Ciudad de Mexico (Mexico)

2015-09-15

The Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) in Mexico is a decentralized body, under the Secretaria de Energia whose main mission is to ensure that activities involving nuclear and radioactive materials as well as ionizing radiation sources are carried out with maximum security, considering the current technological developments. In order to monitor the levels of environmental radiation to which the population is exposed, the CNSNS has established a series of radiological monitoring programs that allow characterize the environmental radiation levels in each zone or region in the country; to identify the occurrence of natural or artificial radiological events, such as nuclear tests and accidents in radioactive or nuclear facilities. The National Automatic Network for Environmental Radiological Monitoring (RENAMORA) project was initiated with the support of the IAEA through MEX9/049 project and its purpose is to have a network of instruments that automatically and in real time, transmit information of the gamma radiological environmental status of the national territory and changes occurring in it. This network provides data such as the speed of ambient dose equivalent, temperature and humidity in different regions of the country. The network is composed of 92 stations that are distributed throughout the national territory. The structure of the stations has evolved since its inception, now allowing detection tasks, data transmission and managing them remotely from the main server, which is located in the CNSNS, which is performed a statistical dose for each monitoring station. Each monitoring station is formed in its current structure by a probe detection of gamma radiation, a communication module and associated electronics, a mini Web server DataGATE, a cellular modem and an interface converter. (Author)

Principles and issues in radiological ecological risk assessment.

Science.gov (United States)

Jones, Daniel; Domotor, Stephen; Higley, Kathryn; Kocher, David; Bilyard, Gordon

2003-01-01

This paper provides a bridge between the fields of ecological risk assessment (ERA) and radioecology by presenting key biota dose assessment issues identified in the US Department of Energy's Graded Approach for Evaluating Radiation Doses to Aquatic and Terrestrial Biota in a manner consistent with the US Environmental Protection Agency's framework for ERA. Current radiological ERA methods and data are intended for use in protecting natural populations of biota, rather than individual members of a population. Potentially susceptible receptors include vertebrates and terrestrial plants. One must ensure that all media, radionuclides (including short-lived radioactive decay products), types of radiations (i.e., alpha particles, electrons, and photons), and pathways (i.e., internal and external contamination) are combined in each exposure scenario. The relative biological effectiveness of alpha particles with respect to deterministic effects must also be considered. Expected safe levels of exposure are available for the protection of natural populations of aquatic biota (10 mGy d(-1)) and terrestrial plants (10 mGy d(-1)) and animals (1 mGy d(-1)) and are appropriate for use in all radiological ERA tiers, provided that appropriate exposure assumptions are used. Caution must be exercised (and a thorough justification provided) if more restrictive limits are selected, to ensure that the supporting data are of high quality, reproducible, and clearly relevant to the protection of natural populations.

Principles and issues in radiological ecological risk assessment

International Nuclear Information System (INIS)

Jones, Daniel; Domotor, Stephen; Higley Kathryn; Kocher, David; Bilyard, Gordon

2003-01-01

This paper provides a bridge between the fields of ecological risk coefficients.variability o published particle-solution distribution coeffiissues identified in the US Department of Energy's Graded Approach fo Evaluating Radiation Doses to Aquatic and Terrestrial Biota in a manner consistent with the US Environmental Protection Agency's framework for ERA. Current radiological ERA methods and data are intended for use in protecting natural populations of biota, rather than individual members of a population. Potentially susceptible receptors include vertebrates and terrestrial plants One must ensure that all media, radionuclides (including short-lived radioactive decay products), types of radiations (i.e., alpha particles electrons, and photons), and pathways (i.e., internal and external contamination) are combined in each exposure scenario. The relative biological effectiveness of alpha particles with respect to deterministic effects must also be considered. Expected safe levels of exposure are available for the protection of natural populations of aquatic biota (10 mGy d -1 ) and terrestrial plants (10 mGy d -1 ) and animals (1 mGy d -1 ) and are appropriate for use in all radiological ERA tiers, provided that appropriate exposure assumptions are used. Caution must be exercised (and a thorough justification provided) if more restrictive limits are selected, to ensure that the supporting data are of high quality, reproducible, and clearly relevant to the protection of natural populations

Development of radiological profiles for U.S. Department of Energy low-level mixed wastes

International Nuclear Information System (INIS)

Wilkins, B.D.; Meshkov, N.K.; Dolak, D.A.; Wang, Y.Y.

1995-01-01

Radiological profiles have been developed by Argonne National Laboratory for low-level mixed wastes (LLMWs) that are under the management of the US Department of Energy (DOE). These profiles have been used in the Office of Environmental Management Programmatic Environmental Impact Statement (EM PEIS) to support the analysis of environmental and health risks associated with the various waste management strategies. The radiological characterization of DOE LLMWs is generally inadequate and has made it difficult to develop a site- and waste-stream-dependent radiological profile for LLMWs. On the basis of the operational history of the DOE sites, a simple model was developed to generate site-dependent and waste-stream-independent radiological profiles for LLMWs. This paper briefly discusses the assumptions used in this model and the uncertainties in the results

Radiological emergency: Malaysian preparedness and response

International Nuclear Information System (INIS)

Yusof, M. A. W.; Ali, H. M.

2011-01-01

Planning and preparation in advance for radiological emergencies can help to minimise potential public health and environmental threats if and when an actual emergency occurs. During the planning process, emergency response organisations think through how they would respond to each type of incident and the resources that will be needed. In Malaysia, planning, preparation for and response to radiological emergencies involve many parties. In the event of a radiological emergency and if it is considered a disaster, the National Security Council, the Atomic Energy Licensing Board and the Malaysian Nuclear Agency (Nuclear Malaysia) will work together with other federal agencies, state and local governments, first responders and international organisations to monitor the situation, contain the release, and clean up the contaminated site. Throughout the response, these agencies use their protective action guidelines. This paper discusses Malaysian preparedness for, and response to, any potential radiological emergency. (authors)

The Role of Radiological Protection in Sweden's National Environmental quality Objectives

International Nuclear Information System (INIS)

Hubbard, L.; Mjones, L.; Holm, E.

2004-01-01

In 1999, the Swedish Parliament adopted fifteen environmental quality objectives, defining the quality of Sweden's environment and of its natural and cultural resources that will insure sustainable growth. In 2001, the government proposed interim targets for each objective, specifying the direction and time scale of the proposed actions. These objectives give Sweden a unique opportunity to define, quantify and achieve an ecologically sustainable environment. One of the national objectives, A Safe Radiation Environment, targets both ionising and non-ionising radiation and states, human health and biological diversity must be protected against the harmful effects of radiation in the environment. The Swedish Radiation Protection Authority (SSI) has the responsibility for formulating and achieving the interim targets for this objective. The targets presently focus on controlling radioactive emissions, limiting exposures to ultraviolet radiation and defining the risks from exposure to electromagnetic fields. Part of SSI's responsibility for the environmental quality objective is to develop a system for monitoring and quantifying progress towards each interim target. Sweden's National Board of Housing, Building and Planning (NBHBP) is responsible for another of the national objectives, A Good Built- Environment. As part of this objective, a special interim target for the indoor environment was approved by Parliament in 2002, which includes a specification for human exposure to radon in indoor air. It states: radon concentrations should be lower than 200 Bq/m3 in schools and pre-schools by the year 2010, and below 200 Bq/m3 in homes by 2020. This substantially raises the level of ambition regarding reducing exposure to indoor radon. The aim of this paper is to briefly summarize the role of radiological protection in Sweden's environmental quality objectives. (Author) 3 refs

Environmental aspects of tritium

International Nuclear Information System (INIS)

Quisenberry, D.R.

1979-01-01

The potential radiological implications of environmental tritium releases must be determined in order to develop a programme for dealing with the tritium inventory predicted for the nuclear power industry which, though still in its infancy, produces tritium in megacurie quantities annually. Should the development of fusion power generation become a reality, it will create a potential source for large releases of tritium, much of it in the gaseous state. At present about 90% of the tritium produced enters the environment through gaseous and liquid effluents and is deposited in the hydrosphere as tritiated water. Tritium can be assimilated by plants and animals and organically bound, regardless of the exposure pathway. However, there appears to be no concentration factor relative to hydrogen at any level of food chains analysed to date. The body burden, for man, is dependent on the exposure pathway and tissue-bound fractions are primarily the result of organically bound tritium in food. (author)

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)

Radiological manifestations of melioidosis

International Nuclear Information System (INIS)

Lim, K.S.; Chong, V.H.

2010-01-01

Melioidosis is a serious infection that is associated with high mortality. It is due to a Gram-negative bacterium, Burkholderia pseudomallei which is an environmental saprophyte found in wet soils. Melioidosis is endemic to northern Australia and the Southeast Asia. However, there is now increasing number of reports of imported cases to regions where this infection has not been previously encountered. Almost any organ can be affected. Like many other conditions, radiological imaging is an integral part of the diagnostic workup of melioidosis. Awareness of the various radiological manifestations can help direct appropriate investigations to achieve early diagnosis and the initiation of appropriate treatment. Generally, there are no known characteristic features on imaging that can specifically differentiate melioidosis from other infections. However, the 'honeycomb' appearance has been described to be characteristic for large melioidosis liver abscesses. Simultaneous involvement of various organs is also characteristics. To date, there are few data available on the radiological manifestations of melioidosis. The present pictorial essay describes melioidosis affecting the various organs.

Educational treasures in Radiology: The Radiology Olympics - striving for gold in Radiology education

OpenAIRE

Talanow, Roland

2010-01-01

This article focuses on Radiology Olympics (www.RadiologyOlympics.com) - a collaboration with the international Radiology community for Radiology education, Radiolopolis (www.Radiolopolis.com). The Radiology Olympics honour the movers and shakers in Radiology education and offer an easy to use platform for educating medical professionals based on Radiology cases.

Radiology

International Nuclear Information System (INIS)

Bigot, J.M.; Moreau, J.F.; Nahum, H.; Bellet, M.

1990-01-01

The 17th International Congress of Radiology was conducted in two separate scientific sessions, one for radiodiagnosis and one for radiation oncology. Topics covered are: Radiobiology -radioprotection; imaging and data processing; contrast media; MRI; nuclear medicine; radiology and disasters; radiology of tropical diseases; cardiovascular radiology; interventional radiology; imaging of trauma; imaging of chest, gastro-intestinal tract, breast and genito-urinary tract; imaging in gynecology;imaging in oncology; bone and joint radiology; head and neck-radiology; neuro-radiology. (H.W.). refs.; fig.; tabs

ERC Radiological Glovebag Program

International Nuclear Information System (INIS)

Nellesen, A.L.

1997-07-01

This document establishes the requirements and responsibilities for the standardized methods for installation, use, and dismantlement of glovebags within the Hanford Site Environmental Contractor Radiological Glovebag Program. This document addresses the following topics: Containment selection and fabrication, Glovebag fabrication, Containment installation and inspection, General glovebag containment work practices, Emergency situations, and Containment removal

Environmental monitoring radiological programs for the nuclear centre and the low level radioactive waste facility in Mexico

International Nuclear Information System (INIS)

Quintero, E.; Cervantes, L.; Rojas, V.

2006-01-01

The National Institute of Nuclear Research of Mexico (ININ) has its Laboratory of Environmental Radiological Monitoring, (LVRA), to assure the critical population and the environment they are not exposed to radiation doses greater than the limits established by the national and international legislation, this laboratory carries out environmental monitoring radiological programs the Nuclear Centre and its surroundings and the Low Level Radioactive Waste Facility (CADER) and its around. In order to carry out these programs the LVRA has rooms for evaporation, drying, grinding, ashing of environmental and food samples, and a laboratory for gamma ray spectrometry, liquid scintillation, alpha-beta gross counting and computer room. Since the year 2000 the (ININ) has tried to implant the quality system ISO 9001:2000 including a its (LVRA). This quality system includes: a Plan of Quality, Quality Manual, programs of technical and administrative document elaboration, technical and administrative procedures, technical and administrative qualification programmes for the laboratory staff, maintenance and calibration programs for measurement systems and finally participation in national and international exercises of intercomparison. The ININ counts with the management of quality assurance to verify these programs, in addition, our Nuclear Regulatory Commission (CNSNS) carries out periodic audits to authorize the of use and handling of radioactive and nuclear material licenses of these facilities. In this work we presented the advances and difficulties found in the implantation of the quality system, also we present the benefits obtained with uses of this system, the samples analyses results, and the calculation of the annual dose to the critical population for the last five years. In addition, we presented the calculation the radionuclides concentration tendencies in different sample types, according to our (CNSNS) requirements. In the same way the results of the calibrations

Radiological and Environmental Research Division: ecology. Annual report, January-December 1982

International Nuclear Information System (INIS)

1983-09-01

This is the annual report of the Radiological and Environmental Division of the Argonne National Laboratory for 1982. Studies of the effects of ozone on crop growth and yield have been carried out by the Terrestrial Ecology Group for winter wheat and for sorghum. The Microcosms for Acid Rain Studies (MARS) facility was completed in the early summer. Controlled investigations of plant and soil responses in acid rain were initiated with crop plants grown in two different midwestern soil types. The Transuranics Group has found that the solubility and adsorptive behavior of plutonium previously observed at fallout concentrations in natural waters (approx. 10 -16 to 10 -18 M) is applicable at plutonium concentrations as high as 10 -8 M. The Lake Michigan eutrophication model has been adapted to operation in a Monte Carlo mode. Simulations based on yearly phosphorus loadings and winter conditions were selected at random from prescribed probability distributions and used to estimate some of the uncertainties associated with model forecasts of Lake Michigan water quality

Radiological environmental monitoring with LiF-700-H dosemeters

International Nuclear Information System (INIS)

Scarnichia, E.; Levanon, I.; Andres, P.; Miani, C.; Ramirez, S.

2011-10-01

Since 2008 a radiological environmental monitoring with LiF-700-H has been carried out as a result of increasing the Ra-6 research reactor core power. The information obtained is used to evaluate and to quantify analytically the air kerma rate, the fading and the associated uncertainty by developing software tools (deconvolution and uncertainty algorithms). LiF-700-H dosemeters were chosen because of their high sensitivity to low air kerma rates. They show a very good stability and a negligible fading for two-month working periods. The air kerma rate detection limit (based on the 3σ criterion) during these working periods is about 0.4 n Gy/h. Air kerma rates of about 70 n Gy/h are measured with this detection limit. Following the Nist guidelines, an algorithm was developed in order to find the associated uncertainty. It considers several aspects, such as the source activity decay, distance source-dosemeter during the calibration procedure, irradiation time, calibration factor, dosemeter readout, dosemeter sensitivity, TLD reader stability and fading. The associated uncertainty is found to be about 25% for a 95% confidence interval (k = 2.025), which can be considered acceptable when taking into account the very low air kerma rates estimated. The LiF-700-H response to different energies and its relationship with climate changes over the calendar year are planned as future tasks. (Author)

618-11 Burial Ground USRADS radiological surveys

International Nuclear Information System (INIS)

Wendling, M.A.

1994-01-01

This report summarizes and documents the results of the radiological surveys conducted from February 4 through February 10, 1993 over the 618-11 Burial Ground, Hanford Site, Richland, Washington. In addition, this report explains the survey methodology using the Ultrasonic Ranging and Data System (USRADS). The 618-11 Burial Ground radiological survey field task consisted of two activities: characterization of the specific background conditions and the radiological survey of the area. The radiological survey of the 618-11 Burial Ground, along with the background study, were conducted by Site Investigative Surveys Environmental Restoration Health Physics Organization of the Westinghouse Hanford Company. The survey methodology was based on utilization of the Ultrasonic Ranging and Data System (USRADS) for automated recording of the gross gamma radiation levels at or near six (6) inches and at three (3) feet from the surface soil

Radiological control criteria for materials considered for recycle and reuse

International Nuclear Information System (INIS)

Kennedy, W.E. Jr.; Hill, R.L.; Aaberg, R.L.; Wallo, A. III

1994-11-01

Pacific Northwest Laboratory (PNL) is conducting technical analyses to support the US Department of Energy (DOE), Office of Environmental Guidance, Air, Water, and Radiation Division (DOE/EH-232) in developing radiological control criteria for recycling or reuse of metals or equipment containing residual radioactive contamination from DOE operations. The criteria, framed as acceptable concentrations for release of materials for recycling or reuse, are risk-based and were developed through analysis of generic radiation exposure scenarios and pathways. The analysis includes evaluation of relevant radionuclides, potential mechanisms of exposure, and non-health-related impacts of residual radioactivity on electronics and film. The analysis considers 42 key radionuclides that DOE operations are known to generate and that may be contained in recycled or reused metals or equipment. Preliminary results are compared with similar results reported by the International Atomic Energy Agency, by radionuclide grouping

Operational environmental monitoring plan for the waste isolation pilot plant

International Nuclear Information System (INIS)

Mercer, D.D.; Baker, P.L.; Cockman, J.S.; Fischer, N.T.; Flynn, D.T.; Harvill, J.P.; Knudtsen, K.L.; Louderbough, E.T.

1989-01-01

This plan defines the scope and extent of the WIPP effluent and environmental monitoring programs during the facility's operational life. It also discusses the quality assurance/quality control programs which ensure that samples collected and the resulting analytical data are representative of actual conditions at the WIPP site. This plan provides a comprehensive description of environmental activities at WIPP, including: a summary of environmental program information, including an update of the status of environmental permits and compliance activities; a description of the WIPP project and its mission; a description of the local environment, including demographics; a summary of applicable standards and regulatory requirements and brief discussions of potential exposure pathways, routine and accidental releases, and their consequences; a summary of the preoperational environmental monitoring and assessment activities and responses to the requirements (Appendix A) and guidelines presented in the ''Radiological Effluent Monitoring and Environmental Surveillance for US DOE Operations.'' 166 refs., 28 figs., 27 tabs

Using the model release ARTM associated with resources for simulation geoprocessing radiological environmental impact of atmospheric emissions from a research reactor; Utilizacao do modelo de dispersao ARTM associado a recursos de geoprocessamento para simulacao do impacto ambiental radiologico de emissoes atmosfericas de um reator de pesquisa

Energy Technology Data Exchange (ETDEWEB)

Alves, Simone Fonseca

2013-08-01

The knowledge of the dispersion of radionuclides emissions into the atmosphere arising from a nuclear reactor, in normal operation, is an important step in the process of the nuclear and environmental assessment study. These processes require an assessment study of the radiological environmental impact. However, to estimate this impact a simulation of the transport mechanisms and deposition of pollutants released into the atmosphere is required. The present study aimed at the application of the dispersion model ARTM (Atmospheric Radionuclide Transport Model), together with the powerful tools of the GIS (Geographic Information System) for the environmental impact assessment of a radiological nuclear reactor under typically routine and conditions. Therefore some important information from the national project for a research reactor known as Brazilian Multipurpose Reactor (RMB) was considered. The information of the atmospheric emissions of the reactor, needed for the simulation of this project, was based on data of the Open Pool Australian Light Water (OPAL).Other important data that had to be collected and analyzed were the source term, the topography, the meteorology and the environmental data. The radionuclides analyzed as pollutants were {sup 41}Ar; {sup 140}Ba; {sup 51}Cr; {sup 137}Cs; {sup 131}I; {sup 133}I; {sup 85m} Kr; {sup 87}Kr; {sup 88}Kr; {sup 140}La; {sup 133}Xe; {sup 135}Xe; {sup 3}H; {sup 90}Sr. The model was run for two chronological scenarios according to their meteorological data for the years 2009 and 2010, respectively. The adoption of GIS techniques was relevant in planning, data preprocessing and in the post-processing of results as well. After pre-processing, the input data were processed by the ARTM dispersion model. Maps, charts, and tables were then produced and evaluated. According to the simulated and evaluated scenarios it could be concluded that exposure pathways that mostly contributed to the dose for individual public were {sup 41}Ar

Conditions of radiological protection in the health unities

International Nuclear Information System (INIS)

Sa, L.R.B.S.; Neto, A.T.; Pires, A.; Azevedo, H.F.; Boasquevisque, E.M.

1987-01-01

The objective of this study was explained which conditions is practiced for occupational and environmental radiological protection. Fifteen hospitables and ambulatories services, pertaining to the public system are studies, verifying that the professional group that are preoccupied with the radioprotection conditions are the assistants services and technician. The common knowledge about Basic Standards of Radiological Protection was also observed, of which is rather precarious. (C.G.C.) [pt

Addressing the coming radiology crisis-the Society for Computer Applications in Radiology transforming the radiological interpretation process (TRIP) initiative.

Science.gov (United States)

Andriole, Katherine P; Morin, Richard L; Arenson, Ronald L; Carrino, John A; Erickson, Bradley J; Horii, Steven C; Piraino, David W; Reiner, Bruce I; Seibert, J Anthony; Siegel, Eliot

2004-12-01

The Society for Computer Applications in Radiology (SCAR) Transforming the Radiological Interpretation Process (TRIP) Initiative aims to spearhead research, education, and discovery of innovative solutions to address the problem of information and image data overload. The initiative will foster interdisciplinary research on technological, environmental and human factors to better manage and exploit the massive amounts of data. TRIP will focus on the following basic objectives: improving the efficiency of interpretation of large data sets, improving the timeliness and effectiveness of communication, and decreasing medical errors. The ultimate goal of the initiative is to improve the quality and safety of patient care. Interdisciplinary research into several broad areas will be necessary to make progress in managing the ever-increasing volume of data. The six concepts involved are human perception, image processing and computer-aided detection (CAD), visualization, navigation and usability, databases and integration, and evaluation and validation of methods and performance. The result of this transformation will affect several key processes in radiology, including image interpretation; communication of imaging results; workflow and efficiency within the health care enterprise; diagnostic accuracy and a reduction in medical errors; and, ultimately, the overall quality of care.

Annual report of national institute of radiological sciences

International Nuclear Information System (INIS)

1993-07-01

This annual report is a compilation of the research activities and achievement in the National Institute of Radiological Sciences (NIRS) in Japan during the fiscal year 1992 (from April 1992 through March 1993). Construction of the Heavy Ion Medical Accelerator in Chiba (HIMAC) has reached semi-final stage. The research covers a wide range of radiological sciences from molecular biology to environmental studies and medicine including engineering for heavy ion therapy of cancer. Topics consists of physics, chemistry, biomedical science, clinical research, and environmental sciences, covering a total of 84 titles. A list of publications by staff members, activities of research divisions, and organization chart of the NIRS are given in Appendix. (J.P.N.) 78 refs

Guide for radiological characterization and measurements for decommissioning of US Department of Energy surplus facilities

International Nuclear Information System (INIS)

Denahm, D.H.; Barnes, M.G.; Jaquish, R.E.; Corley, J.P.; Gilbert, R.O.; Hoenes, G.R.; Jamison, J.D.; McMurray, B.J.; Watson, E.C.

1983-08-01

This Guide describes the elements of radiological characterization at DOE excess facilities in preparation for, during, and subsequent to decommissioning operations. It is the intent of this Guide and accompanying appendices to provide the reader (user) with sufficient information to carry out that task with a minimum of confusion and to provide a uniform basis for evaluating site conditions and verifying that decommissioning operations are conducted according to a specific plan. Some areas of particular interest in this Guide are: the need to involve appropriate staff from the affected states in the early planning stages of decommissioning; the need for and suggested methods of radiological site characterization to complete a decommissioning project, including: historical surveys, environmental pathway analyses, statistical sampling design, and choosing appropriate instrumentation and measurements; the need for and emphasis on quality assurance, documentation and records retention; the establishment of a Design Objective approach to applying site-specific contamination limits based on the ALARA philosophy; the establishment of a ''de minimis'' or minimum dose level of concern for decommissioning operations based on existing standards, experience and ALARA considerations

RASCAL [Radiological Assessment System for Consequence AnaLysis]: A screening model for estimating doses from radiological accidents

International Nuclear Information System (INIS)

Sjoreen, A.L.; Athey, G.F.; Sakenas, C.A.; McKenna, T.J.

1988-01-01

The Radiological Assessment System for Consequence AnaLysis (RASCAL) is a new MS-DOS-based dose assessment model which has been written for the US Nuclear Regulatory Commission for use during response to radiological emergencies. RASCAL is designed to provide crude estimates of the effects of an accident while the accident is in progress and only limited information is available. It has been designed to be very simple to use and to run quickly. RASCAL is unique in that it estimates the source term based on fundamental plant conditions and does not rely solely on release rate estimation (e.g., Ci/sec of I-131). Therefore, it can estimate consequences of accidents involving unmonitored pathways or projected failures. RASCAL will replace the older model, IRDAM. 6 refs

Environmental Report 1996

International Nuclear Information System (INIS)

Harrach, R.J.; Gallegos, G.M.; Tate, P.J.

1997-01-01

This summary provides an overview of LLNL's environmental activities in 1996, including radiological and nonradiological surveillance, effluent and compliance monitoring, remediation, assessment of radiological releases and doses, and determination of the impact of LLNL operations on the environment and public health

The development of an environmental protection programme for the population based on concepts and standards inspired by radiological protection

International Nuclear Information System (INIS)

Recht, P.

1977-01-01

Following the United Nations Conference in Stockholm, 1972, on the protection of the environment a certain number of principles and methods have been put forward to national authorities which put into effect environmental protection programmes. Several of these principles have been taken directly from and inspired by the field of application of radiological protection; it is not without interest to draw comparisons between those which have been conceived and applied in health physics for the prevention of a radioactivity risk as it applies to the population, and those which already exist or which are envisaged vis-a-vis the risks from non radioactive pollutants. It is opportune to remember that the ICRP publications, in particular those published in and after 1958, included recommendations on radiological protection, and that these recommendations laid down the bases for both the theoretical steps and the practical methodology of which the main components are still in existence today; a remarkable achievement which merits emphasis. The ICRP recommendations included in publication 1 and more particularly publications 7, 9 and 22 introduced the basic concepts of a health physics policy which can be recognized as having been beneficial for the protection of man and his environment and which can be utilized as a basis for consideration, if not action, as it concerns the non-radioactive environmental pollutants [fr

Radiological Impacts Assessment during Normal Decommissioning Operation for EU-APR

Energy Technology Data Exchange (ETDEWEB)

Hwang, Do Hyun; Lee, Keun Sung [KHNP CRI, Daejeon (Korea, Republic of); Lee, ChongHui [KEPCO Engineering and Construction, Gimcheon (Korea, Republic of)

2016-10-15

In this paper, radiological impacts on human beings during normal execution of the decommissioning operations from the current standard design of EU-APR which has been modified and improved from its original design of APR1400 to comply with EUR, are evaluated. Decommissioning is the final phase in the life cycle of a nuclear installation, covering all activities from shutdown and removal of fissile material to environmental restoration of the site. According to article 5.4 specified in chapter 2.20 of European Utility Requirements (EUR), all relevant radiological impacts on human being should be considered during the environmental assessment of decommissioning, including external exposure from direct radiation of plant and other radiation sources, and internal exposure due to inhalation and ingestion. In this paper, radiological impacts on human beings during normal circumstances of the decommissioning operation were evaluated from the current standard design of EU-APR based on the simple transport model and practical generic methodology for assessing the radiological impact provided by IAEA. The results of dose assessment fulfilled the dose limit for all scenarios.

GENII [Generation II]: The Hanford Environmental Radiation Dosimetry Software System: Volume 3, Code maintenance manual: Hanford Environmental Dosimetry Upgrade Project

International Nuclear Information System (INIS)

Napier, B.A.; Peloquin, R.A.; Strenge, D.L.; Ramsdell, J.V.

1988-09-01

The Hanford Environmental Dosimetry Upgrade Project was undertaken to incorporate the internal dosimetry models recommended by the International Commission on Radiological Protection (ICRP) in updated versions of the environmental pathway analysis models used at Hanford. The resulting second generation of Hanford environmental dosimetry computer codes is compiled in the Hanford Environmental Dosimetry System (Generation II, or GENII). This coupled system of computer codes is intended for analysis of environmental contamination resulting from acute or chronic releases to, or initial contamination of, air, water, or soil, on through the calculation of radiation doses to individuals or populations. GENII is described in three volumes of documentation. This volume is a Code Maintenance Manual for the serious user, including code logic diagrams, global dictionary, worksheets to assist with hand calculations, and listings of the code and its associated data libraries. The first volume describes the theoretical considerations of the system. The second volume is a Users' Manual, providing code structure, users' instructions, required system configurations, and QA-related topics. 7 figs., 5 tabs

GENII (Generation II): The Hanford Environmental Radiation Dosimetry Software System: Volume 3, Code maintenance manual: Hanford Environmental Dosimetry Upgrade Project

Energy Technology Data Exchange (ETDEWEB)

Napier, B.A.; Peloquin, R.A.; Strenge, D.L.; Ramsdell, J.V.

1988-09-01

The Hanford Environmental Dosimetry Upgrade Project was undertaken to incorporate the internal dosimetry models recommended by the International Commission on Radiological Protection (ICRP) in updated versions of the environmental pathway analysis models used at Hanford. The resulting second generation of Hanford environmental dosimetry computer codes is compiled in the Hanford Environmental Dosimetry System (Generation II, or GENII). This coupled system of computer codes is intended for analysis of environmental contamination resulting from acute or chronic releases to, or initial contamination of, air, water, or soil, on through the calculation of radiation doses to individuals or populations. GENII is described in three volumes of documentation. This volume is a Code Maintenance Manual for the serious user, including code logic diagrams, global dictionary, worksheets to assist with hand calculations, and listings of the code and its associated data libraries. The first volume describes the theoretical considerations of the system. The second volume is a Users' Manual, providing code structure, users' instructions, required system configurations, and QA-related topics. 7 figs., 5 tabs.

Application of geographic information system for radiologic emergency response

International Nuclear Information System (INIS)

Best, R.G.; Doyle, J.F.; Mueller, P.G.

1998-01-01

Comprehensive and timely radiological, cultural, and environmental data are required in order to make informed decisions during a radiological emergency. Within the Federal Radiological Monitoring and Assessment Center (FRMAC), there is a continuing effort to improve the data management and communication process. The most recent addition to this essential function has been the development of the Field Analysis System for Emergency Response (FASER). It is an integrated system with compatible digital image processing and Geographic Information System (GIS) capabilities. FASER is configured with commercially available off-the-shelf hardware and software components. To demonstrate the potential of the FASER system for radiological emergency response, the system has been utilized in interagency FRMAC exercises to analyze the available spatial data to help determine the impact of a hypothetical radiological release and to develop mitigation plans. (R.P.)

Environmental Pathway Models-Ground-Water Modeling in Support of Remedial Decision Making at Sites Contaminated with Radioactive Material

Science.gov (United States)

The Joint Interagency Environmental Pathway Modeling Working Group wrote this report to promote appropriate and consistent use of mathematical environmental models in the remediation and restoration of sites contaminated by radioactive substances.

Compilation of historical radiological data collected in the vicinity of the WIPP site

International Nuclear Information System (INIS)

Bradshaw, P.L.; Louderbough, E.T.

1987-01-01

The Radiological Baseline Program (RBP) at the Waste Isolation Pilot Plant (WIPP) has been implemented to characterize the radiological conditions at the site prior to receipt of radioactive wastes. Because southeastern New Mexico was the site of an underground nuclear test in 1961, various sampling programs have intermittently monitored background and elevated radiation levels in the vicinity of the WIPP. In addition, radiological characterization of the site region was performed during the 1970's in support of the WIPP Environmental Impact Statement. The historical data are drawn primarily from monitoring activities of the US Public Health Service (PHS), the Environmental Protection Agency (EPA), US Geological Survey (USGS) and Sandia National Laboratories, Albuquerque (SNLA). Information on air and water quality, meat, milk, biota and vegetation is included in the report. This survey is intended to provide a source of reference for historical data on radiological conditions in the vicinity of the WIPP site prior to the establishment of a systematic Radiological Baseline Program. 31 refs., 1 fig

Techniques and management strategies for environmental restoration and their ecological consequences

International Nuclear Information System (INIS)

Gutierrez, J.; Vazquez, C.; Meckbach, R.; Wilkins, B.; Rafferty, B.; Holm, E.; Badie, M.; Burton, O.

2000-01-01

The intervention is one of the targeted situations of concern for radiological protection. One of the aspects of the intervention deals with the environmental restoration. In fact, the emergency measures taken immediately or shortly after an accident, in order to avoid unnecessary increases of radiological risks, shoul not be prolonged for long periods because of their elevated cost for society. Hence restoration of the contaminated areas could be needed and therefore researches are required for theevelopmet of obust d optimised restoration strategies. The experimental work carried out after the Chernobyl accident provided large amount of information about the environmental behaviour of radionuclides and their exposure pathways to man. Additionally, some advance on the setting up of intervention methodologies was produced, concluding that the postaccident environmental restoration is possible and desirable. However, for restoration purpose, some limitations remained concerning the capacity to predict the transfer and fluxes of radionuclides (strongly dependent on the local specificity and no directly exchangeable from one place to another) and the correct assessment of the performance of the applicable countermeasures. In the first case, a possible approach to solve the problem would be the identification and further use of some local characteristics (of the scenario of contamination), to predict, using adequate radioecological models, the behaviour of the radionuclides (and their radiological consequences) for places and times different than those experimental sites where information exists. Concerning the second problem, one must identify the features of the scenario having influence on the performance of the countermeasures and to consider those factors (not only radiological) related to their applicability, cost and secondary effects, including the management and disporadiological impact and the countermeasures performance , are unavoidable to face the

Boundary conditions for pathways, safety analysis and basic criteria for low-level radiation waste site selection

International Nuclear Information System (INIS)

Saverot, P.

1994-01-01

There are three successive periods in the life of a disposal facility: the operating period, the institutional control period and the unrestricted site access period. The purpose of safety analysis of the disposal facility is to ensure that the radiological impacts for each period in the life of the facility are acceptable under all circumstances. Founded on a deterministic approach, this analysis leads to a determination of the maximum quantity of each radionuclide present in the facility at the beginning of the institutional control period in order for the impacts to be considered acceptable. Safety analysis involves the calculation of the radiological impacts of a given radiological inventory under a selected scenario, from all plausible scenarios of radionuclide migration to the environment in both normal and accident conditions, and taking into account other specified variables. The calculation itself involves an assessment of the quantities of radionuclides that could be released to the environment under the specific scenario selected and following identified pathways, and a determination of the resultant exposure, both internal and external, to the public. An iterative approach is used in the performance of pathways analyses. If the pathways analyses result in unacceptable radiological impacts, either the radiological inventory of the site is reduced or barrier characteristics not previously factored into the analysis are taken into account. New pathways analyses are then performed until the results are within the acceptable range. Once accepted by the safety authorities, the radiological inventory becomes the radiological capacity, which is the approved quantities of specific radionuclides that may be disposed of at the site. The following elaborates on the boundary conditions used in safety analyses and describes the types of pathways analyses performed for a LLW disposal facility

Environmental Report 1996

Energy Technology Data Exchange (ETDEWEB)

Harrach, R.J.

1996-01-01

This summary provides an overview of LLNL`s environmental activities in 1996, including radiological and nonradiological surveillance, effluent and compliance monitoring, remediation, assessment of radiological releases and doses, and determination of the impact of LLNL operations on the environment and public health.

Determination of the radiological capacity in the IEA environment

International Nuclear Information System (INIS)

Palacios, E.; Oliveira, P.L.C.

1976-01-01

The radiological capacity in the IEA environment, was calculated according to the recommendations of the International Commission on Radiological Protection, in order to assess the management wastes disposal programming. The value of radiological capacity, take into account the isotopic composition, at the production moment, was 850 Ci/year. The IEA radioactive environment disposal, up to now, employed just a small fraction of its capacity. Iodine I-131 air inhalation, and external radiation, derivated from the sediments around the discharged point of Pinheiros river, were the 'critical pathways'; for the second case the 'critical radionuclides' were: Te-125m, Te-123m, Te-127m, I-131 e Cs-137. The 'Dose Commitment' of one year operation will be not upper than 20 mrad in the infant's thyroid and 140 mrad in the whole body [pt

1995 Site environmental report Sandia National Laboratories, Albuquerque, New Mexico

Energy Technology Data Exchange (ETDEWEB)

Shyr, L.J.; Duncan, D. [eds.; Sanchez, R.

1996-09-01

This 1995 report contains data from routine radiological and non-radiological environmental monitoring activities. Summaries of significant environmental compliance programs in progress, such as National Environmental Policy Act documentation, environmental permits, environmental restoration and various waste management programs at Sandia National Laboratories in Albuquerque, New Mexico, are included.

1995 Site environmental report Sandia National Laboratories, Albuquerque, New Mexico

International Nuclear Information System (INIS)

Shyr, L.J.; Duncan, D.; Sanchez, R.

1996-09-01

This 1995 report contains data from routine radiological and non-radiological environmental monitoring activities. Summaries of significant environmental compliance programs in progress, such as National Environmental Policy Act documentation, environmental permits, environmental restoration and various waste management programs at Sandia National Laboratories in Albuquerque, New Mexico, are included

Comparison of the radiological impacts of thorium and uranium nuclear fuel cycles

International Nuclear Information System (INIS)

Meyer, H.R.; Witherspoon, J.P.; McBride, J.P.; Frederick, E.J.

1982-03-01

This report compares the radiological impacts of a fuel cycle in which only uranium is recycled, as presented in the Final Generic Environmental Statement on the Use of Recycle Plutonium in Mixed Oxide Fuel in Light Water Cooled Reactors (GESMO), with those of the light-water breeder reactor (LWBR) thorium/uranium fuel cycle in the Final Environmental Statement, Light Water Breeder Reactor Program. The significant offsite radiological impacts from routine operation of the fuel cycles result from the mining and milling of thorium and uranium ores, reprocessing spent fuel, and reactor operations. The major difference between the impacts from the two fuel cycles is the larger dose commitments associated with current uranium mining and milling operations as compared to thorium mining and milling. Estimated dose commitments from the reprocessing of either fuel type are small and show only moderate variations for specific doses. No significant differences in environmental radiological impact are anticipated for reactors using either of the fuel cycles. Radiological impacts associated with routine releases from the operation of either the thorium or uranium fuel cycles can be held to acceptably low levels by existing regulations

Environmental radiological protection of Bariloche Atomic Center; Proteccion radiologica ambiental del Centro Atomico Bariloche

Energy Technology Data Exchange (ETDEWEB)

Andres, Pablo A.; Levanon, Izhar S., E-mail: andresp@cab.cnea.gov.ar, E-mail: levanon@cab.cnca.gov.ar [Comision Nacional de Energia Atomica (CNEA), San Carlos de Bariloche (Argentina). Centro Atomico Bariloche. Division Proteccion Radiologica

2013-07-01

This plan of monitoring radiological environmental routine fits on environmental policy of CNEA, satisfying national and international recommendations for licensed facilities. Sampling matrices are related to direct routes of exposure: air and water (river, lake, sediments, drinking water). Soil samples are also analyzed for having integrated matrices. They are considered as minimum three points of measurement: a white point (water or winds up), a point of maximum (water or winds down) and a point corresponding to the location of the individual representative or a point of public interest. Measurements in air estimate KERMA rate with thermoluminescent dosimeters, bi-monthly, and concentrations of particulate material and aerosols. For water samples (monthly), soil and sediments (quarterly), radionuclides that have download limits are analyzed, according to its importance in the dosages produced in the representative individual. In these cases artificial radionuclides using gamma spectrometry, beta total and Sr-90 by radiochemical techniques if the value of total screening (1 Bq/L) is exceeded. Foods are not included because no possible matrices were detected, either by their distance. by located not predominant wind direction. They are however still looking for milk producers that fulfills the minimum requirements.The data collected are compared with environmental baselines to set trends that might point to future significant changes in the environment during the life of the facilities. So far it was not observed significant differences with respect to baseline values.

Annual Site Environmental Report for Calendar Years 2005-2006

International Nuclear Information System (INIS)

Finley, Virginia L.

2010-01-01

Contained in the following report are data for radioactivity in the environment collected and analyzed by Princeton Plasma Physics Laboratory's Princeton Environmental, Analytical, and Radiological Laboratory (PEARL). The PEARL is located on-site and is certified for analyzing radiological and non-radiological parameters through the New Jersey Department of Environmental Protection's Laboratory Certification Program, Certification Number 12471. Non-radiological surface and ground water samples are analyzed by NJDEP certified subcontractor laboratories - QC, Inc. and Accutest Laboratory. To the best of our knowledge, these data, as contained in the 'Annual Site Environmental Report for 2005 and 2006,' are documented and certified to be correct.

Radiological control criteria for materials considered for recycle and reuse

International Nuclear Information System (INIS)

Kennedy, W.E. Jr.; Hill, R.L.; Aaberg, R.L.; Wallo, A. III.

1995-01-01

Pacific Northwest Laboratory (PNL) is conducting technical analyses to support the U.S. Department of Energy (DOE), Office of Environmental Guidance, Air, Water, and Radiation Division (DOE/EH-232) in developing radiological control criteria for recycling or reuse of metals or equipment containing residual radioactive contamination from DOE operations. The criteria, framed as acceptable concentrations for release of materials for recycling or reuse, are risk-based and were developed through analysis of generic radiation exposure scenarios and pathways. The analysis includes evaluation of relevant radionuclides, potential mechanisms of exposure, and non-health-related impacts of residual radioactivity on electronics and film. The analysis considers 42 key radionuclides that DOE operations are known to generate and that may be contained in recycled or reused metals or equipment. The preliminary results are compared with similar results reported by the International Atomic Energy Agency, by radionuclide grouping. (author)

Research and development in radiological protection

International Nuclear Information System (INIS)

Butragueno, J. L.; Villota, C.; Gutierrez, C.; Rodriguez, A.

2004-01-01

The objective of Radiological Protection is to guarantee that neither people, be they workers or members of the public, or the environment are exposed to radiological risks considered by society to be unacceptable. Among the various resources available to meet this objective is Research and Development (R and D), which is carried out in three areas: I. Radiological protection of persons: (a) knowledge of the biological effects of radiations, in order to determine the relationship that exists between radiation exposure dose and its effects on health; (b) the development of new personal dosimetry techniques in order to adapt to new situations, instrumental techniques and information management technologies allowing for better assessment of exposure dose; and (c) development of the principle of radiological protection optimisation (ALARA), which has been set up internationally as the fundamental principle on which radiological protection interventions are based. II. Assessment of environmental radiological impact, the objective of which is to assess the nature and magnitude of situations of exposure to ionising radiations as a result of the controlled or uncontrolled release of radioactive material to the environment, and III.Reduction of the radiological impact of radioactive wastes, the objective of which is to develop radioactive material and waste management techniques suitable for each situation, in order to reduce the risks associated with their definitive management or their release to the environment. Briefly described below are the strategic lines of R and D of the CSN, the Electricity Industry, Ciemat and Enresa in the aforementioned areas. (Author)

Depleted uranium residual radiological risk assessment for Kosovo sites

International Nuclear Information System (INIS)

Durante, Marco; Pugliese, Mariagabriella

2003-01-01

During the recent conflict in Yugoslavia, depleted uranium rounds were employed and were left in the battlefield. Health concern is related to the risk arising from contamination of areas in Kosovo with depleted uranium penetrators and dust. Although chemical toxicity is the most significant health risk related to uranium, radiation exposure has been allegedly related to cancers among veterans of the Balkan conflict. Uranium munitions are considered to be a source of radiological contamination of the environment. Based on measurements and estimates from the recent Balkan Task Force UNEP mission in Kosovo, we have estimated effective doses to resident populations using a well-established food-web mathematical model (RESRAD code). The UNEP mission did not find any evidence of widespread contamination in Kosovo. Rather than the actual measurements, we elected to use a desk assessment scenario (Reference Case) proposed by the UNEP group as the source term for computer simulations. Specific applications to two Kosovo sites (Planeja village and Vranovac hill) are described. Results of the simulations suggest that radiation doses from water-independent pathways are negligible (annual doses below 30 μSv). A small radiological risk is expected from contamination of the groundwater in conditions of effective leaching and low distribution coefficient of uranium metal. Under the assumptions of the Reference Case, significant radiological doses (>1 mSv/year) might be achieved after many years from the conflict through water-dependent pathways. Even in this worst-case scenario, DU radiological risk would be far overshadowed by its chemical toxicity

The future policy for radiological protection

International Nuclear Information System (INIS)

2004-01-01

At the end of the 1990's, the International Commission on Radiological Protection (ICRP) launched a process for establishing new recommendations, which are expected to serve as guidelines for national systems of radiological protection. Currently the ICRP's proposed recommendations are being subjected to extensive stakeholder comment and modifications. The NEA Committee on Radiation Protection and Public Health (CRPPH) has been actively involved in this process. Part of the Committee's work has been to undertake collaborative efforts with the ICRP through, for example, the organisation of broad stakeholder fora. The first of these, held in Taormina, Italy in 2002, focused on the development of a policy basis for the radiological protection of the environment. The second forum, held in Lanzarote, Spain in April 2003, addressed the latest concepts and approaches in the ICRP proposed recommendations for a system of radiological protection. During this meeting, the ICRP listened to the views of various stakeholder groups, including radiological protection regulators, environmental protection ministries, the nuclear power industry and NGOs. As a result, the ICRP modified its proposals to better reflect stakeholder needs and wishes. This report presents the outcomes of the discussions, examining what the ICRP proposed and how its proposals have been affected and modified as a result of stakeholder input. (author)

Internal Controlling of a Radiology Department.

Science.gov (United States)

Frewer, W; Busch, H P

2015-11-01

Caused by legal reform initiatives there is a continuous need to increase effectiveness and efficiency in hospitals and surgeries, and thus to improve processes.Consequently the successful management of radiological departments and surgeries requires suitable structures and optimization processes to make optimization in the fields of medical quality, service quality and efficiency possible.In future in the DRG System it is necessary that the organisation of processes must focus on the whole clinical treatment of the patients (Clinical Pathways). Therefore the functions of controlling must be more established and adjusted. On the basis of select Controlling instruments like budgeting, performance indicators, process optimization, staff controlling and benchmarking the target-based and efficient control of radiological surgeries and departments is shown. © Georg Thieme Verlag KG Stuttgart · New York.

ZZ RADDECAY, Decay Data Library for Radiological Assessment

International Nuclear Information System (INIS)

2000-01-01

Description of program or function: - Format: special format defined in documentation. - Nuclides: 500 nuclides of interest in the nuclear fuel cycle, environmental problems, nuclear medicine, fusion reactor technology, and radiological protection assessment. - Origin: DLC-80/DRALIST. ZZ-RADDECAY is a data library of half-lives, radioactive daughter nuclides, probabilities per decay and decay product energies for alpha particles, positrons, electrons, X-rays, and gamma-rays. The current data base contains approximately 500 nuclides of interest in the nuclear fuel cycle, environmental problems, nuclear medicine, fusion reactor technology, and radiological protection assessment. RADIATION DECAY VERSION 2 March 1997: This application is being provided by Aptec as 'Freeware' with permission of the author Mr. Charles Hacker, Engineering and Applied Science, Griffith University, Australia

CRITICAL RADIONUCLIDE AND PATHWAY ANALYSIS FOR THE SAVANNAH RIVER SITE

Energy Technology Data Exchange (ETDEWEB)

Jannik, T.

2011-08-30

This report is an update to the analysis, Assessment of SRS Radiological Liquid and Airborne Contaminants and Pathways, that was performed in 1997. An electronic version of this large original report is included in the attached CD to this report. During the operational history (1954 to the present) of the Savannah River Site (SRS), many different radionuclides have been released to the environment from the various production facilities. However, as will be shown by this updated radiological critical contaminant/critical pathway analysis, only a small number of the released radionuclides have been significant contributors to potential doses and risks to offsite people. The analysis covers radiological releases to the atmosphere and to surface waters, the principal media that carry contaminants offsite. These releases potentially result in exposure to offsite people. The groundwater monitoring performed at the site shows that an estimated 5 to 10% of SRS has been contaminated by radionuclides, no evidence exists from the extensive monitoring performed that groundwater contaminated with these constituents has migrated off the site (SRS 2011). Therefore, with the notable exception of radiological source terms originating from shallow surface water migration into site streams, onsite groundwater was not considered as a potential exposure pathway to offsite people. In addition, in response to the Department of Energy's (DOE) Order 435.1, several Performance Assessments (WSRC 2008; LWO 2009; SRR 2010; SRR 2011) and a Comprehensive SRS Composite Analysis (SRNO 2010) have recently been completed at SRS. The critical radionuclides and pathways identified in these extensive reports are discussed and, where applicable, included in this analysis.

Nuclear-fuel-cycle education: Module 10. Environmental consideration

International Nuclear Information System (INIS)

Wethington, J.A.; Razvi, J.; Grier, C.; Myrick, T.

1981-12-01

This educational module is devoted to the environmental considerations of the nuclear fuel cycle. Eight chapters cover: National Environmental Policy Act; environmental impact statements; environmental survey of the uranium fuel cycle; the Barnwell Nuclear Fuel Reprocessing Plant; transport mechanisms; radiological hazards in uranium mining and milling operations; radiological hazards of uranium mill tailings; and the use of recycle plutonium in mixed oxide fuel

Radiological survey techniques for decontamination and dismantlement applications

International Nuclear Information System (INIS)

Ruesink, G.P.; Stempfley, D.H.; Pettit, P.J.; Warner, R.D.

1997-01-01

The Department of Energy's Fernald Environmental Management Project (FEMP) is engaged in an aggressive Program to remove all above ground structures as part of the Fernald sites final remediation remedy. Through the complete removal of major facilities such as Plant 7, Plant 4, and Plant 1, the FEMP has developed radiological survey approaches that are effective for the different phases of the Decontamination and Dismantlement (D ampersand D) process. Some of the most pressing challenges facing the FEMP are implementing effective, low cost methods for the D ampersand D of former process buildings while minimizing environmental effects. One of the key components to ensure minimal impact on the environment is the collection of radiological contamination information during the D ampersand D process to facilitate the decision making process. Prior to the final demolition of any structure, radiological surveys of floors, walls, and ceilings must take place. These surveys must demonstrate that contamination levels am below 5000 dpm removable beta/gamma for non-porous surfaces and below 1000 dpm removable-beta/gamma for all porous surfaces. Technique which can perform these activities in a safe, effective, and cost efficient manner are greatly desired. The FEMP has investigated new approaches to address this need. These techniques include sampling approaches using standard baseline methodology as well as innovative approaches to accelerate final radiological clearance processes. To further improve upon this process, the FEMP has investigated several new technologies through the Fernald Plant 1 Large Scale Technology Demonstration Project. One of the most promising of these new technologies, Laser Induced Fluorescence, may significantly improve the radiological clearance survey process. This paper will present real world experiences in applying radiological control limits to D ampersand D projects as well as relate potential productivity and cost improvements with the

Water radiological surveillance (II)

International Nuclear Information System (INIS)

Pablo San Martin de, M.

2008-01-01

This paper summarizes the characteristics of the Environmental Surveillance Radiological Networks (ESRN) currently operating in CEDEX. In the first part, the Spanish Continental Waters ESRN has been presented. This second one describes Spanish Costal Waters ESRN and the High Sensitivity Networks in Continental and Marine Waters. It also presents the Radiological Surveillance of Drinking Waters that CEDEX carries out in waters of public consumption management by the Canal de Isabel II (CYII) and by the Mancomunity of Canals Taibilla (M.C.T.). The legislation applicable in each case is reviewed as well. Due to its extension the article has been divided into two parts. As Spanish Continental Waters ESRN has been reviewed in the first part, the others ESRN are discussed in this second one. (Author) 10 refs

Federal Radiological Monitoring and Assessment Center (FRMAC), US response to major radiological accidents

International Nuclear Information System (INIS)

Mueller, P.G.

2000-01-01

During the 1960's and 70's the expanded use of nuclear materials to generate electricity, to provide medical benefits, and for research purposes continued to grow in the United States. While substantial effort went into constructing plants and facilities and providing for a number of redundant backup systems for safety purposes, little effort went into the development of emergency response plans for possible major radiological accidents. Unfortunately, adequate plans and procedures had not been developed to co-ordinate either state or federal emergency response assets and personnel should a major radiological accident occur. This situation became quite evident following the Three Mile Island Nuclear Reactor accident in 1979. An accident of that magnitude had not been adequately prepared for and Pennsylvania's limited emergency radiological resources and capabilities were quickly exhausted. Several federal agencies with statutory responsibilities for emergency response, including the U.S. Environmental Protection Agency (EPA), U.S. Department of Energy (DOE), Federal Emergency Management Agency (FEMA), Nuclear Regulatory Commission (NRC), and others provided extensive assistance and support during the accident. However, the assistance was not fully co-ordinated nor controlled. Following the Three Mile Island incident 13 federal agencies worked co-operatively to develop an agreement called the Federal Radiological Emergency Response Plan (FRERP). Signed in November 1985, this plan delineated the statutory responsibilities and authorities of each federal agency signatory to the FRERP. In the event of a major radiological accident, the FRERP would be activated to ensure that a co-ordinated federal emergency response would be available to respond to any major radiological accident scenario. The FRERP encompasses a wide variety of radiological accidents, not just those stemming from nuclear power plants. Activation of the FRERP could occur from major accidents involving

Optimal layout of radiological environment monitoring based on TOPSIS method

International Nuclear Information System (INIS)

Li Sufen; Zhou Chunlin

2006-01-01

TOPSIS is a method for multi-objective-decision-making, which can be applied to comprehensive assessment of environmental quality. This paper adopts it to get the optimal layout of radiological environment monitoring, it is proved that this method is a correct, simple and convenient, practical one, and beneficial to supervision departments to scientifically and reasonably layout Radiological Environment monitoring sites. (authors)

The radiological assessment system for consequence analysis - RASCAL

International Nuclear Information System (INIS)

Sjoreen, A.L.; Ramsdell, J.V.; Athey, G.F.

1996-01-01

The Radiological Assessment System for Consequence Analysis, Version 2.1 (RASCAL 2.1) has been developed for use during a response to radiological emergencies. The model estimates doses for comparison with U.S. Environmental Protection Agency (EPA) Protective Action Guides (PAGs) and thresholds for acute health effects. RASCAL was designed to be used by U.S. Nuclear Regulatory Commission (NRC) personnel who report to the site of a nuclear accident to conduct an independent evaluation of dose and consequence projections and personnel who conduct training and drills on emergency responses. It allows consideration of the dominant aspects of the source term, transport, dose, and consequences. RASCAL consists of three computational tools: ST-DOSE, FM-DOSE, and DECAY. ST-DOSE computes source term, atmospheric transport, and dose to man from accidental airborne releases of radionuclides. The source-term calculations are appropriate for accidents at U.S. power reactors. FM-DOSE computes doses from environmental concentrations of radionuclides in the air and on the ground. DECAY computes radiological decay and daughter in-growth. RASCAL 2.1 is a DOS application that can be run under Windows 3.1 and 95. RASCAL has been the starting point for other accident consequence models, notably INTERRAS, an international version of RASCAL, and HASCAL, an expansion of RASCAL that will model radiological, biological, and chemical accidents

Guidelines for planning and design of mobile radiological units

Energy Technology Data Exchange (ETDEWEB)

Schelenz, R [Federal Office for Environmental Radioactivity in Food, Total Diet and Infant Food, Federal Research Centre for Nutrition, Karlsruhe (Germany)

1995-07-01

A significant number of mobile radiological units are in operation worldwide aiming to provide reliable radiological data. They mainly have been designed and constructed on a national basis according to the particular needs and commitments of the specific laboratory or country. In most cases, these units are intended to be used in emergency situations for in-situ radiological measurements of accidentally released radioactivity, sometimes for monitoring environmental pollution. As the purpose of these units is very diversified in regard to the kind of vehicle and its in-built measuring equipment the varying outfit of these units cannot be adopted in general for other countries aiming to improve their capability for in-situ radiological measurement. In order to achieve harmonization of equipment and comparability of radiological data being obtained from field measurements it is necessary to have general guidelines available for designing mobile radiological units taking into account different sceneries and tasks to be achieved. In the very early stages of an accident most of the information available on the quantity of radioactive material being released, its radionuclide composition and the likely progression of the accident will come from the operator, and will be based on the conditions in the plant. Few environmental monitoring results from off-side can be expected within the first few hours. In this very early phase, decisions on the application of protective measures will therefore, be based largely on plant status and forecasts of changes in that status as well as on meteorological data. As time progresses, results will increasingly become available from the monitoring of radionuclides in the environment (e.g. dose rates and concentration of radionuclides in air and particular materials such as water, food etc). Monitoring results can be used to estimate potential doses to people and the need for further protective measures can thus be determined from a

Guidelines for planning and design of mobile radiological units

International Nuclear Information System (INIS)

Schelenz, R.

1995-01-01

A significant number of mobile radiological units are in operation worldwide aiming to provide reliable radiological data. They mainly have been designed and constructed on a national basis according to the particular needs and commitments of the specific laboratory or country. In most cases, these units are intended to be used in emergency situations for in-situ radiological measurements of accidentally released radioactivity, sometimes for monitoring environmental pollution. As the purpose of these units is very diversified in regard to the kind of vehicle and its in-built measuring equipment the varying outfit of these units cannot be adopted in general for other countries aiming to improve their capability for in-situ radiological measurement. In order to achieve harmonization of equipment and comparability of radiological data being obtained from field measurements it is necessary to have general guidelines available for designing mobile radiological units taking into account different sceneries and tasks to be achieved. In the very early stages of an accident most of the information available on the quantity of radioactive material being released, its radionuclide composition and the likely progression of the accident will come from the operator, and will be based on the conditions in the plant. Few environmental monitoring results from off-side can be expected within the first few hours. In this very early phase, decisions on the application of protective measures will therefore, be based largely on plant status and forecasts of changes in that status as well as on meteorological data. As time progresses, results will increasingly become available from the monitoring of radionuclides in the environment (e.g. dose rates and concentration of radionuclides in air and particular materials such as water, food etc). Monitoring results can be used to estimate potential doses to people and the need for further protective measures can thus be determined from a

Environmental radiological monitoring methods in TENORM facilities and its relevance

International Nuclear Information System (INIS)

Teng Iyu Lin; Ismail Bahari; Muhamad Samudi Yasir

2011-01-01

In Malaysia, mineral processing plant is one of the Naturally Occurring Radioactive Material (NORM) processing industries controlled by the Atomic Energy Licensing Board (AELB) through the enforcement of Atomic Energy Licensing Act 1984 (Act 304). The activities generated waste which is called as TENORM wastes. TENORM wastes are mainly found in thorium hydroxide from the processing of xenotime and monazite, and iron oxide and red gypsum from the processing of ilmenite. Other TENORM wastes are scales and sludge from the oil and gas industries, tin slag produced from the smelting of tin, and ilmenite, zircon, and monazite produced from the processing of tin tailing (amang). The environmental and radiological monitoring program is needed to ensure that the TENORM wastes did not caused any contamination to the environment. The wastes vary in the types of samples, parameters of analysis as well as the frequency of monitoring based on licenses conditions issued by the AELB. The main objective of this study is to assess the suitability of licenses condition and the monitoring program required in oil and gas, and mineral processing industries. Study was done by assessing the data submitted to the AELB in order to comply with the licensing requirement. This study had found out that there are a few of licenses conditions that need to be reviewed accordingly based on the processing activity. (Author)

The establishment of computer codes for radiological assessment on LLW final disposal in Taiwan

International Nuclear Information System (INIS)

Yang, C.C.; Chen, H.T.; Shih, C.L.; Yeh, C.S.; Tsai, C.M.

1988-01-01

For final shallow land disposal of Low Level Waste (LLW) in Taiwan, an effort was initiated to establish the evaluation codes for the needs of environmental impact analysis. The objective of the computer code is to set up generic radiological standards for future evaluation on 10 CFR Part 61 Licensing Requirements for Land Disposal of Radioactive Wastes. In determining long-term influences resulting from radiological impacts of LLW at disposal sites there are at least three quantifiable impact measures selected for calculation: dose to members of the public (individual and population), occupational exposures and costs. The computer codes are from INTRUDE, INVERSI and INVERSW of NUREG-0782, OPTIONR and GRWATRR of NUREG-0945. They are both installed in FACOM-M200 and IBM PC/AT systems of Institute of Nuclear Energy Research (INER). The systematic analysis of the computer codes depends not only on the data bases supported by NUREG/CR-1759 - Data Base for Radioactive Waste Management, Volume 3, Impact Analysis Methodology Report but also the information collected from the different exposure scenarios and pathways. The sensitivity study is also performed to assure the long-term stability and security for needs of determining performance objectives

Savannah River Site environmental data for 1993

Energy Technology Data Exchange (ETDEWEB)

Arnett, M.W. [ed.

1994-05-01

The figures and tables in this report represent a capsule view of the routine environmental monitoring and surveillance programs at the Savannah River Site. An attempt has been made to include all available data from environmental research programs. The first section of the book is a collection of maps of radiological and nonradiological sampling locations. Also included are general radiological and nonradiological sampling and analysis schedules; a list of the media sampled, along with sample sizes and representative aliquots; a list of the lower limits of detection for radiological detection instruments; the minimum detectable concentrations for gamma analysis of water and air samples; and the minimum detectable concentrations for gamma analysis of soil, food, fish and wildlife, and vegetation samples. Following the first section are data tables containing radiological and nonradiological effluent monitoring results, radiological and nonradiological environmental surveillance results, dose estimates, quality assurance activities, and results of nonroutine occurrences and special surveys.

Nevada Test Site Environmental Report 2005

International Nuclear Information System (INIS)

Cathy A. Wills

2006-01-01

The Nevada Test Site Environmental Report 2005 (NTSER) was prepared to meet the information needs of the public and the requirements and guidelines of the U.S. Department of Energy (DOE) for annual site environmental reports. Its purpose is to (1) report compliance status with environmental standards and requirements, (2) present results of environmental monitoring of radiological and nonradiological effluents, (3) report estimated radiological doses to the public from releases of radioactive material, (4) summarize environmental incidents of noncompliance and actions taken in response to them, (5) describe the NTS Environmental Management System and characterize its performance, and (6) highlight significant environmental programs and efforts

Nevada Test Site Environmental Report 2005

Energy Technology Data Exchange (ETDEWEB)

Cathy A. Wills

2006-10-01

The Nevada Test Site Environmental Report 2005 (NTSER) was prepared to meet the information needs of the public and the requirements and guidelines of the U.S. Department of Energy (DOE) for annual site environmental reports. Its purpose is to (1) report compliance status with environmental standards and requirements, (2) present results of environmental monitoring of radiological and nonradiological effluents, (3) report estimated radiological doses to the public from releases of radioactive material, (4) summarize environmental incidents of noncompliance and actions taken in response to them, (5) describe the NTS Environmental Management System and characterize its performance, and (6) highlight significant environmental programs and efforts.

Performance of Models in Radiological Impact Assessment for Normal Operation. Report of Working Group 1 Reference Methodologies for Controlling Discharges of Routine Releases of EMRAS II Topical Heading Reference Approaches for Human Dose Assessment. Environmental Modelling for Radiation Safety (EMRAS II) Programme

International Nuclear Information System (INIS)

2017-01-01

This publication provides the results from Working Group 1, on Reference Methodologies for Controlling Discharges of Routine Releases, of the IAEA’s EMRAS II (Environmental Modelling for Radiation Safety) programme, which ran from 2009 to 2011. This Working Group carried out an intercomparison of methods used for assessing radiological impacts to people and the environment due to authorized releases of radionuclides during normal operation of nuclear facilities. Three important types of exposure scenarios were considered, those related to atmospheric, marine and river releases. The publication describes the details of the hypothetical radioactive release scenarios, the environmental pathways considered, the environmental transfer models applied, the calculation methods and the results obtained. An analysis of the results and the main findings and conclusions relevant for the use of the described input data and methodologies in regulatory applications is included. The publication also presents considerations on selection of the ‘representative person’ and a summary of the different approaches in some States for the regulatory control of radioactive discharges. Input data is included in the annex.

Automation of the radiological survey process: USRADS ultrasonic ranging and data system

International Nuclear Information System (INIS)

Berven, B.A.; Blair, M.S.; Little, C.A.

1987-01-01

The Radiological Survey Activities (RASA) program at Oak Ridge National Laboratory (ORNL) serves as the Inclusion Survey Contractor (ISC) in the Department of Energy's (DOE) Uranium Mill Tailings Remedial Action project (UMTRAP). The ISC is to identify properties in the vicinity of 24 inactive uranium mill sites suspected of having 226 Ra-bearing uranium mill tailings by-product material originating from the processing of uranium ore contamination. Mobile gamma scanning was the primary method used to identify these properties. Once identified, the ISC conducts an inclusion survey. This survey performs sufficient radiological measurements to determine if uranium mill tailing contamination is present, and, if so, if it is in excess of relevant Environmental Protection Agency (EPA) criteria. Radon emanating from 226 Ra is the primary pathway of exposure to human occupants at these sites. EPA criteria focus on controlling 226 Ra concentration in soil. The concentration of 226 Ra in soil can be measured directly by soil sampling and subsequent gamma spectrographic analysis of the sample, or by direct measurement of the gamma exposure rate at the soil surface using portable instrumentation in the field. In both methods, the concentration of 226 Ra is inferred by examining the frequency of gamma emission of 214 Bi, a radioactive decay product in the 238 U decay chain

Annual Site Environmental Report for Calendar Years 2005-2006

Energy Technology Data Exchange (ETDEWEB)

Virginia L. Finley

2010-01-25

Contained in the following report are data for radioactivity in the environment collected and analyzed by Princeton Plasma Physics Laboratory's Princeton Environmental, Analytical, and Radiological Laboratory (PEARL). The PEARL is located on-site and is certified for analyzing radiological and non-radiological parameters through the New Jersey Department of Environmental Protection's Laboratory Certification Program, Certification Number 12471. Non-radiological surface and ground water samples are analyzed by NJDEP certified subcontractor laboratories - QC, Inc. and Accutest Laboratory. To the best of our knowledge, these data, as contained in the "Annual Site Environmental Report for 2005 and 2006," are documented and certified to be correct.

Off-site response for radiological emergencies

International Nuclear Information System (INIS)

Eldridge, J.S.; Oakes, T.W.; Hubbard, H.M.; Hibbitts, H.W.

1982-01-01

Environmental radiological surveillance under emergency conditions at off-site locations is one of the advisory functions provided by DOE within the ORO jurisdiction. The Department of Environmental Management of ORNL has been requested to provide sampling and analytical assistance at such emergency response activities. We have assembled and identified specific individuals and equipment to provide a rapid response force to perform field measurements for environmental radioactivity releases as a consequence of nuclear accidents. Survey teams for sample collection and field measurements are provided along with analytical assistance to operate the radioactivity measuring equipment in the DOE emergency van

Radiology today

International Nuclear Information System (INIS)

Donner, M.W.; Heuck, F.H.W.

1981-01-01

The book encompasses the proceedings of a postgraduate course held in Salzburg in June 1980. 230 radiologists from 17 countries discussed here the important and practical advances of diagnostic radiology, nuclear medicine and ultrasound as they contribute to gastrointestinal, urologic, skeletal, cardiovascular, pediatric, and neuroradiology. The book contains 55 single contributions of different authors to the following main themes: Cardiovascular, Radiology, pulmonary radiology, gastrointestinal radiology, urinary tract radiology, skeletal radiology, mammography, lymphography, ultrasound, ENT radiology, and neuroradiology. (orig./MG)

An aerial radiological survey of the Fernald Environmental Management Project and surrounding area, Fernald, Ohio

International Nuclear Information System (INIS)

Phoenix, K.A.

1997-04-01

An aerial radiological survey was conducted from May 17--22, 1994, over a 36 square mile (93 square kilometer) area centered on the Fernald Environmental Management Project located in Fernald, Ohio. The purpose of the survey was to detect anomalous gamma radiation in the environment surrounding the plant. The survey was conducted at a nominal altitude of 150 feet (46 meters) with a line spacing of 250 feet (76 meters). A contour map of the terrestrial gamma exposure rate extrapolated to 1 meter (3.3 feet) above ground was prepared and overlaid on an aerial photograph of the area. Analysis of the data for man made sources showed five sites within the boundaries of the Fernald Environmental Management Project having elevated readings. The exposure rates outside the plant boundary were typical of naturally occurring background radiation. Soil samples and pressurized ion chamber measurements were obtained at four locations within the survey boundaries to supplement the aerial data. It was concluded that although the radionuclides identified in the high-exposure-rate areas are naturally occurring, the levels encountered are greatly enhanced due to industrial activities at the plant

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

Fifty years of studies on environmental radioactivity in Peru

International Nuclear Information System (INIS)

Osores, Jose M.; Gonzales, Susana; Martinez, Jorge; Lopez, Edith; Jara, Raul; Anaya, Aurelio

2008-01-01

In May of 1962, due to the explosions carried out by the Commission of Atomic Energy of the United States in the Christmas Island, a group of professionals of the 'Junta de Control de Energia Atomica' of Peru, created in 1957, carried out experimental evaluations of atmospheric radioactivity, obtaining acceptable results regarding those of Naval US Research Laboratory, this was the beginning of the Laboratory of Atmospheric Radioactivity that begins to operate permanently in February of 1964. In 1966, France began a program of nuclear tests in the French Polynesian, generating concern due to the meteorological conditions that could affect the peruvian population. With the support of experts and equipments on the part of the government from France, the Laboratory of Environmental Radioactivity began their activities in August of 1966. At the present time, the Laboratory of Environmental Radioactivity is located in the Nuclear Center RACSO of the 'Instituto Peruano de Energia Nuclear' and it carries out the following programs: Radiological Environmental Surveillance in the Influence Area of the Nuclear Center, Nationwide Radiological Environmental Surveillance, Marine Radiological Environmental Surveillance, Radiological Environmental Surveillance in the Peruvian Antarctic Region and Surveillance of the Radioactive Contamination of Foods. The results of the evaluations of the programs of radiological environmental surveillance, developed nationwide from 1962, show one gradual decrease of the levels of environmental radioactivity. Significant concentrations of Cs-137 and Be-7 were found in the Antarctic region, and, in the area of influence of the nuclear center RACSO, environmental discharges of I-131, Cs-137, Co-60, Cs- 134 and Te-123m were detected, however, the concentrations did not present radiological risk for the population. (author)

Methodology to assess the radiological sensitivity of soils: Application to Spanish soils

International Nuclear Information System (INIS)

Trueba Alonso, C.

2005-01-01

A methodology, based on standard physical and chemical soil properties, has been developed to estimate the radiological sensitivity of soils to a 137 C s and 90 S r contamination. In this framework, the soil radiological sensitivity is defined as the soil capability to mobilise or to retain these radionuclides. The purpose of this methodology is to assess, in terms of radiological sensitivity indexes, the behaviour of 137 C s and 90 S r in soils and their fluxes to man, considering two exposure pathways, the external irradiation exposure and the internal exposure from ingestion. The methodology is applied to the great variety of soil types found in Spain, where the soil profile is the reference unit for the assessment. The results for these soil types show, that their basic soil properties are the key to categorise the radiological sensitivity according to the risks considered. The final categorisation allows to identify soils specially sensible and improves the radiological impact assessment predictions. (Author)

Proposal of inspection methodology for environment radiological control

International Nuclear Information System (INIS)

Martins, Nadia Soido Falcao

2005-01-01

The Radiation Protection and Dosimetry Institute (IRD) of the Brazilian Nuclear Energy Commission (CNEN) is in charge of verifying that the self-monitoring operator is effective to control the radiological quality of environmental around the nuclear facilities and carried out in accordance with the regulatory requirements. While a long time, the verification of compliance was kept by the conduction of large scale monitoring programs around all the authorized installations. The IRD decided to reformulate its performance behavior, starting another kind of control program, due to the number increase of nuclear installations and the diversity of activities conducted by the operators. This program, so-called Monitoring Control Program (PCM) is a regulatory activity developed by the Environmental Impact Assessment Service (SEAIA) of IRD and has the aim of check the effectiveness of authorized self-control. Actually the regulatory control of environmental radiological integrity around the authorized nuclear installation essentially depends on the effectiveness of regulatory inspections fulfilled by the SEAIA/IRD. Due to the implementation of modern practices of management in the IRD, specially the quality management system on regulatory inspection activities, emerged the need of unify these actions. It was also necessary to establish standard procedures required for inspection conduction. This work proposes one methodology for the inspections of environmental radiological control suitable to assure the compliance and effectiveness of environmental and effluent monitoring programs conducted by the operator, through the systematic verification of compliance and data quality assessment. The proposed methodology seeks to attend the appeals for high control standards of environment protection and public health. Here, we presented as products of this work: The inspection handbook and checklists for inspections; one framework for sampling, handling, recording and reporting of

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

Radiological Effluent Technical Specifications (RETS) implementation, Kewaunee Nuclear Power Plant

International Nuclear Information System (INIS)

Serrano, W.; Akers, D.W.

1985-06-01

A review of the Radiological Effluent Technical Specifications (RETS) for the Kewaunee Nuclear Power Plant was performed. The principal review guidelines used were NUREG-0133, ''Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants,'' and Draft 7'' of NUREG-0472, Revision 3, ''Radiological Effluent Technical Specifications for Pressurized Water Reactors.'' Draft submittals were discussed with the Licensee by the NRC staff until all items requiring changes to the Technical Specifications were resolved. The Licensee then submitted final proposed RETS to the NRC which were evaluated and found to be in compliance with the NRC review guidelines. The proposed Offsite Dose Calculation Manual and the Radiological Environmental Monitoring Manual were reviewed and generally found to be in compliance with the NRC review guidelines

Annual Report of National Institute of Radiological Sciences, April 1991 - March 1992

International Nuclear Information System (INIS)

1992-07-01

This annual report is a compilation of the research activities and achievement in the National Institute of Radiological Sciences (NIRS) in Japan during the fiscal year 1991 (from April 1991 through March 1992). The research covers a wide range of radiological sciences from molecular to environmental studies and medicine including engineering. Topics consists of physics, chemistry, biomedical science, clinical research, and environmental sciences, covering a total of 69 titles. A list of publications by staff members, activities of research divisions, and organization chart of the NIRS are given in Appendix. (J.P.N.) 64 refs

Pediatric radiology for medical-technical radiology assistants/radiologists

International Nuclear Information System (INIS)

Oppelt, Birgit

2010-01-01

The book on pediatric radiology includes the following chapter: differences between adults and children; psycho-social aspects concerning the patient child in radiology; relevant radiation doses in radiology; help for self-help: simple phantoms for image quality estimation in pediatric radiology; general information; immobilization of the patient; pediatric features for radiological settings; traumatology; contrast agents; biomedical radiography; computerized tomography; NMR imaging; diagnostic ultrasonography; handling of stress practical recommendations; medical displays.

Guide for radiological characterization and measurements for decommissioning of US Department of Energy surplus facilities

Energy Technology Data Exchange (ETDEWEB)

Denahm, D. H.; Barnes, M. G.; Jaquish, R. E.; Corley, J. P.; Gilbert, R. O.; Hoenes, G. R.; Jamison, J. D.; McMurray, B. J.; Watson, E. C.

1983-08-01

This Guide describes the elements of radiological characterization at DOE excess facilities in preparation for, during, and subsequent to decommissioning operations. It is the intent of this Guide and accompanying appendices to provide the reader (user) with sufficient information to carry out that task with a minimum of confusion and to provide a uniform basis for evaluating site conditions and verifying that decommissioning operations are conducted according to a specific plan. Some areas of particular interest in this Guide are: the need to involve appropriate staff from the affected states in the early planning stages of decommissioning; the need for and suggested methods of radiological site characterization to complete a decommissioning project, including: historical surveys, environmental pathway analyses, statistical sampling design, and choosing appropriate instrumentation and measurements; the need for and emphasis on quality assurance, documentation and records retention; the establishment of a Design Objective approach to applying site-specific contamination limits based on the ALARA philosophy; the establishment of a ''de minimis'' or minimum dose level of concern for decommissioning operations based on existing standards, experience and ALARA considerations.

An integrated approach for a dynamic energy and environmental system analysis of biogas production pathways

NARCIS (Netherlands)

Pierie, Frank; Liu, Wen; Moll, Henri C.

2014-01-01

Abstract written to Biogas Science for oral presentation. Regarding a new methodology for determining the energy efficiency, carbon footprint and environmental impact of anaerobic biogas production pathways. Additionally, results are given regarding the impacts of energy crops and waste products

Offsite dose calculation manual guidance: Standard radiological effluent controls for pressurized water reactors

International Nuclear Information System (INIS)

Meinke, W.W.; Essig, T.H.

1991-04-01

This report contains guidance which may be voluntarily used by licensees who choose to implement the provision of Generic Letter 89-01, which allows Radiological Effect Technical Specifications (RETS) to be removed from the main body of the Technical Specifications and placed in the Offsite Dose Calculation Manual (ODCM). Guidance is provided for Standard Effluent Controls definitions, Controls for effluent monitoring instrumentation, Controls for effluent releases, Controls for radiological environmental monitoring, and the basis for Controls. Guidance on the formulation of RETS has been available in draft from (NUREG-0471 and -0473) for a number of years; the current effort simply recasts those RETS into Standard Radiological Effluent Controls for application to the ODCM. Also included for completeness are: (1) radiological environmental monitoring program guidance previously which had been available as a Branch Technical Position (Rev. 1, November 1979); (2) existing ODCM guidance; and (3) a reproduction of generic Letter 89-01

Site Environmental Report for Calendar Year 2000. DOE Operations at The Boeing Company, Rocketdyne Propulsion & Power

Energy Technology Data Exchange (ETDEWEB)

Rutherford, Phil [The Boeing Company, Canoga Park, CA (United States); Samuels, Sandy [The Boeing Company, Canoga Park, CA (United States); Lee, Majelle [The Boeing Company, Canoga Park, CA (United States)

2001-09-01

This Annual Site Environmental Report (ASER) for 2000 describes the environmental conditions related to work performed for the Department of Energy (DOE) at Area IV of the Rocketdyne Santa Susana Field Laboratory (SSFL). In the past, these operations included development, fabrication, and disassembly of nuclear reactors, reactor fuel, and other radioactive materials, under the former Atomics International (AI) Division. Other activities included the operation of large-scale liquid metal facilities for testing of liquid metal fast breeder components at the Energy Technology Engineering Center (ETEC), a government-owned company-operated, test facility within Area IV. All nuclear work was terminated in 1988, and subsequently, all radiological work has been directed toward decontamination and decommissioning (D&D) of the previously used nuclear facilities and associated site areas. Large-scale D&D activities of the sodium test facilities began in 1996. Results of the radiological monitoring program for the calendar year of 2000 continue to indicate no significant releases of radioactive material from Rocketdyne sites. All potential exposure pathways are sampled and/or monitored, including air, soil, surface water, groundwater, direct radiation, transfer of property (land, structures, waste), and recycling. All radioactive wastes are processed for disposal at DOE disposal sites and other sites approved by DOE and licensed for radioactive waste. Liquid radioactive wastes are not released into the environment and do not constitute an exposure pathway.

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

TENORM radiological survey of Utica and Marcellus Shale

International Nuclear Information System (INIS)

Ying, Leong; O’Connor, Frank

2013-01-01

Comprehensive on-site radiological survey of processed sludge drilled materials extracted from the oil and gas production activities in the Utica and Marcellus Shale in Ohio has been conducted with a shielded isotopic identifier incorporating an advanced patented algorithmic processor to measure low-activity levels in compliance with environmental standards. - highlights: • First on-site radiological survey of processed shale sludge from oil and gas fields. • Mobile spectroscopic radiation inspection system with shielding for low-activity measurements. • Quantification of Ra-226 and Ra-228 radionuclides contamination in soil samples

Radiological effects of a nuclear power plant on a river system, as demonstrated by the Gundremmingen BWR on the Danube

International Nuclear Information System (INIS)

Herrmann, H.; Ruf, M.; Huebel, K.; Luensmann, W.

1975-01-01

The Gundremmingen Nuclear Power Plant (boiling water reactor, 237 MW(e)), on the Upper Danube, has been in operation since 1967. Radiological data have been collected throughout its period of operation. The behaviour of the radioactive waste products in the ecological system of the Upper Danube (water, sediments, suspended solids, water-plants, fish) has been analysed in connection with environmental contamination, the uptake capacity of the Danube, and the possible pathways to man. As a result of the investigations, it seems possible to build further nuclear power plants on the Danube, if their rates of release of radioactivity are similar to those at Gundremmingen. (author)

An Assessment of the radiological vulnerability for Spanish soils

International Nuclear Information System (INIS)

Trueba, C.; Millan, R.; Schimid, T.; Lago, C.; Gutierrez, J.

2000-01-01

A methodology is presented to assess the radiological vulnerability of soils, based exclusively on their pedagogical properties. The radiological vulnerability defined as the potential capacity of soils to fix or transfer deposited radiocaesium and radiostrontium to plants, is represented in terms of vulnerability indexes. Two pathways are considered, the external irradiation and their transfer through the food chain, where the top horizon and a critical depth of 60 cm is taken into account, respectively, Partial vulnerability indexes are considered for each pathway, which allows a qualitative prediction of the behaviour of the contaminants in soils Global indexes have been obtained as the sum of the partial indexes. The methodology has been applied and validated using a data base consisting of more than 2000 soil profiles selected from all over Spain. This included a pedagogical characterisation and normalisation of the different soil profiles. Results have been obtained for individual soil profiles and with the aid of a GIS, the distribution of the partial and global indexes have been presented for the most representative soil types. (Author)

Radiological reference base line establishment around CENM site

International Nuclear Information System (INIS)

Elkhoukhi, T.; Dehbi, N.; Amechmachi, N.

2008-01-01

Full text: As for any installation presenting risks for its surrounding, CENM (Centre d'Etudes Nucleaires de Maamora) that accommodates TRIGA Mark II Research Reactor and related laboratories is subjected to a statutory requirement stipulating that the CNESTEN (Centre National De L'Energie Des Sciences Et Des Techniques Nucleaires) that is in charge the operating of CENM must define its own environmental monitoring program assuring that the nuclear installation is in appropriateness with its environment. In this frame , since 1996 the team of USE (Unite Surveillance de L'Environnement) is conducting periodic work consisting in in-situ measurement of ambient gamma rays and collect of environmental samples and their preparation for adequate analysis form required for each radioactive measurement system. This first step of the environmental monitoring program allows establishing the radiological base line on the CENM's site. This base line is necessary to inform on the present radiological state in order to detect any change of this state consequently to the operating of the reactor or the arrival of abnormal radioactive panache from any source.

Consequences of radiological emergencies at Goiania and Mayapuri

International Nuclear Information System (INIS)

Sharma, Ranjit; Pradeepkumar, K.S.; Singh, Rajvir

2012-01-01

Radiological accidents due to orphan sources can lead to emergencies in the public domain, as reported worldwide. Inadequate regulatory control, lack of accountability and improper disposal of radioactive materials in scrap have resulted in radiological emergencies. Apart from few fatalities, they lead to environmental contamination, economic loss and social and psychological impact on the society. The 137 Cs and 60 Co sources of strength TBq to PBq activity level may pose high radiation exposure risk if shielding integrity is affected in any accident. There had been few radiological accidents reported world over which resulted in radiation injuries, environmental contamination and out of proportion panic in the society. The response actions for both these radiological emergencies included search, recovery of sources, decontamination and waste removal for reducing the radiation/contamination levels at the affected site. In both cases, encapsulated sources were damaged by the persons unknowingly. Response operations were carried out for longer period at Goiania compared to Mayapuri because of large scale contamination. 60 Co source being metallic in nature, even after the breaking of sources at Mayapuri the spread of contamination was confined to a small area. In Goiania, the granules of Cesium Chloride were distributed to many people because of its glowing nature in dark which caused spread of contamination to a large area and the accident was detected early as more persons reported with radiation injuries. The detection of Mayapuri accident was delayed as affected personnel reported to the hospital after three weeks of exposure to radiation. The lack of expertise in identifying radiation injuries by medical professionals contributed to further delay in reporting and detection of this emergency. The fatalities in both accidents resulted from acute radiation exposures and delay in getting medical support. The experience gained at radiological emergencies of Goiania

Environmental behavior of technetium in soil and vegetation: implications for radiological impact assessment

International Nuclear Information System (INIS)

Hoffman, F.O.

1982-04-01

Significant radiological exposures have been estimated for hypothetical atmospheric releases of Tc-99 from gaseous diffusion facilities when vegetation-to-soil concentration ratios representative of laboratory experiments are substituted for generic default values assumed in current regulatory models. To test the relevancy of these laboratory ratios, field investigations were conducted to obtain measurements of the vegetation-to-soil concentration ratio for Tc-99 in samples collected near operating gaseous diffusion facilities and to observe the dynamic behavior of technetium in soil and vegetation following a single application of a sprayed solution of /sup 95m/TcO 4 - Comparison of observed field concentration ratios and calculated steady-state concentration ratios with ratios obtained from previous laboratory experiments indicates that concentration ratios obtained from field data are one to two orders of magnitude less than those obtained from the laboratory. Furthermore, a substantial accumulation of technetium in soil and vegetation may not occur over long periods of time, since concentrations of technetium in both environmental media were observed to decrease with time subsequent to initial application of /sup 95m/TcO 4 -

Federal Radiological Monitoring and Assessment Center Analytical Response

International Nuclear Information System (INIS)

Nielsen, E.C.

2003-01-01

The Federal Radiological Monitoring and Assessment Center (FR-MAC) is authorized by the Federal Radiological Emergency Response Plan to coordinate all off-site radiological response assistance to state and local government s, in the event of a major radiological emergency in the United States. The FR-MAC is established by the U.S. Department of Energy, National Nuclear Security Administration, to coordinate all Federal assets involved in conducting a comprehensive program of radiological environmental monitoring, sampling, radioanalysis, quality assurance, and dose assessment. During an emergency response, the initial analytical data is provided by portable field instrumentation. As incident responders scale up their response based on the seriousness of the incident, local analytical assets and mobile laboratories add additional capability and capacity. During the intermediate phase of the response, data quality objectives and measurement quality objectives are more rigorous. These higher objectives will require the use of larger laboratories, with greater capacity and enhanced capabilities. These labs may be geographically distant FR-om the incident, which will increase sample management challenges. This paper addresses emergency radioanalytical capability and capacity and its utilization during FR-MAC operations

Radiological Worker Training: Radiological Worker 2 study guides

International Nuclear Information System (INIS)

1992-10-01

Upon completion of this training course, the participant will have the knowledge to work safely in areas controlled for radiological purposes using proper radiological practices. Radiological Worker H Training, for the worker whose job assignment involves entry into Radiological Buffer Areas and all types of Radiation Contamination and Airborne Radioactivity Areas. This course is designed to prepare the worker to work safely in and around radiological areas and present methods to use to ensure individual radiation exposure is maintained As Low As Reasonably Achievable

Environmental sampling plan for Kwajalein Atoll Lagoon: 2017 Kwajalein sampling event

Energy Technology Data Exchange (ETDEWEB)

Hamilton, T. F. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

2017-07-01

Since the early 1980s, the U.S DOE Marshall Islands Program at LLNL has provided radiological monitoring of the marine and terrestrial environment at nuclear affected atolls in the northern Marshall Islands. The fundamental aim of these studies was to identify the level and distribution of key residual fallout radionuclide in the environment, improve understanding of prevalent radiation exposure pathways, and develop predictive dose assessments for resettled and resettling atoll population groups. These data and information were essential in terms of guiding the development of effective and environmentally protective remedial measures, and promoting potential actions to improve on food safety and security.

Assessment of the radiological conditions in areas of Kuwait with residues of depleted uranium

International Nuclear Information System (INIS)

Cabianca, T.; Danesi, P.R.; Linsley, G.

2004-01-01

The 1991 Gulf War was the first conflict in which DU munitions were used extensively. After this conflict, questions arose regarding the possible link between exposure to ionizing radiation from DU and harmful biological effects. In view of these concerns, the Government of Kuwait, in February 2001, requested the IAEA to conduct an assessment to evaluate the possible radiological impact of residues of DU munitions from the 1991 Gulf War at 11 locations in Kuwait. For this purpose, the IAEA assembled a team of senior experts, who visited Kuwait in September 2001 to carry out a preliminary assessment of the sites and to evaluate the available information. In February 2002 scientists from the IAEA, the Spiez Laboratory (Switzerland), representing UNEP, and the Radiation Protection Department of the Ministry of Health of Kuwait, carried out a sampling campaign at these sites. Around 200 environmental samples, including soil, water and vegetation, were collected during the campaign and subsequently analysed. This study constitutes the first comprehensive radiological assessment of compliance with international radiation protection criteria and standards for areas with residues of DU munitions conducted under the auspices of the IAEA. The findings of this investigation indicate that DU does not pose a radiological hazard to the population of Kuwait. Annual radiation doses arising from exposure to DU residues would be of a few micro-sieverts, well below the annual doses from natural sources of radiation and far below the reference level recommended by the IAEA as a criterion to help establish whether remedial actions are necessary. DU penetrators can still be found at some of the locations visited. Prolonged skin contact with these residues is the only possible pathway that could result in exposures of radiological significance. As long as access to these areas remains restricted, the likelihood that members of the public could come into contact with these residues is low

Federal Radiological Monitoring and Assessment Center. The analytical response

International Nuclear Information System (INIS)

Nielsen, E.C.

2005-01-01

The Federal Radiological Monitoring and Assessment Center (FRMAC) is authorized by the Federal Radiological Emergency Response Plan to coordinate all off-site radiological response assistance to state and local governments, in the event of a major radiological emergency in the United States. The FRMAC is established by the U.S. Department of Energy, National Nuclear Security Administration, to coordinate all Federal assets involved in conducting a comprehensive program of radiological environmental monitoring, sampling, radioanalysis, quality assurance, and dose assessment. During an emergency response, the initial analytical data is provided by portable field instrumentation. As incident responders scale up their response based on the seriousness of the incident, local analytical assets and mobile laboratories add additional capability and capacity. During the intermediate phase of the response, data quality objectives and measurement quality objectives are more rigorous. These higher objectives will require the use of larger laboratories, with greater capacity and enhanced capabilities. These labs may be geographically distant from the incident, which will increase sample management challenges. Emergency radioanalytical capability and capacity and its utilization during FRMAC operations are discussed. (author)

Intercomparison Measurements Exercises of Mobile Radiological Laboratories (invited paper)

International Nuclear Information System (INIS)

Martincic, R.

2000-01-01

After the reactor accident in Chernobyl, the importance of mobile radiological laboratories became evident and in situ gamma spectrometry became a common method for the rapid detection of gamma emitters in the environment. Since then different institutions in European countries have organised periodic intercomparison exercises of mobile radiological laboratories to improve the measurement methods and the preparedness of emergency monitoring teams. The general objectives of these workshops are to promote the knowledge and to exchange the experiences of emergency monitoring teams that use mobile radiological laboratories, as well as to foster the international harmonisation of emergency monitoring procedures and cooperation among teams. Finally, the results of intercomparison measurements have shown that such exercises are mandatory for rapid, efficient and correct environmental monitoring in nuclear or radiological emergencies. An overview of these intercomparison measurements is given, results from the 1999 intercomparison workshop are presented and lessons learned are discussed. (author)

Radiological clerkships as a critical curriculum component in radiology education

International Nuclear Information System (INIS)

Kourdioukova, Elena V.; Verstraete, Koenraad L.; Valcke, Martin

2011-01-01

Objective: The aim of this research was to explore the perceived value of clinical clerkships in the radiology curriculum as well as the impact of radiology clerkship on students' beliefs about the profession of radiology as a whole and as a career. Methods: This study is a sequel to a previous survey in which student perceptions about radiology curriculum components were investigated. The present study focuses on a further analysis of a subsection in this study, based on 14 statements about radiology clerkship and two statements about radiology as a career. Results: Perceived usefulness of the aspects of radiology clerkship as 'radiology examination', 'skills development' and 'diagnosis focus' were awarded the highest scores. The predict value of the subscale 'radiology examination' on the level of performance was very high (adjusted R 2 = 0.19, p < .001). Conclusion: Students expressed highly favorable evaluation of clerkship as a learning environment to learn to order and to interpret imaging studies as well as an unique possibility to attend various radiological examinations and to access to specific radiology software systems, as well as to get a better view on radiology and to improve image interpretation skills. This positive attitude towards clerkship is closely tied to students' beliefs about the profession of radiology as a whole. These aspects of dedicated radiology clerkship are crucial for effective and high-quality education as well as for the choice of radiology as a career.

Diagnostic radiology 1987

International Nuclear Information System (INIS)

Margulis, A.R.; Gooding, C.A.

1987-01-01

This is the latest version of the continuing education course on diagnostic radiology given yearly by the Department of Radiology at the University of California, San Francisco. The lectures are grouped into sections on gastrointestinal radiology, mammography, uroradiology, magnetic resonance, hepatobiliary radiology, pediatric radiology, ultrasound, interventional radiology, chest radiology, nuclear medicine, cardiovascular radiology, and skeletal radiology. Each section contains four to eight topics. Each of these consists of text that represents highlights in narrative form, selected illustrations, and a short bibliography. The presentation gives a general idea of what points were made in the lecture

Radiological Protection Science and Application

International Nuclear Information System (INIS)

Janssens, Augustin; ); Mossman, Ken; Morgan, Bill

2016-01-01

importance of stakeholder involvement and individual and societal values in radiological protection decision making, Chapter 2 of this report addresses the societal aspects of radiological protection decision making. Chapter 3 addresses the application-related aspects of radiological protection. These include existing exposure situations, planned exposure situations, emergency exposure situations and environmental radiological protection. Chapter 4 of the report addresses international standards and Chapter 5 provides CRPPH views on overall ways forward. Annex A provides a more detailed overview of the International Commission on Radiological Protection (ICRP) system of radiological protection, its interpretation in the International Basic Safety Standards (IBSS) and in the Euratom Basic Safety Standards (Euratom BSS). It demonstrates how the ICRP system may be influenced by both an evolving science and society, and in particular by the increasing focus on addressing protection in the context of prevailing circumstances. Each chapter of this report was prepared by experts on the topic, and an attempt has been made to follow a common framework. Having a common framework for chapters addressing science and those addressing implementation proved to be particularly difficult. As a consequence, the report's structure is constructed in such a way so as to address the state of the art in each area, while attempting to present aspects under broadly common headlines. (authors)

Annual report of national institute of radiological sciences, April 1990 - March 1991

International Nuclear Information System (INIS)

1991-07-01

This annual report is a compilation of the research activities and achievement in the National Institute of Radiological Sciences (NIRS) in Japan during the fiscal year 1990 (from April 1990 through March 1991). The research covers a wide range of radiological sciences from molecular to environmental studies and medicine including engineering. Topics consists of physics, chemistry, bio-medical science, clinical research, and environmental sciences, covering a total of 86 titles. A list of publications by staff members, activities of research divisions, and organization chart of the NIRS are given in Appendix. (J.P.N.) 102 refs

Site Environmental Report for calendar year 1998, DOE operations at Rocketdyne Propulsion and Power

International Nuclear Information System (INIS)

Rutherford, P.D.

1999-01-01

This Annual Site Environmental Report for 1998 describes the environmental conditions related to work performed for the Department of Energy (DOE) at Area IV of the Rocketdyne Santa Susana Field Laboratory (SSFL) and De Soto facilities. In the past, these operations included development, fabrication, and disassembly of nuclear reactors, reactor fuel, and other radioactive materials, under the Atomics International (AI) Division. Other activities included the operation of large-scale liquid metal facilities for testing of liquid metal fast breeder components at the Energy Technology Engineering Center (ETEC), a government-owned company-operated, test facility within Area IV. AI was merged into Rocketdyne in 1984 and many of the AI functions were transferred to existing Rocketdyne departments. All nuclear work was terminated in 1988, and subsequently, all radiological work has been directed toward decontamination and decommissioning (D and D) of the previously used nuclear facilities and associated site areas. Large-scale D and D activities of the sodium test facilities began in 1996. Results of the radiological monitoring program for the calendar year of 1998 continue to indicate that there are no significant releases of radioactive material from Rocketdyne sites. All potential exposure pathways are sampled and/or monitored, including air, soil, surface water, groundwater, and direct radiation. All radioactive wastes are processed for disposal at DOE disposal sites and other sites approved by DOE and licensed for radioactive waste. Liquid radioactive wastes are not released into the environment and do not constitute an exposure pathway

Developing a comprehensive and accountable database after a radiological accident

International Nuclear Information System (INIS)

Berry, H.A.; Burson, Z.G.

1986-09-01

After a radiological accident occurs, it is highly desirable to promptly begin developing a comprehensive and accountable environmental database both for immediate health and safety needs and for long-term documentation. The need to assess and evaluate the impact of the accident as quickly as possible is always very urgent, the technical integrity of the data must also be assured and maintained. Care must therefore be taken to log, collate, and organize the environmental data into a complete and accountable database. The key components of the database development are summarized as well as the experience gained in organizing and handling environmental data acquired during: (1) TMI (1979); (2) the St. Lucie Reactor Accident Exercise (through the Federal Radiological Measurement and Assessment Center (FRMAC), March 1984); (3) the Sequoyah Fuels Inc., uranium hexafluoride accident near Gore, Oklahoma (January 1986); and (4) Chernobyl reactor accident in Russia (April 1986)

Radiological Environmental Protection for LCLS-II High Power Operation

Science.gov (United States)

Liu, James; Blaha, Jan; Cimeno, Maranda; Mao, Stan; Nicolas, Ludovic; Rokni, Sayed; Santana, Mario; Tran, Henry

2017-09-01

The LCLS-II superconducting electron accelerator at SLAC plans to operate at up to 4 GeV and 240 kW average power, which would create higher radiological impacts particularly near the beam loss points such as beam dumps and halo collimators. The main hazards to the public and environment include direct or skyshine radiation, effluent of radioactive air such as 13N, 15O and 41Ar, and activation of groundwater creating tritium. These hazards were evaluated using analytic methods and FLUKA Monte Carlo code. The controls (mainly extensive bulk shielding and local shielding around high loss points) and monitoring (neutron/photon detectors with detection capabilities below natural background at site boundary, site-wide radioactive air monitors, and groundwater wells) were designed to meet the U.S. DOE and EPA, as well as SLAC requirements. The radiological design and controls for the LCW systems [including concrete housing shielding for 15O and 11C circulating in LCW, 7Be and erosion/corrosion products (22Na, 54Mn, 60Co, 65Zn, etc.) captured in resin and filters, leak detection and containment of LCW with 3H and its waste water discharge; explosion from H2 build-up in surge tank and release of radionuclides] associated with the high power beam dumps are also presented.

The American Board of Radiology Holman Research Pathway: 10-Year Retrospective Review of the Program and Participant Performance

International Nuclear Information System (INIS)

Wallner, Paul E.; Ang, K. Kian; Zietman, Anthony L.; Harris, Jay R.; Ibbott, Geoffrey S.; Mahoney, Mary C.; Mezwa, Duane G.; Wilson, Lynn D.; Becker, Gary J.

2013-01-01

Introduction: In 1999, the American Board of Radiology (ABR) implemented an innovative training program track in diagnostic radiology (DR) and radiation oncology (RO) designed to stimulate development of a cadre of future academic researchers and educators in the 2 disciplines. The program was designated the Holman Research Pathway (HRP). An in-depth retrospective review of initial certification examination performance, post-training career choices, and academic productivity has not been written. This report represents a 10-year retrospective review of post-training performance of a cohort of trainees who have had sufficient time to complete their training and initial certification process and to enter practice. Methods and Materials: All pertinent proceedings of the ABR and Accreditation Council for Graduate Medical Education (ACGME) Residency Review Committees for DR and RO between 1997 and May 2011 were reviewed. Thirty-four HRP candidates who fulfilled the established evaluation criteria were identified, and their ABR data files were analyzed regarding performance on the qualifying and certifying examinations. All candidates were contacted directly to obtain a current curriculum vitae. Results: Twenty candidates in RO and 14 candidates in DR were identifiable for review. All candidates attained initial certification. At the time of analysis, 23 of 33 (66.6%) candidates were employed in full-time academic practice (1 DR candidate remained in a fellowship and was not evaluated regarding employment status). Fifteen of 20 (75%) RO candidates were in faculty positions compared with 7 of 13 (53.8%) DR trainees. Additional academic productivity metrics are reported. Conclusions: A high percentage of HRP trainees remained in academic practice and demonstrated significant academic productivity as measured by manuscript authorship and research support. Additional time and observation will be needed to determine whether these findings will be sustained by past, current

Radiological protection at particle accelerators: An overview

International Nuclear Information System (INIS)

Thomas, R.H.

1991-01-01

Radiological protection began with particle accelerators. Many of the concerns in the health physics profession today were discovered at accelerator laboratories. Since the mid-1940s, our understanding has progressed through seven stages: observation of high radiation levels; shielding; development of dosimetric techniques; studies of induced activity and environmental impact; legislative and regulatory concerns; and disposal. The technical and scientific aspects of accelerator radiation safety are well in hand. In the US, there is an urgent need to move away from a ''best available technology'' philosophy to risk-based health protection standards. The newer accelerators will present interesting radiological protection issues, including copious muon production and high LET (neutron) environments

A virtual environment for simulation of radiological accidents

International Nuclear Information System (INIS)

Silva, Tadeu Augusto de Almeida; Farias, Oscar Luiz Monteiro de

2013-01-01

A virtual environment is a computer environment, representative of a subset of the real world, and where models of the real world entities, process and events are included in a virtual (three-dimensional) space. Virtual environments are ideal tools for simulation of certain critical processes, such as radiological accidents, where human beings or properties can suffer irreversible or long term damages. Radiological accidents are characterized by the significant exposure to radiation of specialized workers and general public. The early detection of a radiological accident and the determination of its possible extension are essential factors for the planning of prompt answers and emergency actions. This paper proposes the integration of georeferenced representation of the three-dimensional space and agent-based models, with the objective to construct virtual environments that have the capacity to simulate radiological accidents. The three-dimensional georeferenced representations of space candidates are: 1) the spatial representation of traditional geographical information systems (GIS); 2) the representation adopted by Google Maps®. Adding agents to these spatial representations allow us to simulate radiological accidents, quantify the doses received by members of the public, obtain a possible spatial distribution of people contaminated, estimate the number of contaminated individuals, estimate the impact on the health-network, estimate environmental impacts, generate exclusion zones, build alternative scenarios and train staff to deal with radiological accidents. (author)

A virtual environment for simulation of radiological accidents

Energy Technology Data Exchange (ETDEWEB)

Silva, Tadeu Augusto de Almeida, E-mail: tedsilva@ird.gov.br [Instituto de Radioprotecao e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil); Farias, Oscar Luiz Monteiro de, E-mail: fariasol@eng.uerj.br [Universidade do Estado do Rio de Janeiro (UERJ), Rio de Janeiro, RJ (Brazil)

2013-07-01

A virtual environment is a computer environment, representative of a subset of the real world, and where models of the real world entities, process and events are included in a virtual (three-dimensional) space. Virtual environments are ideal tools for simulation of certain critical processes, such as radiological accidents, where human beings or properties can suffer irreversible or long term damages. Radiological accidents are characterized by the significant exposure to radiation of specialized workers and general public. The early detection of a radiological accident and the determination of its possible extension are essential factors for the planning of prompt answers and emergency actions. This paper proposes the integration of georeferenced representation of the three-dimensional space and agent-based models, with the objective to construct virtual environments that have the capacity to simulate radiological accidents. The three-dimensional georeferenced representations of space candidates are: 1) the spatial representation of traditional geographical information systems (GIS); 2) the representation adopted by Google Maps®. Adding agents to these spatial representations allow us to simulate radiological accidents, quantify the doses received by members of the public, obtain a possible spatial distribution of people contaminated, estimate the number of contaminated individuals, estimate the impact on the health-network, estimate environmental impacts, generate exclusion zones, build alternative scenarios and train staff to deal with radiological accidents. (author)

Experience and improved techniques in radiological environmental monitoring at major DOE low-level waste disposal sites

International Nuclear Information System (INIS)

1986-09-01

A summary of routine radiological environmental surveillance programs conducted at major active US Department of Energy (DOE) solid low-level waste (LLW) disposal sites is provided. The DOE disposal sites at which monitoring programs were reviewed include those located at Hanford, Idaho National Engineering Laboratory (INEL), Nevada Test Site (NTS), Los Alamos National Laboratory (LANL), Oak Ridge National Laboratory (ORNL) and Savannah River Plant (SRP). The review is limited to activities conducted for the purpose of monitoring disposal site performance. Areas of environmental monitoring reviewed include air monitoring for particulates and gases, monitoring of surface water runoff, surface water bodies, ground water, monitoring of surface soils and the vadose zone, and monitoring of ambient penetrating radiation. Routine environmental surveillance is conducted at major LLW disposal sites at various levels of effort for specific environmental media. In summary, all sites implement a routine monitoring program for penetrating radiation. Four sites (INEL, NTS, LANL, and SRP) monitor particulates in air specifically at LLW disposal sites. Hanford monitors particulates at LLW sites in conjunction with monitoring of other site operations. Particulates are monitored on a reservationwide network at ORNL. Gases are monitored specifically at active LLW sites operated at NTS, LANL, and SRP. Ground water is monitored specifically at LLW sites at INEL, LANL, and SRP, in conjunction with other operations at Hanford, and as part of a reservationwide program at NTS and ORNL. Surface water is monitored at INEL, LANL, and SRP LLW sites. Surface soil is sampled and analyzed on a routine basis at INEL and LANL. Routine monitoring of the vadose zone is conducted at the INEL and SRP. Techniques and equipment in use are described and other aspects of environmental monitoring programs, such as quality assurance and data base management, are reviewed

Radiological impacts from nuclear facilities on non-human species

International Nuclear Information System (INIS)

1997-07-01

This monograph is the Proceedings of a Symposium on Radiological Impacts from Nuclear Facilities on Non-Human Species, held in Ottawa, Canada, December 1 and 2, 1996. The Symposium was held in response to the assessment of radiological impacts from nuclear facilities on non-human biota by Environment Canada and the move by Atomic Energy Control Board to include the radiological impacts in its regulatory regime. The two major goals of the Symposium were to critically evaluate the ecological risk assessment as applied to radionuclides and contribute to the wide consultation sought by the Atomic Energy Control Board on their new environmental initiatives. The series of papers presented at the Symposium discuss issues relevant to the two major objectives of the Symposium

Proceedings of the 3. Regional Meeting on Radiological and Nuclear Safety. Radiological protection in Latin America and the Caribbean. Vol. 1,2; Actas del 3. Congreso Regional sobre Seguridad Radiologica y Nuclear. Proteccion Radiologica en America Latina y el Caribe. Vol. 1,2

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-08-01

Two volumes contain more than 183 complete papers presented during the Third Regional Meeting on Radiological Protection and Nuclear Safety held on 23-27 October, 1995 in Cusco-Peru. Latin american specialist talk about nuclear safety and radiological protection, radiation natural exposure, biological effect of radiation, radiotherapy and medical radiological safety, radiological safety in industry and research. Also we deal with subjects related to radiological safety of nuclear and radioactive facilities, radioactive waste management, radioactive material transport, environmental radiological monitoring program, radiological emergency and accidents, instruments and dosimetry, basic safety standards of protection against radiation.

Radiological and environmental consequences. Final report of the Nordic Nuclear Safety Research project BOK-2

International Nuclear Information System (INIS)

Palsson, S.E.

2002-11-01

Final report of the Nordic Nuclear Safety Research project BOK-2, Radiological and Environmental Consequences. The project was carried out 1998-2001 with participants from all the Nordic countries. Representatives from the Baltic States were also invited to some of the meetings and seminars. The project consisted of work on terrestrial and marine radioecology and had a broad scope in order to enable participation of research groups with various fields of interest. This report focuses on the project itself and gives a general summary of the studies undertaken. A separate technical report summarises the work done by each research group and gives references to papers published in scientific journals. The topics in BOK-2 included improving assessment of old and recent fallout, use of radionuclides as tracers in Nordic marine areas, improving assessment of internal doses and use of mass spectrometry in radioecology. (au)

Lower limit of detection: definition and elaboration of a proposed position for radiological effluent and environmental measurements

International Nuclear Information System (INIS)

Currie, L.A.

1984-09-01

A manual is provided to define and illustrate a proposed use of the Lower Limit of Detection (LLD) for Radiological Effluent and Environmental Measurements. The manual contains a review of information regarding LLD practices gained from site visits; a review of the literature and a summary of basic principles underlying the concept of detection in Nuclear and Analytical Chemistry; a detailed presentation of the application of LLD principles to a range of problem categories (simple counting to multinuclide spectroscopy), including derivations, equations, and numerical examples; and a brief examination of related issues such as reference samples, numerical quality control, and instrumental limitations. An appendix contains a summary of notation and terminology, a bibliography, and worked-out examples. 100 references, 10 figures, 7 tables

Radiology fundamentals

CERN Document Server

Singh, Harjit

2011-01-01

""Radiology Fundamentals"" is a concise introduction to the dynamic field of radiology for medical students, non-radiology house staff, physician assistants, nurse practitioners, radiology assistants, and other allied health professionals. The goal of the book is to provide readers with general examples and brief discussions of basic radiographic principles and to serve as a curriculum guide, supplementing a radiology education and providing a solid foundation for further learning. Introductory chapters provide readers with the fundamental scientific concepts underlying the medical use of imag

Environmental surveillance in the Marshall Islands: an application of alternative energy sources in the Third World

International Nuclear Information System (INIS)

Greenhouse, N.A. Jr.

1980-01-01

Recent assessments of potential radiation exposure pathways at Bikini and Enewetak have indicated that doses in excess of current radiation protection guidelines are possible or even likely for persons living in these areas. Rongelap and Utirik Atolls, which were downwind of the 1954 BRAVO event, also received significant fallout; potential radiological problems exist in these areas as well. In view of this prospect, followup environmental monitoring and personnel monitoring programs are being established to maintain our cognizance of radiological conditions, and to take corrective action where necessary. Various aspects of this program require the operation of scientific equipment in remote areas which have no electrical power. In order to solve this problem, windpowered electrical generators were installed on three islands in a planned program through which they will be turned over to the local inhabitants for community use after about two years. This paper describes environmental surveillance efforts for the inhabitants of Pacific Islands who were the recipients of radioactive fallout from US nuclear weapons tests in the Pacific

Nevada Test Site Environmental Report 2007

Energy Technology Data Exchange (ETDEWEB)

Cathy Wills

2008-09-01

The Nevada Test Site Environmental Report 2007 (NTSER) was prepared to meet the information needs of the public and the requirements and guidelines of the U.S. Department of Energy (DOE) for annual site environmental reports. It was prepared by National Security Technologies, LLC (NSTec). This Executive Summary presents the purpose of the document, the major programs conducted at the Nevada Test Site (NTS), NTS key environmental initiatives, radiological releases and potential doses to the public resulting from site operations, a summary of nonradiological releases, implementation status of the NTS Environmental Management System, a summary of compliance with environmental regulations, pollution prevention and waste minimization accomplishments, and significant environmental accomplishments. Much of the content of this Executive Summary is also presented in a separate stand-alone pamphlet titled Nevada Test Site Environmental Report Summary 2007. This NTSER was prepared to satisfy DOE Order 231.1A, Environment, Safety and Health Reporting. Its purpose is to (1) report compliance status with environmental standards and requirements, (2) present results of environmental monitoring of radiological and nonradiological effluents, (3) report estimated radiological doses to the public from releases of radioactive material, (4) summarize environmental incidents of noncompliance and actions taken in response to them, (5) describe the NTS Environmental Management System and characterize its performance, and (6) highlight significant environmental programs and efforts. This report meets these objectives for the NTS and three offsite Nevada facilities mentioned in this report.

Nevada Test Site Environmental Report 2007

International Nuclear Information System (INIS)

Cathy Wills

2008-01-01

The Nevada Test Site Environmental Report 2007 (NTSER) was prepared to meet the information needs of the public and the requirements and guidelines of the U.S. Department of Energy (DOE) for annual site environmental reports. It was prepared by National Security Technologies, LLC (NSTec). This Executive Summary presents the purpose of the document, the major programs conducted at the Nevada Test Site (NTS), NTS key environmental initiatives, radiological releases and potential doses to the public resulting from site operations, a summary of nonradiological releases, implementation status of the NTS Environmental Management System, a summary of compliance with environmental regulations, pollution prevention and waste minimization accomplishments, and significant environmental accomplishments. Much of the content of this Executive Summary is also presented in a separate stand-alone pamphlet titled Nevada Test Site Environmental Report Summary 2007. This NTSER was prepared to satisfy DOE Order 231.1A, Environment, Safety and Health Reporting. Its purpose is to (1) report compliance status with environmental standards and requirements, (2) present results of environmental monitoring of radiological and nonradiological effluents, (3) report estimated radiological doses to the public from releases of radioactive material, (4) summarize environmental incidents of noncompliance and actions taken in response to them, (5) describe the NTS Environmental Management System and characterize its performance, and (6) highlight significant environmental programs and efforts. This report meets these objectives for the NTS and three offsite Nevada facilities mentioned in this report

The Generalised Ecosystem Modelling Approach in Radiological Assessment

Energy Technology Data Exchange (ETDEWEB)

Klos, Richard

2008-03-15

An independent modelling capability is required by SSI in order to evaluate dose assessments carried out in Sweden by, amongst others, SKB. The main focus is the evaluation of the long-term radiological safety of radioactive waste repositories for both spent fuel and low-level radioactive waste. To meet the requirement for an independent modelling tool for use in biosphere dose assessments, SSI through its modelling team CLIMB commissioned the development of a new model in 2004, a project to produce an integrated model of radionuclides in the landscape. The generalised ecosystem modelling approach (GEMA) is the result. GEMA is a modular system of compartments representing the surface environment. It can be configured, through water and solid material fluxes, to represent local details in the range of ecosystem types found in the past, present and future Swedish landscapes. The approach is generic but fine tuning can be carried out using local details of the surface drainage system. The modular nature of the modelling approach means that GEMA modules can be linked to represent large scale surface drainage features over an extended domain in the landscape. System change can also be managed in GEMA, allowing a flexible and comprehensive model of the evolving landscape to be constructed. Environmental concentrations of radionuclides can be calculated and the GEMA dose pathway model provides a means of evaluating the radiological impact of radionuclide release to the surface environment. This document sets out the philosophy and details of GEMA and illustrates the functioning of the model with a range of examples featuring the recent CLIMB review of SKB's SR-Can assessment

The Generalised Ecosystem Modelling Approach in Radiological Assessment

International Nuclear Information System (INIS)

Klos, Richard

2008-03-01

An independent modelling capability is required by SSI in order to evaluate dose assessments carried out in Sweden by, amongst others, SKB. The main focus is the evaluation of the long-term radiological safety of radioactive waste repositories for both spent fuel and low-level radioactive waste. To meet the requirement for an independent modelling tool for use in biosphere dose assessments, SSI through its modelling team CLIMB commissioned the development of a new model in 2004, a project to produce an integrated model of radionuclides in the landscape. The generalised ecosystem modelling approach (GEMA) is the result. GEMA is a modular system of compartments representing the surface environment. It can be configured, through water and solid material fluxes, to represent local details in the range of ecosystem types found in the past, present and future Swedish landscapes. The approach is generic but fine tuning can be carried out using local details of the surface drainage system. The modular nature of the modelling approach means that GEMA modules can be linked to represent large scale surface drainage features over an extended domain in the landscape. System change can also be managed in GEMA, allowing a flexible and comprehensive model of the evolving landscape to be constructed. Environmental concentrations of radionuclides can be calculated and the GEMA dose pathway model provides a means of evaluating the radiological impact of radionuclide release to the surface environment. This document sets out the philosophy and details of GEMA and illustrates the functioning of the model with a range of examples featuring the recent CLIMB review of SKB's SR-Can assessment

Aging in Context: Individual and Environmental Pathways to Aging-Friendly Communities-The 2015 Matthew A. Pollack Award Lecture.

Science.gov (United States)

Scharlach, Andrew E

2017-08-01

Reflecting the theme of the 2015 Gerontological Society of America (GSA) Annual Scientific Meeting, "Aging as a Lifelong Process," this paper examines intersections between aging processes and their environmental context, develops theory regarding constructive developmental processes and their environmental context, and considers potential implications for conceptualizing and creating aging-friendly communities. The first section examines the primary goals of aging-friendly communities, that is, promoting elder well-being. The second section explores the role of environmental pathways in fostering well-being throughout the lifecourse. The third section presents a new Process Model of Constructive Aging that identifies key developmental processes at the intersection of individual and environmental pathways. The final section considers potential implications for creating aging-friendly communities, including ways in which cities and towns can promote the ability of community members to live fully throughout their lives, and identifies some key conceptual and empirical challenges affecting the future of the field. © The Author 2017. Published by Oxford University Press on behalf of The Gerontological Society of America. All rights reserved. For permissions, please e-mail: journals.permissions@oup.com.

Environmental radioactivity survey in Andong

Energy Technology Data Exchange (ETDEWEB)

Yoon, Zi Hong; Jo, Kum Ju [Andong Regional Radioactivity Monitoring Station, Andong National Univ., Andong (Korea, Republic of)

2003-12-15

The objectives of the project are to monitor an abnormal level in Andong area and to provide a base line data on environmental radiation/radioactivity levels in case of any radiological emergency situation. The project is important in view of protecting the public health from the potential hazards of radiation and keeping up the clean environment. This report simonizes and interprets environmental radiation/radioactivity monitoring samples : Gamma exposure rates, airborne dust, precipitation, fall out and drinking-water. Environmental samples 2 kinds of indicator plant, 4 kinds of mushroom, 7 kinds of nut and seeds, and drinking waters. Among the all 2003 radiological monitoring and environmental data in Andong area were not found the extraordinary data. And a nation-wide environmental radiation/radioactivity level survey results were all background levels attributed to terrestrial and cosmic radiation.

Environmental radioactivity survey in Andong

Energy Technology Data Exchange (ETDEWEB)

Yoon, Zi Hong; Jo, Kum Ju [Andong Regional Radioactivity Monitoring Station, Andong National Univ., Andong (Korea, Republic of)

2002-12-15

The objectives of the project are to monitor an abnormal level in Andong area and to provide a base-line data on environmental radiation/radioactivity levels in case of any radiological emergency situation. The project is important in view of protecting the public health from the potential hazards of radiation and keeping up the clean environment. This report summarizes and interprets environmental radiation/radioactivity monitoring samples Gamma exposure rates, airborne dust, precipitation, fall-out and drinking-water. Environmental samples 2 kinds of indicator plant, 4 kinds of mushroom, 7 kinds of nut and seeds, and drinking waters. Among the all 2002 radiological monitoring and environmental data in Andong area were not found the extraordinary data. And a nation-wide environmental radiation/radioactivity level survey results were all background levels attributed to terrestrial and cosmic radiation.

assessment of radiological hazard indices from surface soil to ...

African Journals Online (AJOL)

samples in Eagle, Atlas and rock cement companies in Port Harcourt was carried out by ... and external hazard indices in order to assess the radiological implication to the people .... Sciences & Environmental Management, Vol. 9, No. 3, pp.

Informal E-waste recycling in developing countries: review of metal(loid)s pollution, environmental impacts and transport pathways.

Science.gov (United States)

Ackah, Michael

2017-11-01

Crude or primitive recycling practices are often adopted in material resource recovery from E-waste in developing nations. Significant human health and environmental impacts may occur because of such practices. Literature on metal(loid)s pollution during E-waste processing is fragmented. Here, I review the health and environmental impacts of E-waste recycling operations and transport pathways of metal(loid)s, dispersed during operations. This paper is organised into five sections. Section 1 relates to the background of global E-waste generation and legal/illegal trade, citing specific cases from Ghana and other developing nations. Section 2 provides a brief information on sources of metal(loid)s in E-waste. Section 3 describes characteristics of informal E-waste recycling operations in developing nations. Section 4 examines the health and environmental impacts in E-waste recycling while section 5 evaluates major transport pathways of metal(loid)s contaminants.

Radiological safety and control

International Nuclear Information System (INIS)

Kim, Jang Hee; Kim, Ki Sub

1995-01-01

The practical objective of radiological safety control is intended for achievement and maintenance of appropreately safe condition in environmental control for activities involving exposure from the use of radiation. In order to establish these objectives, we should be to prevent deterministic effects and to limit the occurrence stochastic effects to level deemed to be acceptable by the application of general principles of radiation protection and systems of dose limitation based on ICRP recommendations. 34 tabs., 19 figs., 11 refs. (Author) .new

Poul Erik Andersen's radiological work on Osteochondrodysplasias and interventional radiology

DEFF Research Database (Denmark)

Andersen, Poul Erik

2011-01-01

Hospital. His significant experience and extensive scientific work has led to many posts in the Danish Society of Interventional Radiology, the European Society of Radiology and the Cardiovascular and Interventional Radiological Society of Europe, where he is a fellow and has passed the European Board...... of Interventional Radiology - The European qualification in Interventional Radiology....

The use of comparative 137Cs body burden estimates from environmental data/models and whole body counting to evaluate diet models for the ingestion pathway

International Nuclear Information System (INIS)

Robison, W.L.; Sun, C.

1997-01-01

Rongelap and Utirik Atolls were contaminated on 1 March 1954, by a U.S. nuclear test at Bikini Atoll code named BRAVO. The people at both atolls were removed from their atolls in the first few days after the detonation and were returned to their atolls at different times. Detailed studies have been carried out over the years by Lawrence Livermore National Laboratory (LLNL) to determine the radiological conditions at the atolls and estimate the doses to the populations. The contribution of each exposure pathway and radionuclide have been evaluated. All dose assessments show that the major potential contribution to the estimated dose is 137 Cs uptake via the terrestrial food chain. Brookhaven National Laboratory (BNL) has carried out an extensive whole body counting program at both atolls over several years to directly measure the 137 Cs body burden. Here we compare the estimates of the body burdens from the LLNL environmental method with body burdens measured by the BNL whole body counting method. The combination of the results from both methods is used to evaluate proposed diet models to establish more realistic dose assessments. Very good agreement is achieved between the two methods with a diet model that includes both local and imported foods. Other diet models greatly overestimate the body burdens (i.e., dose) observed by whole body counting. The upper 95% confidence limit of interindividual variability around the population mean value based on the environmental method is similar to that calculated from direct measurement by whole body counting. Moreover, the uncertainty in the population mean value based on the environmental method is in very good agreement with the whole body counting data. This provides additional confidence in extrapolating the estimated doses calculated by the environmental method to other islands and atolls. 46 refs., 8 figs., 5 tabs

Nuclear law and radiological accidents

International Nuclear Information System (INIS)

Frois, F.

1998-01-01

Nuclear activities in Brazil, and particularly the radiological accident of Goiania, are examined in the light of the environmental and nuclear laws of Brazil and the issue of responsibility. The absence of legislation covering radioactive wastes as well as the restrictions on Brazilian States to issue regulations covering nuclear activities are reviewed. The radiological accident and its consequences, including the protection and compensation of the victims, the responsibility of the shareholders of the Instituto Goiano de Radioterapia, operator of the radioactive source, the provisional storage and the final disposal at Abadia de Goias of the radioactive waste generated by the accident are reviewed. Finally, nuclear responsibility, the inapplicability of the Law 6453/77 which deals with nuclear damages, and the state liability regime are analysed in accordance with the principles of the Brazilian Federal Constitution. (author)

Sampling on radiological protection training in diagnostic radiology

International Nuclear Information System (INIS)

Gaona, E.

2001-01-01

Radiological security aspects were evaluated in radiology departments from Mexico City. The study was carried out in two stages, the first one evaluated 40 departments just before the implementation of the new Official Mexican Standards related to Radiological Security and Quality Control in Radiology; in the second stage 33 departments were evaluated 2 years after those standards were implanted, showing a favorable impact of the training programs for the type of answers obtained [es

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

International Nuclear Information System (INIS)

1978-02-01

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

Qualitative evaluation of environmental radiological impact in a phosphate associated uranium conventional mine: Santa Quiteria Project, CE, Brazil

International Nuclear Information System (INIS)

Reis, Rocio G. dos; Santo, Aline Sa E.

2013-01-01

The aim of this study is to identify and evaluate qualitatively the main potential sources of mineral and installation terms of Santa Quiteria, CE, Brazil, evaluating their possible impacts on the environment. The key terms sources in the production of phosphoric acid are usually: the dig of the mines, tailings dams and phospho plaster stack. Thus, this work intends to inform the academic community about this issue, as well as the population in general and also, acting proactively in order to warn about the possible environmental impacts, so that actions to compensate, minimize or avoid these radiological impacts on the environment, can be included in the planning of the industrial mineral project of Santa Quiteria (author)

Radiological Environmental Protection for LCLS-II High Power Operation

Directory of Open Access Journals (Sweden)

Liu James

2017-01-01

Full Text Available The LCLS-II superconducting electron accelerator at SLAC plans to operate at up to 4 GeV and 240 kW average power, which would create higher radiological impacts particularly near the beam loss points such as beam dumps and halo collimators. The main hazards to the public and environment include direct or skyshine radiation, effluent of radioactive air such as 13N, 15O and 41Ar, and activation of groundwater creating tritium. These hazards were evaluated using analytic methods and FLUKA Monte Carlo code. The controls (mainly extensive bulk shielding and local shielding around high loss points and monitoring (neutron/photon detectors with detection capabilities below natural background at site boundary, site-wide radioactive air monitors, and groundwater wells were designed to meet the U.S. DOE and EPA, as well as SLAC requirements. The radiological design and controls for the LCW systems [including concrete housing shielding for 15O and 11C circulating in LCW, 7Be and erosion/corrosion products (22Na, 54Mn, 60Co, 65Zn, etc. captured in resin and filters, leak detection and containment of LCW with 3H and its waste water discharge; explosion from H2 build-up in surge tank and release of radionuclides] associated with the high power beam dumps are also presented.

Putting tailings in perspective radiologically, environmentally and managerially

International Nuclear Information System (INIS)

Shreve, J.D. Jr.

1978-01-01

Present management of uranium mill tailings is sophisticated compared with recounted practises of 15 to 20 years ago. Further improvements while possible and wanted should not be rushed. Many factors enter. The paper suggests routes to selecting radiological protective standards, elucidates the site-specific and process-specific nature of tailings control, provides comparative references on source terms of radon, uranium, thorium and radium, defends the need for multiple control and for plan endorsement in perpetuity once approval is granted, except as improved control at lesser cost proves doable. One idea is proffered for reducing tailings mass to one-third that accumulated by current practises

Chronicle of pediatric radiology

International Nuclear Information System (INIS)

Benz-Bohm, Gabriele; Richter, Ernst

2012-01-01

The chronicle of pediatric radiology covers the following issues: Development of pediatric radiology in Germany (BRD, DDR, pediatric radiological accommodations); development of pediatric radiology in the Netherlands (chronology and pediatric radiological accommodations); development of pediatric radiology in Austria (chronology and pediatric radiological accommodations); development of pediatric radiology in Switzerland (chronology and pediatric radiological accommodations).

Role of the Federal Radiological Monitoring and Assessment Center (FRMAC) following a radiological accident

International Nuclear Information System (INIS)

Doyle, J.F. III.

1986-01-01

The Federal Radiological Emergency Response Plan (FRERP) calls for the Department of Energy to establish a Federal Radiological Monitoring and Assessment Center (FRMAC) immediately following a major radiological accident to coordinate all federal off-site monitoring efforts in support of the State and the Cognizant Federal Agency (CFA) for the facility or material involved in the accident. Some accidents are potentailly very complex and may require hundreds of radiation specialists to ensure immediate protection of the public and workers in the area, and to identify priorities for the Environmental Protection Agency (EPA) long-term efforts once the immediate protective actions have been carried out. The FRMAC provides a working environment with today's high technology tools (i.e., communication, computers, management procedures, etc.) to assure that the State and CFA decision makers have the best possible information in a timely manner on which to act. The FRMAC planners also recognize an underlying responsibility to continuously document such operations in order to provide the State, the CFA, and the EPA the technical information they will require for long term assessments. In addition, it is fully recognized that information collected and actions taken by the FRMAC will be subjected to the same scrutiny as other parts of the accident and the overall response

Radiological dose assessment of Department of Energy Pinellas Plant waste proposed for disposal at Laidlaw Environmental Services of South Carolina, Inc

International Nuclear Information System (INIS)

Socolof, M.L.; Lee, D.W.

1996-05-01

The U.S. Department of Energy (DOE) Pinellas Plant in Largo, FL is proposing to ship and dispose of hazardous sludge, listed as F006 waste, to the Laidlaw Environmental Services of South Carolina, Inc. (Laidlaw) treatment, storage, and disposal facility in Pinewood, South Carolina. This sludge contains radioactive tritium in concentrations of about 28 pCi/g. The objective of this study is to assess the possible radiological impact to workers at the Laidlaw facility and members of the public due to the handling, processing, and burial of the DOE waste containing tritium

Radiological dose assessment of Department of Energy Pinellas Plant waste proposed for disposal at Laidlaw Environmental Services of South Carolina, Inc.

Energy Technology Data Exchange (ETDEWEB)

Socolof, M.L.; Lee, D.W.

1996-05-01

The U.S. Department of Energy (DOE) Pinellas Plant in Largo, FL is proposing to ship and dispose of hazardous sludge, listed as F006 waste, to the Laidlaw Environmental Services of South Carolina, Inc. (Laidlaw) treatment, storage, and disposal facility in Pinewood, South Carolina. This sludge contains radioactive tritium in concentrations of about 28 pCi/g. The objective of this study is to assess the possible radiological impact to workers at the Laidlaw facility and members of the public due to the handling, processing, and burial of the DOE waste containing tritium.

Imaging and radiology

Science.gov (United States)

Interventional radiology; Diagnostic radiology; X-ray imaging ... DIAGNOSTIC RADIOLOGY Diagnostic radiology helps health care professionals see structures inside your body. Doctors that specialize in the interpretation ...

The Idaho National Engineering Laboratory site environmental report for calendar year 1989

International Nuclear Information System (INIS)

Hoff, D.L.; Mitchell, R.G.; Bowman, G.C.; Moore, R.

1990-06-01

To verify that exposures resulting from operations at the Department of Energy (DOE) nuclear facilities have remained very small, each site at which nuclear activities are underway operates an environmental surveillance program to monitor the air, water and any other pathway where radionuclides from operations might conceivably reach workers or members of the public. This report presents data collected in 1989 for the routine environmental surveillance program conducted by the Radiological and Environmental Sciences Laboratory (RESL) of DOE and the US Geological Survey (USGS) at the Idaho National Engineering Laboratory (INEL) site. The environmental surveillance program for the INEL and vicinity for 1989 included the collection and analysis of samples from potential exposure pathways. Three basic groups of samples were collected. Those collected within the INEL boundaries will be referred to as onsite samples. Samples collected outside, but near, the Site boundaries will be referred to as boundary samples or part of a group of offsite samples. Samples collected from locations considerably beyond the Site boundaries will be referred to as distant samples or part of the offsite group. With the exception of Craters of the Moon National Monument, the distant locations are sufficiently remote from the Site to ensure that detectable radioactivity is primarily due to natural background sources or sources other than INEL operations. 35 refs., 14 figs., 13 tabs

CUEX methodology for assessing radiological impacts in the context of ICRP Recommendations

International Nuclear Information System (INIS)

Rohwer, P.S.; Kaye, S.V.; Struxness, E.G.

1975-01-01

The Cumulative Exposure Index (CUEX) methodology was developed to estimate and assess, in the context of International Commission on Radiological Protection (ICRP) Recommendations, the total radiation dose to man due to environmental releases of radioactivity from nuclear applications. Each CUEX, a time-integrated radionuclide concentration (e.g.μCi.h.cm -3 ), reflects the selected annual dose limit for the reference organ and the estimated total dose to that organ via all exposure modes for a specific exposure situation. To assess the radiological significance of an environmental release of radioactivity, calculated or measured radionuclide concentrations in a suitable environmental sampling medium are compared with CUEXs determined for that medium under comparable conditions. The models and computer codes used in the CUEX methodology to predict environmental transport and to estimate radiation dose have been thoroughly tested. These models and codes are identified and described briefly. Calculation of a CUEX is shown step by step. An application of the methodology to a hypothetical atmospheric release involving four radionuclides illustrates use of the CUEX computer code to assess the radiological significance of a release, and to determine the relative importance (i.e. percentage of the estimated total dose contributed) of each radionuclide and each mode of exposure. The data requirements of the system are shown to be extensive, but not excessive in view of the assessments and analyses provided by the CUEX code. (author)

GENII: The Hanford Environmental Radiation Dosimetry Software System: Volume 1, Conceptual representation

Energy Technology Data Exchange (ETDEWEB)

Napier, B.A.; Peloquin, R.A.; Strenge, D.L.; Ramsdell, J.V.

1988-12-01

The Hanford Environmental Dosimetry Upgrade Project was undertaken to incorporate the internal dosimetry models recommended by the International Commission on Radiological Protection (ICRP) in updated versions of the environmental pathway analysis models used at Hanford. The resulting second generation of Hanford environmental dosimetry computer codes is compiled in the Hanford Environmental Dosimetry System (Generation II, or GENII). The purpose of this coupled system of computer codes is to analyze environmental contamination resulting from acute or chronic releases to, or initial contamination of, air, water, or soil. This is accomplished by calculating radiation doses to individuals or populations. GENII is described in three volumes of documentation. The first volume describes the theoretical considerations of the system. The second volume is a Users' Manual, providing code structure, users' instructions, required system configurations, and QA-related topics. The third volume is a Code Maintenance Manual for the user who requires knowledge of code detail. It includes code logic diagrams, global dictionary, worksheets, example hand calculations, and listings of the code and its associated data libraries. 72 refs., 15 figs., 34 tabs.

GENII: The Hanford Environmental Radiation Dosimetry Software System: Volume 1, Conceptual representation

International Nuclear Information System (INIS)

Napier, B.A.; Peloquin, R.A.; Strenge, D.L.; Ramsdell, J.V.

1988-12-01

The Hanford Environmental Dosimetry Upgrade Project was undertaken to incorporate the internal dosimetry models recommended by the International Commission on Radiological Protection (ICRP) in updated versions of the environmental pathway analysis models used at Hanford. The resulting second generation of Hanford environmental dosimetry computer codes is compiled in the Hanford Environmental Dosimetry System (Generation II, or GENII). The purpose of this coupled system of computer codes is to analyze environmental contamination resulting from acute or chronic releases to, or initial contamination of, air, water, or soil. This is accomplished by calculating radiation doses to individuals or populations. GENII is described in three volumes of documentation. The first volume describes the theoretical considerations of the system. The second volume is a Users' Manual, providing code structure, users' instructions, required system configurations, and QA-related topics. The third volume is a Code Maintenance Manual for the user who requires knowledge of code detail. It includes code logic diagrams, global dictionary, worksheets, example hand calculations, and listings of the code and its associated data libraries. 72 refs., 15 figs., 34 tabs

The importance of recording physical and chemical variables simultaneously with remote radiological surveillance of aquatic systems: a perspective for environmental modelling

International Nuclear Information System (INIS)

Abril, J.M.; El-Mrabet, R.; Barros, H.

2004-01-01

Modern nuclear metrological tools allow the remote surveillance of the radiological status of the aquatic systems, providing an important advance in the protection of the environment. Nevertheless, the significance of the radiological data could be highly improved through simultaneous recording of physical and chemical variables that govern the behaviour and bioavailability of radionuclides in these aquatic systems. This work reviews some of these variables from the point of view of the environmental modelling. The amount, nature and dynamics of the suspended loads and bottom sediments strongly influence the behaviour of particle-reactive radionuclides. The kinetics of this process has a very fast component, as it is shown from our recent studies with 241 Am, 239 Pu and 133 Ba in several aquatic systems from southern Spain. Changes in pH, temperature and in the electrical conductivity are influencing the uptake kinetics and the final partitioning of the radioactivity. Water currents govern the radionuclide transport and dispersion. These points are illustrated with modelling exercises in the scenarios of the Suez Canal (Egypt) and the Haersvatten Lake (Sweden)

Radiological Control Manual

Energy Technology Data Exchange (ETDEWEB)

1993-04-01

This manual has been prepared by Lawrence Berkeley Laboratory to provide guidance for site-specific additions, supplements, and clarifications to the DOE Radiological Control Manual. The guidance provided in this manual is based on the requirements given in Title 10 Code of Federal Regulations Part 835, Radiation Protection for Occupational Workers, DOE Order 5480.11, Radiation Protection for Occupational Workers, and the DOE Radiological Control Manual. The topics covered are (1) excellence in radiological control, (2) radiological standards, (3) conduct of radiological work, (4) radioactive materials, (5) radiological health support operations, (6) training and qualification, and (7) radiological records.

Radiological Control Manual

International Nuclear Information System (INIS)

1993-04-01

This manual has been prepared by Lawrence Berkeley Laboratory to provide guidance for site-specific additions, supplements, and clarifications to the DOE Radiological Control Manual. The guidance provided in this manual is based on the requirements given in Title 10 Code of Federal Regulations Part 835, Radiation Protection for Occupational Workers, DOE Order 5480.11, Radiation Protection for Occupational Workers, and the DOE Radiological Control Manual. The topics covered are (1) excellence in radiological control, (2) radiological standards, (3) conduct of radiological work, (4) radioactive materials, (5) radiological health support operations, (6) training and qualification, and (7) radiological records

Radiological English

Energy Technology Data Exchange (ETDEWEB)

Ribes, R. [Hospital Reina Sofia, Cordoba (Spain). Servicio de Radiologia; Ros, P.R. [Harvard Medical School, Boston, MA (United States). Div. of Radiology

2007-07-01

The book is an introductory book to radiological English on the basis that there are a lot of radiologists, radiology residents, radiology nurses, radiology students, and radiographers worldwide whose English level is indeterminate because their reading skills are much higher than their fluency. It is intended to help those health care professionals who need English for their work but do not speak English on a day-to-day basis. (orig.)

Radiological English

International Nuclear Information System (INIS)

Ribes, R.; Ros, P.R.

2007-01-01

The book is an introductory book to radiological English on the basis that there are a lot of radiologists, radiology residents, radiology nurses, radiology students, and radiographers worldwide whose English level is indeterminate because their reading skills are much higher than their fluency. It is intended to help those health care professionals who need English for their work but do not speak English on a day-to-day basis. (orig.)

Handbook of radiologic procedures

International Nuclear Information System (INIS)

Hedgcock, M.

1986-01-01

This book is organized around radiologic procedures with each discussed from the points of view of: indications, contraindications, materials, method of procedures and complications. Covered in this book are: emergency radiology chest radiology, bone radiology, gastrointestinal radiology, GU radiology, pediatric radiology, computerized tomography, neuroradiology, visceral and peripheral angiography, cardiovascular radiology, nuclear medicine, lymphangiography, and mammography

Guidelines for Remediation Strategies to Reduce the Radiological Consequences of Environmental Contamination

Energy Technology Data Exchange (ETDEWEB)

Fesenko, S; Howard, B J [eds.

2012-11-15

There are many areas around the world contaminated with radioactive substances which may require remediation. The source of contamination with radionuclides varies; the most important sources include nuclear testing, radiation accidents and inadequate waste disposal practices. Contamination at such sites may present a risk to humans and the environment. Therefore, issues related to remediation of such sites are potentially of concern for both the general public and a wide variety of stakeholders. In response to the needs of its Member States, the IAEA has published many books covering different aspects of remediation of contaminated environments. These books range from safety fundamentals and safety requirements to technical publications describing remedial technologies. Almost all of the publications on environmental remediation are related to uranium mining areas and decommissioning of nuclear facilities. IAEA radiation safety standards on remediation of contaminated environments are largely based on these two types of remediation. The exception is a publication that was a joint undertaking by the IAEA and the Food and Agriculture Organization of the United Nations (FAO) related to accidents entitled Guidelines for Agricultural Countermeasures Following an Accidental Release of Radionuclides, Technical Reports Series No. 363 (1994) (TRS 363). This publication has constituted a major source of information over many years for staff of authorities providing environmental remediation planning after accidents. TRS 363 focused mainly on agricultural management options following an accidental release of radionuclides; remedial actions for other environments and other practices were not considered. Since the publication of TRS 363, there has been a considerable increase in relevant information. Given the importance of Chernobyl and other accidents, there have been a considerable number of IAEA activities devoted to the remediation of radiation accidents since 1994. Many

Guidelines for Remediation Strategies to Reduce the Radiological Consequences of Environmental Contamination

International Nuclear Information System (INIS)

Fesenko, S.; Howard, B.J.

2012-01-01

There are many areas around the world contaminated with radioactive substances which may require remediation. The source of contamination with radionuclides varies; the most important sources include nuclear testing, radiation accidents and inadequate waste disposal practices. Contamination at such sites may present a risk to humans and the environment. Therefore, issues related to remediation of such sites are potentially of concern for both the general public and a wide variety of stakeholders. In response to the needs of its Member States, the IAEA has published many books covering different aspects of remediation of contaminated environments. These books range from safety fundamentals and safety requirements to technical publications describing remedial technologies. Almost all of the publications on environmental remediation are related to uranium mining areas and decommissioning of nuclear facilities. IAEA radiation safety standards on remediation of contaminated environments are largely based on these two types of remediation. The exception is a publication that was a joint undertaking by the IAEA and the Food and Agriculture Organization of the United Nations (FAO) related to accidents entitled Guidelines for Agricultural Countermeasures Following an Accidental Release of Radionuclides, Technical Reports Series No. 363 (1994) (TRS 363). This publication has constituted a major source of information over many years for staff of authorities providing environmental remediation planning after accidents. TRS 363 focused mainly on agricultural management options following an accidental release of radionuclides; remedial actions for other environments and other practices were not considered. Since the publication of TRS 363, there has been a considerable increase in relevant information. Given the importance of Chernobyl and other accidents, there have been a considerable number of IAEA activities devoted to the remediation of radiation accidents since 1994. Many

Environmental design of the Olympic Dam operations

International Nuclear Information System (INIS)

Middleton, B.A.

1989-01-01

Environmental Design of The Olympic Dam Operations has been required to take into account the Environmental Management Programme as approved by the South Australian Government and radiological protection standards as determined by the Commonwealth of Australia's Code of Practice on Radiation Protection in the Mining and Milling of Radioactive Ores 1987. The article describes the natural environment, project assessment and infrastructure relating to the environmental design. The radiological standards refer to the control of exposure to radiation above naturally occurring background levels both for employees and for members of the public. 2 tabs., maps

RSVP radiology

International Nuclear Information System (INIS)

Kirks, D.R.; Chaffee, D.J.

1990-01-01

This paper develops a relative scale of value for pediatric radiology (RSVPR). Neither the HCFA/ACA Relative Value Scale nor the Workload Measurement System developed by Health and Welfare Canada specifically addressed pediatric radiologic examinations. Technical and professional charges for examinations at Children's Hospital Medical Center were reviewed and compared with time and cost analysis. A scale was developed with chest radiography (PA and lateral views) assigned a value of 1. After review by pediatric radiologic technologists, radiologic administrators, pediatric radiologists, and chairs of departments of children's hospitals, this proposed scale was modified to reflect more accurately relative value components of pediatric radiologic and imaging examinations

Radiological protection report 2012

International Nuclear Information System (INIS)

2013-06-01

measurements. In addition, the Swiss Federal Office of Public Health publishes environmental monitoring data in its Annual Report. For the purpose of monitoring environmental radioactivity, ENSI operates a network that automatically monitors dose rates in the vicinity of nuclear power plants. The results are made available to the Swiss National Emergency Operations Centre, the Ministry of the Environment in Baden-Wuerttemberg and the European Radiological Data Exchange Platform. In 2012 emissions from Swiss nuclear facilities are similar to those in previous years and in the immediate vicinity of nuclear facilities the annual dose is less than 10μSv. However, the water-borne releases of radiation from the Muehleberg nuclear power station, unlike those at other nuclear facilities, continue to be so high that further remedial measures are required. In the field of dispersion, hourly simulations are calculated for all locations in the vicinity of a nuclear power station. They are based on current 3D wind speeds as provided by MeteoSwiss with a spatial resolution of 2 km. These calculations, together with the annual aero-radiometric test flights, are a valuable and precise tool that can be used at any time to analyse the current situation and forecast the development of radiation

Radiological anatomy - evaluation of integrative education in radiology.

Science.gov (United States)

Dettmer, S; Schmiedl, A; Meyer, S; Giesemann, A; Pabst, R; Weidemann, J; Wacker, F K; Kirchhoff, T

2013-09-01

Evaluation and analysis of the integrative course "Radiological Anatomy" established since 2007 at the Medical School Hannover (MHH) in comparison with conventional education. Anatomy and radiology are usually taught separately with a considerable time lag. Interdisciplinary teaching of these associated subjects seems logical for several reasons. Therefore, the integrative course "Radiological Anatomy" was established in the second year of medical education, combining these two closely related subjects. This interdisciplinary course was retrospectively evaluated by consideration of a student questionnaire and staff observations. The advantages and disadvantages of integrative teaching in medical education are discussed. The course ratings were excellent (median 1; mean 1.3 on a scale of 1 to 6). This is significantly (p radiology increased during the course (88 %). According to the students' suggestions the course was enhanced by a visitation in the Department of Radiology and the additional topic central nervous system. Integrative teaching of anatomy and radiology was well received by the students. Both, anatomical and radiological comprehension and the motivation to learn were improved. However, it should be considered, that the amount of work and time required by the teaching staff is considerably increased compared to traditional teaching. © Georg Thieme Verlag KG Stuttgart · New York.

Analysis of the Radiology Reports from Radiology Clinics

International Nuclear Information System (INIS)

Kim, Eun Jin; Kwack, Kyu Sung; Cho, Jae Hyun; Jang, Eun Ho

2009-01-01

The purpose of this study was to investigate the form and content of the radiology reports from radiology clinics in Korea. One hundred and sixty six radiology reports from 49 radiology clinics were collected, and these reports were referred to the academic tertiary medical center from March 2008 to February 2009. These included reports for CT (n = 18), MRI (n = 146) and examinations not specified (n = 2). Each report was evaluated for the presence of required contents (demographics, technical information, findings, conclusion, the name, license number and signature of the radiologist and the referring facility). These requirements were based on the guideline of the American College of Radiology and the previous research. The name of the patient, the gender, the body part, the type of examination, the time of examination and the conclusion, the name of the radiologist and the name of facility were well recorded in over 90% of the radiology reports. However, the identification number of the patient, the referring facility, the referring physician, the use of contrast material, the clinical information, the time of dictation, the signature of the radiologist and the license number of the radiologist were poorly recorded (less than 50%). The optimal format of a radiology report should be established for reliable and valid communication with clinicians

Effluent and environmental monitoring of Chalk River Laboratories

Energy Technology Data Exchange (ETDEWEB)

Pilgrim, T.; De Waele, C.; Gallagher, C. [Atomic Energy of Canada Limited, Chalk River, ON (Canada)

2014-07-01

Atomic Energy of Canada Limited's (AECL's) Environmental Protection Program has been gathering environmental monitoring data at its Chalk River Laboratories (CRL) for over 60 years. The comprehensive effluent and environmental monitoring program at CRL consists of more than 600 sampling locations, including the Ottawa River, with approximately 60,000 analyses performed on air and liquid effluent parameters each year. Monitoring for a variety of radiological and non-radiological parameters is regularly conducted on various media, including ambient air, foodstuff (e.g. milk, fish, garden produce, large game, and farm animals), groundwater, Ottawa River water and other surface water on and off-site. The purpose of the monitoring program is to verify that past and current radiological and non-radiological emissions derived from AECL operations and activities, such as process water effluent into the Ottawa River, are below regulatory limits and demonstrate that CRL operations do not negatively affect the quality of water on or leaving the site. In fact, ongoing program reports demonstrate that radiological emissions are well below regulatory limits and have been declining for the past five years, and that non-radiological contaminants do not negatively affect the quality of water on and off the site. Two updated Canadian Standards Association (CSA) standards for Effluent and Environmental monitoring have come into effect and have resulted in some changes to the AECL Program. This presentation will discuss effluent and surface water monitoring results, the observed trends, the changes triggered by the CSA standards, and a path forward for the future. (author)

The Multimedia Environmental Pollutant Assessment System (MEPAS)reg-sign: Riverine pathway formulations

International Nuclear Information System (INIS)

Whelan, G.; McDonald, J.P.

1996-11-01

This report describes the mathematical formulations used for contaminant fate and transport in the riverine pathway of the Multimedia Environmental Pollutant Assessment System (MEPAS). Of the many types of surface-water bodies (e.g., nontidal rivers, estuaries, lakes, open coasts, reservoirs, impoundments, etc.) in which contaminant fate and transport could be simulated, only a nontidal river model is currently incorporated into MEPAS. Nontidal rivers refer to freshwater bodies with unidirectional flow in definable channels. Because the MEPAS methodology is compositely coupled, other surface-water models can be added when deemed necessary

Nevada Test Site Environmental Report 2004

International Nuclear Information System (INIS)

BECHTEL NEVADA

2005-01-01

The ''Nevada Test Site Environmental Report 2004'' was prepared by Bechtel Nevada (BN) to meet the information needs of the public and the requirements and guidelines of the U.S. Department of Energy (DOE) for annual site environmental reports. This Executive Summary presents the purpose of the document, the major programs conducted at the Nevada Test Site (NTS), NTS key environmental initiatives, radiological releases and potential doses to the public resulting from site operations, a summary of non-radiological releases, implementation status of the NTS Environmental Management System, and significant environmental accomplishments. Much of the content of this Executive Summary is also presented in a separate stand-alone pamphlet titled ''Nevada Test Site Environmental Report Summary 2004''. It was produced this year to provide a more cost-effective and wider distribution of a hardcopy summary of the ''Nevada Test Site Environmental Report 2004'' to interested DOE stakeholders

Radiology research in mainland China in the past 10 years: a survey of original articles published in Radiology and European Radiology.

Science.gov (United States)

Zhang, Long Jiang; Wang, Yun Fei; Yang, Zhen Lu; Schoepf, U Joseph; Xu, Jiaqian; Lu, Guang Ming; Li, Enzhong

2017-10-01

To evaluate the features and trends of Radiology research in Mainland China through bibliometric analysis of the original articles published in Radiology and European Radiology (ER) between 2006 and 2015. We reviewed the original articles published in Radiology and ER between 2006 and 2015. The following information was abstracted: imaging subspecialty, imaging technique(s) used, research type, sample size, study design, statistical analysis, study results, funding declarations, international collaborations, number of authors, department and province of the first author. All variables were examined longitudinally over time. Radiology research in Mainland China saw a substantial increase in original research articles published, especially in the last 5 years (P Radiology research, neuroradiology, vascular/interventional Radiology, and abdominal Radiology were the most productive fields; MR imaging was the most used modality, and a distinct geographic provenience was observed for articles published in Radiology and ER. Radiology research in Mainland China has seen substantial growth in the past 5 years with neuroradiology, vascular/interventional Radiology, and abdominal Radiology as the most productive fields. MR imaging is the most used modality. Article provenience shows a distinct geographical pattern. • Radiology research in Mainland China saw a substantial increase. • Neuroradiology, vascular/interventional Radiology, and abdominal Radiology are the most productive fields. • MRI is the most used modality in Mainland China's Radiology research. • Guangdong, Shanghai, and Beijing are the most productive provinces.

Environmental and energy system analysis of bio-methane production pathways: A comparison between feedstocks and process optimizations

International Nuclear Information System (INIS)

Pierie, F.; Someren, C.E.J. van; Benders, R.M.J.; Bekkering, J.; Gemert, W.J.Th. van; Moll, H.C.

2015-01-01

Highlights: • Using local waste feedstock and optimization improves environmental sustainability. • Optimization favors waste feedstocks. • Transport distances should not exceed 150 km. • The produced energy should be used for powering the green gas process first. • The AD process should be used primarily for local waste treatment. - Abstract: The energy efficiency and sustainability of an anaerobic green gas production pathway was evaluated, taking into account five biomass feedstocks, optimization of the green gas production pathway, replacement of current waste management pathways by mitigation, and transport of the feedstocks. Sustainability is expressed by three main factors: efficiency in (Process) Energy Returned On Invested (P)EROI, carbon footprint in Global Warming Potential GWP(100), and environmental impact in EcoPoints. The green gas production pathway operates on a mass fraction of 50% feedstock with 50% manure. The sustainability of the analyzed feedstocks differs substantially, favoring biomass waste flows over, the specially cultivated energy crop, maize. The use of optimization, in the shape of internal energy production, green gas powered trucks, and mitigation can significantly improve the sustainability for all feedstocks, but favors waste materials. Results indicate a possible improvement from an average (P)EROI for all feedstocks of 2.3 up to an average of 7.0 GJ/GJ. The carbon footprint can potentially be reduced from an average of 40 down to 18 kgCO_2eq/GJ. The environmental impact can potentially be reduced from an average of 5.6 down to 1.8 Pt/GJ. Internal energy production proved to be the most effective optimization. However, the use of optimization aforementioned will result in les green gas injected into the gas grid as it is partially consumed internally. Overall, the feedstock straw was the most energy efficient, where the feedstock harvest remains proved to be the most environmentally sustainable. Furthermore, transport

Environmental radioactivity survey in Andong area

Energy Technology Data Exchange (ETDEWEB)

Yoon, Zi Hong; Jo, Kum Ju [Andong Regional Radioactivity Monitoring Station, Andong National Univ., Andong (Korea, Republic of)

2001-12-15

The objectives of the project are to monitor an abnormal level in Andong area and to provide a base-line data on environmental radiation/radioactivity levels in case of any radiological emergency situation. The project is important in view of protecting the public health from the potential hazards of radiation and keeping up the clean environment. This report summarizes and interprets environmental radiation/radioactivity monitoring samples Gamma exposure rates, airborne dust, precipitation, fall-out and drinking-water. Environmental samples : vegetables, fishes/shellfishes, fruits, starch and starch roots and drinking waters. Among the all 2001 radiological monitoring and environmental data in Andong area were not found the extraordinary data. And a nation-wide environmental radiation/radioactivity level survey results were all background levels attributed to terrestrial and cosmic radiation.

Introduction of radiological protection; Pengenalan kepada perlindungan radiologi

Energy Technology Data Exchange (ETDEWEB)

NONE

1988-12-31

The chapter briefly discussed the following subjects: basic principles of radiological protection , dose limit which was suggested, stochastic and nonstochastic effects, equivalent dose and alternative of it`s calculation, limit for the publics, ICRP (International Commission for Radiological Protection) recommendations, and the principles of radiological protection. Dangerous radiation sources also briefly summarized i.e. x-ray generators, reactor nucleus.

Radiological protection of the environment: the path forward to a new policy?

International Nuclear Information System (INIS)

2002-01-01

The international system of radiological protection is currently being revised with the aim of making it more coherent and concise. During the revision process, particular attention is being given to the development of an explicit system for the radiological protection of the environment in addition to that of human beings. In order to support the ongoing discussions of the international community of radiological protection experts, these proceedings try to answer the questions: Is there an international rationale behind the wish to protect the environment from radiation? Do we have enough scientific information to develop and define a broadly accepted policy? What are the socio-political dynamics, beyond science, that will influence policy on radiological protection of the environment? What are the characteristics of the process for developing a system of radiological protection of the environment? These proceedings comprise the views of a broad range of invited speakers, including policy makers, regulators, radiological protection and environmental protection professionals, industry, social scientists and representatives of both non-governmental and intergovernmental organisations. (author)

Genes and pathways underlying susceptibility to impaired lung function in the context of environmental tobacco smoke exposure

NARCIS (Netherlands)

K. de Jong (Kim); J.M. Vonk (Judith); M. Imboden (Medea); L. Lahousse (Lies); A. Hofman (Albert); G.G. Brusselle (Guy); N.M. Probst-Hensch (Nicole M.); D.S. Postma (Dirkje); H.M. Boezen (Marike)

2017-01-01

textabstractBackground: Studies aiming to assess genetic susceptibility for impaired lung function levels upon exposure to environmental tobacco smoke (ETS) have thus far focused on candidate-genes selected based on a-priori knowledge of potentially relevant biological pathways, such as glutathione

Radiology

International Nuclear Information System (INIS)

Edholm, P.R.

1990-01-01

This is a report describing diagnostic techniques used in radiology. It describes the equipment necessary for, and the operation of a radiological department. Also is described the standard methods used in radiodiagnosis. (K.A.E.)

Angra nuclear plant - environmental control program; Usina Nuclear de Angra: programa de controle ambiental

Energy Technology Data Exchange (ETDEWEB)

Kircher, E; Cruz, E.S. da [FURNAS, Rio de Janeiro, RJ (Brazil)

1990-12-31

The pre-operational studies, that were elaborated before the beginning of Angra I Power Plant operation, are described in particular the environmental radiological safety area till the fuel loading in the core reactor. Several aspects are included, as socio-economic survey, seismological analysis, Meteorological Program, marine biology, water cooling system, exposure measures of natural radiation, marine sediments characterization in the effluent dispersion area and Environmental Radiological Monitoring Program. The main environmental programs developed for the operational phase of the Angra I Plant are also presented, citing some considerations about the Meteorological Program, Marine Biology Control Program, Temperature and Chlorine Control in Piraquara de Fora Bay, Radiological Environmental Monitoring Program, Sanitary Effluent Control Program and Radiological Emergency Program. (C.G.C.). 2 refs.

Radiological characterization of practices employed at the Center for the Protection and Hygiene of Radiation (CPHR)

International Nuclear Information System (INIS)

Domenech Nieves, H.; Callis Fernandez, E.

1998-01-01

This work makes the radiological characterization of practices carried out at the CPHR to evaluate dose possible restrictions. The characterization was based on data processed from annual individual doses to which workers were exposed during 1994-1997. This was done in a global way and also for different groups of workers identified (Group of Radioactive Refuses; Secondary laboratory of Dosimetric Calibration; the Laboratory of Environmental Radiological Surveillance and the Group that Evaluates Radiological Safety)

Radiological assessment of past, present and potential sources to environmental contamination in the Southern Urals and strategies for remedial measures (SUCON)

Energy Technology Data Exchange (ETDEWEB)

Aarkrog, A. [Risoe National Lab. (Denmark); Simmonds, J. [National Radiological Protection Board (United Kingdom); Strand, P. [Norwegian Radiation Protection Authority (Norway); Christensen, G. [Institute of Energy Technology (Norway); Salbu, B. [Agricultural Univ. of Norway (Norway)

2000-12-01

This report summarises work done on the SUCON Project during 1996-1999 (European Commission Contract No. FI4C-CT95-0001). The project has focused on three major objectives: 1) An assessment of the radiological consequences of the contamination of the South Urals and the Ob river system from the production of plutonium at 'Mayak', 2) The development of models to calculate doses to individuals and populations in the South Urals using environmental data, and 3) The intercomparison, harmonisation and standardisation of techniques used in dose reconstruction and specification of good practice in particular with regard to remedial measures. (au)

Radiological assessment of past, present and potential sources to environmental contamination in the Southern Urals and strategies for remedial measures (SUCON)

International Nuclear Information System (INIS)

Aarkrog, A.; Simmonds, J.; Strand, P.; Christensen, G.; Salbu, B.

2000-12-01

This report summarises work done on the SUCON Project during 1996-1999 (European Commission Contract No. FI4C-CT95-0001). The project has focused on three major objectives: 1) An assessment of the radiological consequences of the contamination of the South Urals and the Ob river system from the production of plutonium at 'Mayak', 2) The development of models to calculate doses to individuals and populations in the South Urals using environmental data, and 3) The intercomparison, harmonisation and standardisation of techniques used in dose reconstruction and specification of good practice in particular with regard to remedial measures. (au)

Annual Site Environmental Report, Department of Energy Operations at the Energy Technology Engineering Center – Area IV, Santa Susana Field Laboratory

Energy Technology Data Exchange (ETDEWEB)

Frazee, Brad [North Wind, Inc., Idaho Falls, ID (United States); Hay, Scott [North Wind, Inc., Idaho Falls, ID (United States); Wondolleck, John [North Wind, Inc., Idaho Falls, ID (United States); Sorrels, Earl [North Wind, Inc., Idaho Falls, ID (United States); Rutherford, Phil [North Wind, Inc., Idaho Falls, ID (United States); Dassler, David [North Wind, Inc., Idaho Falls, ID (United States); Jones, John [North Wind, Inc., Idaho Falls, ID (United States)

2015-05-01

This Annual Site Environmental Report (ASER) for 2014 describes the environmental conditions related to work performed for the DOE at Area IV of the Santa Susana Field Laboratory (SSFL). The ETEC, a government-owned, company-operated test facility, was located in Area IV. The operations in Area IV included development, fabrication, operation and disassembly of nuclear reactors, reactor fuel, and other radioactive materials. Other activities in the area involved the operation of large-scale liquid metal facilities that were used for testing non-nuclear liquid metal fast breeder reactor components. All nuclear work was terminated in 1988, and all subsequent radiological work has been directed toward environmental restoration and decontamination and decommissioning (D&D) of the former nuclear facilities and their associated sites. Liquid metal research and development ended in 2002. Since May 2007, the D&D operations in Area IV have been suspended by the DOE, but the environmental monitoring and characterization programs have continued. Results of the radiological monitoring program continue to indicate that there are no significant releases of radioactive material from Area IV of SSFL. All potential exposure pathways are sampled and/or monitored, including air, soil, surface water, groundwater, direct radiation, transfer of property (land, structures, waste), and recycling.

AERIAL RADIOLOGICAL SURVEYS

International Nuclear Information System (INIS)

Proctor, A.E.

1997-01-01

Measuring terrestrial gamma radiation from airborne platforms has proved to be a useful method for characterizing radiation levels over large areas. Over 300 aerial radiological surveys have been carried out over the past 25 years including U.S. Department of Energy (DOE) sites, commercial nuclear power plants, Formerly Utilized Sites Remedial Action Program/Uranium Mine Tailing Remedial Action Program (FUSRAP/UMTRAP) sites, nuclear weapons test sites, contaminated industrial areas, and nuclear accident sites. This paper describes the aerial measurement technology currently in use by the Remote Sensing Laboratory (RSL) for routine environmental surveys and emergency response activities. Equipment, data-collection and -analysis methods, and examples of survey results are described

Assessment of radiological consequences of routine releases in a site with various nuclear facilities

International Nuclear Information System (INIS)

Lucinio, Elena Albeira Guirado

2003-01-01

This work evaluates the radiological consequences of a nuclear site with a complex of fuel enrichment, conversion, reconversion facilities and a nuclear reactor. A methodology recommended by the Commission of the European Communities (CEC) is used and implemented in the PC-CREAM computer code. This code is composed of six linked modules, which describe the transfer of radionuclides to the environment, the pathways on which people may be exposed to radiation, and the radiological consequences. Radiation doses to a selected population are evaluated taking into account atmospheric and aquatic releases. (author)

Nevada Test Site Environmental Report 2004

Energy Technology Data Exchange (ETDEWEB)

BECHTEL NEVADA

2005-10-01

The ''Nevada Test Site Environmental Report 2004'' was prepared by Bechtel Nevada (BN) to meet the information needs of the public and the requirements and guidelines of the U.S. Department of Energy (DOE) for annual site environmental reports. This Executive Summary presents the purpose of the document, the major programs conducted at the Nevada Test Site (NTS), NTS key environmental initiatives, radiological releases and potential doses to the public resulting from site operations, a summary of non-radiological releases, implementation status of the NTS Environmental Management System, and significant environmental accomplishments. Much of the content of this Executive Summary is also presented in a separate stand-alone pamphlet titled ''Nevada Test Site Environmental Report Summary 2004''. It was produced this year to provide a more cost-effective and wider distribution of a hardcopy summary of the ''Nevada Test Site Environmental Report 2004'' to interested DOE stakeholders.

Preventing radiological threat in the Republic of Azerbaijan

International Nuclear Information System (INIS)

Gabulov, I.A.

2005-01-01

Full text: Azerbaijan is a developing and transit country in the Caucasus, connecting East and West. In addition, Azerbaijan is neighboring countries with pronounced political instability, some of which have extensive nuclear infrastructure or try to develop nuclear infrastructure. Furthermore, in the recent past fundamentalist religious terrorism has taken roots in some of these countries. Therefore, in spite of the fact that the Republic of Azerbaijan has no nuclear facilities or nuclear materials in its own territory, it could be interesting for terrorist groups trying to develop a crude radiological dispersal device using radioactive sources that are widely used in everyday life especially in such areas as oil industry, medicine, agriculture and scientific researches. The issues of reduction and prevention of both radiological and nuclear terrorism threat are one of the main global challenges around the world. The Republic of Azerbaijan is a part of world community and so we are concerned that radioactive sources used for peaceful applications could be stolen by the terrorist groups and used in the development of radiological dispersal devices sometimes referred to as a 'dirty bomb'. It is obvious that using highly radioactive materials in radiological dispersal devices could be very disruptive to society, causing panic, environmental contamination, and large financial losses. One of the ways for reduction and prevention of radiological threat for the countries like Azerbaijan with underdeveloped nuclear security and radiation safety infrastructure is closely participation in the international cooperation programs. As an example of such cooperation, I would like to present the United States Department of Energy's International Radiological Threat Reduction (IRTR) Program. Good progress has made in the field of radiological security within the framework of this program that was started 2003. Actually, in comparison with any IAEA programs, the progress reached by

Proceedings of the 3. Regional Meeting on Radiological and Nuclear Safety, Regional Meeting on International Radiation Protection Association (IRPA)and 3. Peruvian Meeting on Radiological Protection; 3. Congreso Regional sobre Seguridad Radiologica y Nuclear, Congreso Regional IRPA y 3. Congreso Peruano de Proteccion Radiologica. Libro de Resumenes

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-10-01

There we show works of the Third Regional Meeting on Radiological and Nuclear Safety held on 23-27 October, 1995 in Cusco-Peru. Latin americans specialists talk about nuclear safety and radiological protection, radiation natural exposure, biological effect of radiation, radiotherapy and medical radiological safety, radiological safety in industry and research. Also we deal with subjects related to radiological safety of nuclear and radioactive facilities, radioactive waste management, radioactive material transport, environmental radiological monitoring program, radiological emergency and accidents, instruments and dosimetry, basic safety standards of protection against radiation. More than 225 works were presented on the meeting.

WSPEEDI-II system user's manual for a nuclear or radiological emergency

International Nuclear Information System (INIS)

Nakanishi, Chika; Sato, Sohei; Muto, Shigeo; Furuno, Akiko; Terada, Hiroaki; Nagai, Haruyasu

2011-03-01

Nuclear Emergency Assistance and Training Center (NEAT) has developed the response system to evaluate the radiological consequences of an accident on a nuclear power plant or nuclear weapons testing around Japan and to support prediction of radioactive material distributions by using an atmospheric dispersion model on the framework of the Response Assistance Network (RANET) which is established by the International Atomic Energy Agency (IAEA). For the enhancement of assistance capability to external organizations at a nuclear or radiological emergency, NEAT will introduce a computer-based emergency response system, 'Worldwide version of System for Prediction of Environmental Emergency Dose Information: WSPEEDI 2nd version (WSPEEDI-II)' developed by Division of Environmental and Radiation Sciences. This manual covers the overview of the system and configuration parameters as the basic knowledge needed for operating the systems. (author)

Radiology research in mainland China in the past 10 years: a survey of original articles published in Radiology and European Radiology

International Nuclear Information System (INIS)

Zhang, Long Jiang; Wang, Yun Fei; Yang, Zhen Lu; Lu, Guang Ming; Schoepf, U.J.; Xu, Jiaqian; Li, Enzhong

2017-01-01

To evaluate the features and trends of Radiology research in Mainland China through bibliometric analysis of the original articles published in Radiology and European Radiology (ER) between 2006 and 2015. We reviewed the original articles published in Radiology and ER between 2006 and 2015. The following information was abstracted: imaging subspecialty, imaging technique(s) used, research type, sample size, study design, statistical analysis, study results, funding declarations, international collaborations, number of authors, department and province of the first author. All variables were examined longitudinally over time. Radiology research in Mainland China saw a substantial increase in original research articles published, especially in the last 5 years (P < 0.001). Within Mainland China's Radiology research, neuroradiology, vascular/interventional Radiology, and abdominal Radiology were the most productive fields; MR imaging was the most used modality, and a distinct geographic provenience was observed for articles published in Radiology and ER. Radiology research in Mainland China has seen substantial growth in the past 5 years with neuroradiology, vascular/interventional Radiology, and abdominal Radiology as the most productive fields. MR imaging is the most used modality. Article provenience shows a distinct geographical pattern. (orig.)

Radiology research in mainland China in the past 10 years: a survey of original articles published in Radiology and European Radiology

Energy Technology Data Exchange (ETDEWEB)

Zhang, Long Jiang; Wang, Yun Fei; Yang, Zhen Lu; Lu, Guang Ming [Medical School of Nanjing University, Department of Medical Imaging, Jinling Hospital, Nanjing, Jiangsu (China); Schoepf, U.J. [Medical School of Nanjing University, Department of Medical Imaging, Jinling Hospital, Nanjing, Jiangsu (China); Medical University of South Carolina, Division of Cardiovascular Imaging, Department of Radiology and Radiological Science, Charleston, SC (United States); Xu, Jiaqian [Medical University of South Carolina, Division of Cardiovascular Imaging, Department of Radiology and Radiological Science, Charleston, SC (United States); Li, Enzhong [National Natural Science Foundation of China, Department of Medical Science, Beijing (China)

2017-10-15

To evaluate the features and trends of Radiology research in Mainland China through bibliometric analysis of the original articles published in Radiology and European Radiology (ER) between 2006 and 2015. We reviewed the original articles published in Radiology and ER between 2006 and 2015. The following information was abstracted: imaging subspecialty, imaging technique(s) used, research type, sample size, study design, statistical analysis, study results, funding declarations, international collaborations, number of authors, department and province of the first author. All variables were examined longitudinally over time. Radiology research in Mainland China saw a substantial increase in original research articles published, especially in the last 5 years (P < 0.001). Within Mainland China's Radiology research, neuroradiology, vascular/interventional Radiology, and abdominal Radiology were the most productive fields; MR imaging was the most used modality, and a distinct geographic provenience was observed for articles published in Radiology and ER. Radiology research in Mainland China has seen substantial growth in the past 5 years with neuroradiology, vascular/interventional Radiology, and abdominal Radiology as the most productive fields. MR imaging is the most used modality. Article provenience shows a distinct geographical pattern. (orig.)

Radiological Safety Analysis Computer (RSAC) Program Version 7.0 Users’ Manual

Energy Technology Data Exchange (ETDEWEB)

Dr. Bradley J Schrader

2009-03-01

The Radiological Safety Analysis Computer (RSAC) Program Version 7.0 (RSAC-7) is the newest version of the RSAC legacy code. It calculates the consequences of a release of radionuclides to the atmosphere. A user can generate a fission product inventory from either reactor operating history or a nuclear criticality event. RSAC-7 models the effects of high-efficiency particulate air filters or other cleanup systems and calculates the decay and ingrowth during transport through processes, facilities, and the environment. Doses are calculated for inhalation, air immersion, ground surface, ingestion, and cloud gamma pathways. RSAC-7 can be used as a tool to evaluate accident conditions in emergency response scenarios, radiological sabotage events and to evaluate safety basis accident consequences. This users’ manual contains the mathematical models and operating instructions for RSAC-7. Instructions, screens, and examples are provided to guide the user through the functions provided by RSAC-7. This program was designed for users who are familiar with radiological dose assessment methods.

Radiological Safety Analysis Computer (RSAC) Program Version 7.2 Users’ Manual

Energy Technology Data Exchange (ETDEWEB)

Dr. Bradley J Schrader

2010-10-01

The Radiological Safety Analysis Computer (RSAC) Program Version 7.2 (RSAC-7) is the newest version of the RSAC legacy code. It calculates the consequences of a release of radionuclides to the atmosphere. A user can generate a fission product inventory from either reactor operating history or a nuclear criticality event. RSAC-7 models the effects of high-efficiency particulate air filters or other cleanup systems and calculates the decay and ingrowth during transport through processes, facilities, and the environment. Doses are calculated for inhalation, air immersion, ground surface, ingestion, and cloud gamma pathways. RSAC-7 can be used as a tool to evaluate accident conditions in emergency response scenarios, radiological sabotage events and to evaluate safety basis accident consequences. This users’ manual contains the mathematical models and operating instructions for RSAC-7. Instructions, screens, and examples are provided to guide the user through the functions provided by RSAC-7. This program was designed for users who are familiar with radiological dose assessment methods.

Radiological Safety Analysis Computer (RSAC) Program Version 7.0 Users Manual

International Nuclear Information System (INIS)

Schrader, Bradley J.

2009-01-01

The Radiological Safety Analysis Computer (RSAC) Program Version 7.0 (RSAC-7) is the newest version of the RSAC legacy code. It calculates the consequences of a release of radionuclides to the atmosphere. A user can generate a fission product inventory from either reactor operating history or a nuclear criticality event. RSAC-7 models the effects of high-efficiency particulate air filters or other cleanup systems and calculates the decay and ingrowth during transport through processes, facilities, and the environment. Doses are calculated for inhalation, air immersion, ground surface, ingestion, and cloud gamma pathways. RSAC-7 can be used as a tool to evaluate accident conditions in emergency response scenarios, radiological sabotage events and to evaluate safety basis accident consequences. This users manual contains the mathematical models and operating instructions for RSAC-7. Instructions, screens, and examples are provided to guide the user through the functions provided by RSAC-7. This program was designed for users who are familiar with radiological dose assessment methods

Radiological protection in interventional radiology

International Nuclear Information System (INIS)

Padovani, R.

2001-01-01

Interventional radiology (IR) reduces the need for many traditional interventions, particularly surgery, so reducing the discomfort and risk for patients compared with traditional systems. IR procedures are frequently performed by non-radiologist physicians, often without the proper radiological equipment and sufficient knowledge of radiation protection. Levels of doses to patients and staff in IR vary enormously. A poor correlation exists between patient and staff dose, and large variations of dose are reported for the same procedure. The occurrence of deterministic effects in patients is another peculiar aspect of IR owing to the potentially high skin doses of some procedures. The paper reviews the use of IR and the radiological protection of patients and staff, and examines the need for new standards for IR equipment and the training of personnel. (author)

Radiological planning and implementation for nuclear-facility decommissioning

International Nuclear Information System (INIS)

Valentine, A.M.

1982-01-01

The need and scope of radiological planning required to support nuclear facility decommissioning are issues addressed in this paper. The role of radiation protection engineering and monitoring professionals during project implementation and closeout is also addressed. Most of the discussion focuses on worker protection considerations; however, project support, environmental protection and site release certification considerations are also covered. One objective is to identify radiological safety issues that must be addressed. The importance of the issues will vary depending on the type of facility being decommissioned; however, by giving appropriate attention to these issues difficult decommissioning projects can be accomplished in a safer manner with workers and the public receiving minimal radiation exposures

CRRIS: a computerized radiological risk-investigation system

International Nuclear Information System (INIS)

Baes, C.F. III; Miller, C.W.

1981-01-01

The US Environmental Protection Agency (EPA) is responsible for regulating radioactive airborne effluents in the US. A comprehensive, integrated Computerized Radiological Risk Investigation System (CRRIS) is being developed to support EPA's radiation standards development. This modular system consists primarily of five computer codes and their supporting data bases for estimating environmental transport and radiation doses and risks. Health effects are estimated on the basis of a life-table methodology developed by EPA. CRRIS is designed to provide EPA with a reasonable and flexible way of assessing the risk to man associated with radionuclide releases to the atmosphere

Remotely Piloted Aircraft Systems and a Wireless Sensors Network for Radiological Accidents

Directory of Open Access Journals (Sweden)

A. Reyes-Muñoz

2016-01-01

Full Text Available In critical radiological situations, the real time information that we could get from the disaster area becomes of great importance. However, communication systems could be affected after a radiological accident. The proposed network in this research consists of distributed sensors in charge of collecting radiological data and ground vehicles that are sent to the nuclear plant at the moment of the accident to sense environmental and radiological information. Afterwards, data would be analyzed in the control center. Collected data by sensors and ground vehicles would be delivered to a control center using Remotely Piloted Aircraft Systems (RPAS as a message carrier. We analyze the pairwise contacts, as well as visiting times, data collection, capacity of the links, size of the transmission window of the sensors, and so forth. All this calculus was made analytically and compared via network simulations.

Comparison of the DOE and the EPA risk assessment methodologies and default parameters for the air exposure pathway

International Nuclear Information System (INIS)

Tan, Z.; Eckart, R.

1993-01-01

The U.S. Department of Energy (DOE) and the U.S. Environmental Protection Agency (EPA) each publish radiological health effects risk assessment methodologies. Those methodologies are in the form of computer program models or extensive documentation. This research paper compares the significant differences between the DOE and EPA methodologies and default parameters for the important air exposure pathway. The purpose of this analysis was to determine the fundamental differences in methodology and parameter values between the DOE and the EPA. This study reviewed the parameter values and default values that are utilized in the air exposure pathway and revealed the significant differences in risk assessment results when default values are used in the analysis of an actual site. The study details the sources and the magnitude of the parameter departures between the DOE and the EPA methodologies and their impact on dose or risk

Radiological and environmental aspects of fusion power

International Nuclear Information System (INIS)

Easterly, C.E.; Shank, K.E.; Shoup, R.L.

1977-01-01

Fusion-reactor technology is presently in conceptual and early developmental stages. Concomitant with hardware development, potential health and environmental impacts must be evaluated to ensure that technologists have pertinent information available so that adequate consideration may be given to health and environmental problems. This article discusses problem areas attendant to tritium, activation products, and magnetic fields associated with fusion-reactor systems

Development of an open platform system for environmental pathway analysis

International Nuclear Information System (INIS)

LePoire, D. J.; Arnish, J. J.; Gnanapragasam, E.; Chen, S. Y.

2001-01-01

Most existing computer codes for environmental pathway modeling have been developed to satisfy a specific objective (e.g., perform analyses to demonstrate regulatory compliance). These codes were written in various computer languages and software environments over time and often are not mutually compatible. In recent years, largely driven by advancements in industrial software development, a new concept based on ''modularization'' has emerged. This approach entails the development of common ''modules,'' or components, that can be shared by and used in different applications that have certain common needs. For instance, an air dispersion model can be written as a common component to be shared by several different applications, each with the need to model air dispersion of some material release. When this concept is fully developed, modeling applications would become an exercise of selecting, integrating, and applying a consistent combination of appropriate pre-existing modules for a specific problem. Although modularization holds promising advantages over the traditional approach, a number of issues do exist. These issues must be fully addressed and resolved before the approach can be accepted as a new paradigm for environmental modeling. This paper discusses these issues and provides recommendations and a course of actions for future development

Radiological safety and environmental surveillance during the mining and milling of beach minerals and processing of monazite

International Nuclear Information System (INIS)

Pillai, P.M.B.; Khan, A.H.

2003-01-01

This paper highlights the occupational and environmental radiological safety aspects and surveillance activities associated with mining and milling of beach minerals and processing of monazite, based on the experience gained over more than three decades of operations of the plants of Indian Rare Earths Ltd, at Chavara (Kerala), Manavalakurichi (Tamilnadu) and Udyogamandal (Kerala). The mining of beach sands, mineral separation and chemical processing of monazite for the recovery of Th and U involve occupational radiation hazards and safety problems of varying magnitudes. This part of the front end of the nuclear fuel cycle involves average per-capita occupational exposures ranging from 1.0 mSv to 8 mSv per year. The collective doses involved work out to 4.5 to 5.4 Person Sieverts per year and involve nearly 1000 radiation workers. Internal exposure contributes to nearly half of the exposure. Mechanization of the operations, process modifications, administrative controls and constant safety surveillance have over the years helped to reduce the exposures and to maintain them at levels as low as reasonably achievable (ALARA). Environmental releases resulting from the operations are well within the limits stipulated by competent authorities and exposures to public from the mining, mineral separation and monazite processing are not significant. (author)

Radiological protection report 2014; Strahlenschutzbericht 2014

Energy Technology Data Exchange (ETDEWEB)

NONE

2015-06-15

In its 11{sup th} Annual Report on Radiological Protection, the Swiss Federal Nuclear Safety Inspectorate (ENSI) provides the public with information on dose rates for individuals professionally exposed to radiation, releases of radioactive material and the monitoring of environmental radiation. ENSI, as the regulatory body for nuclear facilities in Switzerland, is continuing to expand its information provision over and above that contained in the Radiological Protection Report. At 0.6 mSv per year, the average individual dose for professionally exposed persons remains significantly below the annual limit of 20 mSv specified by the Swiss Federal Council. It is also less than the average annual rate of natural environmental exposure of 5.5 mSv for the population in Switzerland as a whole. The highest individual dose during the year was 12 mSv. The collective doses lie within the range of past years. There is a trend towards higher collective doses at KKL. As a general rule, planning by the licensees of nuclear facilities in the field of radiological protection is of a high standard. Actual collective doses in 2014 at Beznau 1, Goesgen and Leibstadt were within 10% of projected exposure rates and at Beznau 2 and Muehleberg the doses were about 30% lower. Demands in terms of radiological protection were particularly high at Leibstadt and Beznau 1; at Leibstadt mainly as a result of a fuel cladding defect and at Beznau 1 because of the continuing elevated ambient rate for components in the primary circuit. ENSI concluded that the Swiss nuclear facilities continue to operate a consistent approach to radiological protection. In 2014, licensees of nuclear facilities remained within official release limits, in some cases by a significant margin. Liquid releases from Muehleberg were below the target value of 1 GBq per year set by ENSI on the basis of international recommendations. At the Central Interim Storage Facility (ZWILAG) and at the Paul Scherrer Institute (PSI

200-UP-2 operable unit radiological surveys

International Nuclear Information System (INIS)

Wendling, M.A.

1994-01-01

This report summarizes and documents the results of the radiological surveys conducted from August 17 through December 16, 1993 over a partial area of the 200-UP-2 Operable Unit, 200-W Area, Hanford Site, Richland, Washington. In addition, this report explains the survey methodology of the Mobile Surface Contamination Monitor 11 (MSCM-II) and the Ultra Sonic Ranging And Data System (USRADS). The radiological survey of the 200-UP-2 Operable Unit was conducted by the Site Investigative Surveys/Environmental Restoration Health Physics Organization of the Westinghouse Hanford Company. The survey methodology for the majority of area was based on utilization of the MSCM-II or the USRADS for automated recording of the gross beta/gamma radiation levels at or near six (6) inches from the surface soil

General Employee Radiological Training and Radiological Worker Training: Program management manual

International Nuclear Information System (INIS)

1992-10-01

This manual defines and describes the DOE General Employee Radiological Training (GERT) and Radiological Worker I and II (RW I and II) Training programs. It includes material development requirements, standards and policies, and program administration. This manual applies to General Employee Radiological Training and Radiological Worker Training at all DOE contractor sites. The training materials of both GERT and RW I and II training reflect the requirements identified in the DOE Radiological Control Manual and DOE Order 5480.11. The training programs represent the minimum requirement for the standardized core materials. Each contractor shall implement the program in its entirety and may augment the standardized core materials to increase the general employee and radiological worker level of competency

Site Environmental Report for Calendar Year 2011. DOE Operations at The Boeing Company Santa Susana Field Laboratory, Area IV

Energy Technology Data Exchange (ETDEWEB)

Liu, Ning [The Boeing Company, Canoga Park, CA (United States); Rutherford, Phil [The Boeing Company, Canoga Park, CA (United States); Dassler, David [The Boeing Company, Canoga Park, CA (United States)

2012-09-01

This Annual Site Environmental Report (ASER) for 2011 describes the environmental conditions related to work performed for the Department of Energy (DOE) at Area IV of Boeing’s Santa Susana Field Laboratory (SSFL). The Energy Technology Engineering Center (ETEC), a government-owned, company-operated test facility, was located in Area IV. The operations in Area IV included development, fabrication, operation and disassembly of nuclear reactors, reactor fuel, and other radioactive materials. Other activities in the area involved the operation of large-scale liquid metal facilities that were used for testing non-nuclear liquid metal fast breeder reactor components. All nuclear work was terminated in 1988, and all subsequent radiological work has been directed toward environmental restoration and decontamination and decommissioning (D&D) of the former nuclear facilities and their associated sites. Liquid metal research and development ended in 2002. Since May 2007, the D&D operations in Area IV have been suspended by the DOE, but the environmental monitoring and characterization programs have continued. Results of the radiological monitoring program for the calendar year 2011 continue to indicate that there are no significant releases of radioactive material from Area IV of SSFL. All potential exposure pathways are sampled and/or monitored, including air, soil, surface water, groundwater, direct radiation, transfer of property (land, structures, waste), and recycling.

Site Environmental Report For Calendar Year 2012. DOE Operations at The Boeing Company Santa Susana Field Laboratory, Area IV

Energy Technology Data Exchange (ETDEWEB)

Liu, Ning [The Boeing Company, Canoga Park, CA (United States); Rutherford, Phil [The Boeing Company, Canoga Park, CA (United States); Dassler, David [The Boeing Company, Canoga Park, CA (United States)

2013-09-01

This Annual Site Environmental Report (ASER) for 2012 describes the environmental conditions related to work performed for the Department of Energy (DOE) at Area IV of Boeing’s Santa Susana Field Laboratory (SSFL). The Energy Technology Engineering Center (ETEC), a government-owned, company-operated test facility, was located in Area IV. The operations in Area IV included development, fabrication, operation and disassembly of nuclear reactors, reactor fuel, and other radioactive materials. Other activities in the area involved the operation of large-scale liquid metal facilities that were used for testing non-nuclear liquid metal fast breeder reactor components. All nuclear work was terminated in 1988, and all subsequent radiological work has been directed toward environmental restoration and decontamination and decommissioning (D&D) of the former nuclear facilities and their associated sites. Liquid metal research and development ended in 2002. Since May 2007, the D&D operations in Area IV have been suspended by the DOE, but the environmental monitoring and characterization programs have continued. Results of the radiological monitoring program for the calendar year 2012 continue to indicate that there are no significant releases of radioactive material from Area IV of SSFL. All potential exposure pathways are sampled and/or monitored, including air, soil, surface water, groundwater, direct radiation, transfer of property (land, structures, waste), and recycling.

Radioactive characterization of the main materials involved in the titanium dioxide production process and their environmental radiological impact.

Science.gov (United States)

Mantero, J; Gazquez, M J; Bolivar, J P; Garcia-Tenorio, R; Vaca, F

2013-06-01

A study about the distribution of several radionuclides from the uranium and the thorium series radionuclides along the production process of a typical NORM industry devoted to the production of titanium dioxide has been performed. With this end the activity concentrations in raw materials, final product, co-products, and wastes of the production process have been determined by both gamma-ray and alpha-particle spectrometry. The main raw material used in the studied process (ilmenite) presents activity concentrations of around 300 Bq kg(-1) for Th-series radionuclides and 100 Bq kg(-1) for the U-series ones. These radionuclides in the industrial process are distributed in the different steps of the production process according mostly to the chemical behaviour of each radioelement, following different routes. As an example, most of the radium remains associated with the un-dissolved material waste, with activity concentrations around 3 kBq kg(-1) of (228)Ra and around 1 kBq kg(-1) of (226)Ra, while the final commercial products (TiO2 pigments and co-products) contain negligible amounts of radioactivity. The obtained results have allowed assessing the possible public radiological impact associated with the use of the products and co-products obtained in this type of industry, as well as the environmental radiological impact associated with the solid residues and liquid generated discharges. Copyright © 2013 Elsevier Ltd. All rights reserved.

Low-level wastes pathways at EDF

International Nuclear Information System (INIS)

Hilmoine, R.; Casseau, L.Ph.

1999-01-01

First, what are, for EDF, the main issues dealing with the future management of low level wastes (LLW) will be recalled; and followed by a description of what are the implications of implementing these management principles: areas zoning, set up of pathways, traceability of the wastes and associated controls. The origin of the wastes will then be described using both qualitative and quantitative approaches; the description will specifically address the spreading of wastes production in time. LLW management at EDF will then be envisaged: storage in a specific discharge, pathways for treatment and elimination of wastes with acceptable radiological impact and costs. The example of LLW oils will be developed: particularly as far as hypothesis and results concerning the radiological impacts are concerned. The choice of incineration will then be justified, however expected difficulties to implement it industrially will be pointed out. Other on going studies and their main results will be mentioned: the present time is a turning point on that issue between thought and action; to be on going dismantling must take into account the emerging principles and give rise to good communication. (author)

Radiological protection of the environment from the Swedish point of view

International Nuclear Information System (INIS)

Holm, Lars-Erik; Hubbard, Lynn; Larsson, Carl-Magnus; Sundell-Bergman, Synnoeve

2002-01-01

The current system of radiological protection is aimed at protecting human health, and largely neglects both the effects of radiation on the environment and the managerial aspects of environmental protection. The Swedish Radiation Protection Act was revised in 1988 and includes environmental protection as one of its aims. In practice, little guidance had been given in the regulations based on the Act until 1998, when the Swedish Radiation Protection Authority (SSI) formulated environmental aims in its regulations concerning protection of human health and the environment in connection to the final management of spent nuclear fuel and waste. These regulations focus on protection of biodiversity and biological resources, based on ecosystem characterisation. In a broader perspective, the Swedish Parliament established 15 national environmental quality objectives in 1999, covering all aspects of protecting the environment, including the effects of radiation. This paper reviews the background for radiological protection of the environment from both an international and a Swedish perspective, describing the aims and current activities in establishing a system for assessing environmental effects and their consequences that can be used in decision-making. Such activities are largely a result of the European Union research project FASSET (Framework for Assessment of Environmental Impact), carried out under the 5th Framework Programme of the Union. This work is complemented at the Swedish national level by government support to initiate a national environmental monitoring and assessment programme for characterising the radiation environment, which will provide the foundation for decision-making. (review)

Radiological impact of oil/gas industry

International Nuclear Information System (INIS)

Botezatu, E.; Grecea, C.

2006-01-01

The objective of this study was to assess the radiological impact on the environment and population of the oil/gas industry that is non-nuclear industry but uses and can produce materials, with an enhanced content of naturally occurring radionuclides. The natural radioactivity levels in the oil field environmental media, which could represent a risk for the people living in the areas influenced by this non-nuclear industry, do not indicate an increase in the natural radiation background. From a radiological point of view, the situation does not pose any immediate concern. Some places however need further investigations, with special emphasis on the control of 226 Ra releases to prevent from polluting the environment with this radionuclide. The growing concern amongst the population about the quality of their environment increases the significance of impact assessment of radioactive releases into the environment even if natural radionuclides occur. (N.C.)

Site Environmental Report for Calendar Year 2009. DOE Operations at The Boeing Company Santa Susana Field Laboratory, Area IV

Energy Technology Data Exchange (ETDEWEB)

Liu, Ning [The Boeing Company, Canoga Park, CA (United States); Rutherford, Phil [The Boeing Company, Canoga Park, CA (United States); Amar, Ravnesh [The Boeing Company, Canoga Park, CA (United States)

2010-09-01

This Annual Site Environmental Report (ASER) for 2009 describes the environmental conditions related to work performed for the Department of Energy (DOE) at Area IV of Boeing’s Santa Susana Field Laboratory (SSFL). The Energy Technology Engineering Center (ETEC), a government-owned, company-operated test facility, was located in Area IV. The operations in Area IV included development, fabrication, and disassembly of nuclear reactors, reactor fuel, and other radioactive materials. Other activities in the area involved the operation of large-scale liquid metal facilities that were used for testing non-nuclear liquid metal fast breeder reactor components. All nuclear work was terminated in 1988, and all subsequent radiological work has been directed toward decontamination and decommissioning (D&D) of the former nuclear facilities and their associated sites. Liquid metal research and development ended in 2002. Since May 2007, the D&D operations in Area IV have been suspended by the DOE, but the environmental monitoring and characterization programs have continued. Results of the radiological monitoring program for the calendar year 2009 continue to indicate that there are no significant releases of radioactive material from Area IV of SSFL. All potential exposure pathways are sampled and/or monitored, including air, soil, surface water, groundwater, direct radiation, transfer of property (land, structures, waste), and recycling.

Site Environmental Report for Calendar Year 2010. DOE Operations at The Boeing Company Santa Susana Field Laboratory, Area IV

Energy Technology Data Exchange (ETDEWEB)

Liu, Ning [The Boeing Company, Canoga Park, CA (United States); Rutherford, Phil [The Boeing Company, Canoga Park, CA (United States); Amar, Ravnesh [The Boeing Company, Canoga Park, CA (United States)

2011-09-01

This Annual Site Environmental Report (ASER) for 2010 describes the environmental conditions related to work performed for the Department of Energy (DOE) at Area IV of Boeing’s Santa Susana Field Laboratory (SSFL). The Energy Technology Engineering Center (ETEC), a government-owned, company-operated test facility, was located in Area IV. The operations in Area IV included development, fabrication, and disassembly of nuclear reactors, reactor fuel, and other radioactive materials. Other activities in the area involved the operation of large-scale liquid metal facilities that were used for testing non-nuclear liquid metal fast breeder reactor components. All nuclear work was terminated in 1988, and all subsequent radiological work has been directed toward decontamination and decommissioning (D&D) of the former nuclear facilities and their associated sites. Liquid metal research and development ended in 2002. Since May 2007, the D&D operations in Area IV have been suspended by the DOE, but the environmental monitoring and characterization programs have continued. Results of the radiological monitoring program for the calendar year 2010 continue to indicate that there are no significant releases of radioactive material from Area IV of SSFL. All potential exposure pathways are sampled and/or monitored, including air, soil, surface water, groundwater, direct radiation, transfer of property (land, structures, waste), and recycling.

Environmental Sampling, Monitoring and Site Assessment Data

Data.gov (United States)

U.S. Environmental Protection Agency — Quality Data Asset includes all current and historical data on environmental quality with regard to the presence of radiological contamination of all kinds regulated...

Radiological aspects of postfission waste management for light-water reactor fuel cycle options

Energy Technology Data Exchange (ETDEWEB)

Shipler, D B; Nelson, I C [Battelle Pacific Northwest Laboratories, Richland, WA (United States)

1978-12-01

A generic environmental impact statement on the management of radioactive postfission wastes from various light-water reactor fuel cycles in the United States has been prepared. The environmental analysis for post-fission waste management includes an examination of radiological impacts related to different waste treatment, storage, transportation, and disposal options at the process level. Effects addressed include effluents from plants, and radiological impacts from facility operation (routine and accidents), and decommissioning. Environmental effects are combined for fuel reprocessing plants, mixed-oxide fuel fabrication plants, and waste repositories. Radiological effects are also aggregated for several fuel cycle options over the period 1980 and 2050. Fuel cycles analyzed are (1) once-through cycle in which spent reactor fuel is cooled in water basins for at least 6-1/2 years and then disposed of in deep geologic repositories; (2) spent fuel reprocessing in which uranium only and uranium and plutonium is recycled and solidified high level waste, fuel residues, and non-high-level transuranic wastes are disposed of in deep geologic repositories; and (3) deferred cycle that calls for storage of spent fuel at Federal spent fuel storage facilities until the year 2000 at which time a decision is made whether to dispose of spent fuel as a waste or to reprocess the fuel to recover uranium and plutonium. Key environmental issues for decision-making related to waste management alternatives and fuel cycle options are highlighted. (author)

Herbert M. Parker: Publications and contributions to radiological and health physics

International Nuclear Information System (INIS)

Kathren, R.L.; Baalman, R.W.; Bair, W.J.

1986-01-01

For more than a half century, Herbert M. Parker was a leading force in radiological physics. As a scientist, he was codeveloper of a systematic dosimetry scheme for implant therapy and the innovative proposer of radiological units with unambiguous physical and biological bases. He made seminal contributions to the development of scientifically based radiation protection standards and, as an administrator and manager as well as scientist, helped the Hanford Laboratories to achieve preeminance in several areas, including radiation biology, radioactive waste disposal, and environmental radioactivity. This volume brings together, sometimes from obscure sources, his works

Surface radiological investigations at environmental research area 11, 137Cs- and 60Co-contaminated plots at Oak Ridge National Laboratory, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

Uziel, M.S.; Tiner, P.F.; Williams, J.K.

1993-02-01

A surface radiological investigation at the 137 Cs- and 6O Co-contaminated forest area (Chestnut Ridge east and west plots) was conducted from January 1992 through August 1992. Results of the survey revealed numerous spots and small areas of surface contamination that followed the original placement of feeders used for 6O Co- and 137 Cs-labeled seeds in a 1969--1970 study. Surface gamma exposure rates reached 380 μR/h at the east plot and 400 μR/h at the west plot, but approximately one-half and one- third, respectively, of the identified anomalies did not exceed 39 μR/h. Results of soil sample analyses demonstrated that 137 Cs and 6O Co were responsible for the elevated radiation levels. Radionuclides were found below the surface at soil sample locations, in some cases at depths below 18 in. The same pattern of subsurface contamination may be present at other elevated surface spots at both plots. These survey results show that current radiological conditions at the site remain an environmental problem. Recommendations for corrective actions are included

Savannah River Site environmental report for 1993 summary pamphlet

International Nuclear Information System (INIS)

Karapatakis, L.

1994-01-01

This pamphlet summarizes the impact of 1993 Savannah River Site operations on the environment and the off-site public. It includes an overview of site operations; the basis for radiological and nonradiological monitoring; 1993 radiological releases and the resulting dose to the off-site population; and results of the 1993 nonradiological program. The Savannah River Site Environmental Report for 1993 describes the findings of the environmental monitoring program for 1993. The report contains detailed information about site operations,the environmental monitoring and surveillance programs, monitoring and surveillance results, environmental compliance activities, and special programs. The report is distributed to government officials, members of the US Congress, universities, government facilities, environmental and civic groups, the news media, and interested individuals

Radiological effects

International Nuclear Information System (INIS)

Anon.

1978-01-01

Environmental monitoring in the vicinity of the Calvert Cliffs Nuclear Power Plant has been shown the radiation dose to the public from plant operation to be quite small. Calculations from the reported release rates yield 0.2 mrem whole body dose and 0.6 mrem skin dose for the calendar quarter of maximum release. Radioactivity discharges to the Chesapeake Bay have resulted in detectable concentrations of /sup 110m/Ag, 58 Co, and 60 Co in sediments and shellfish. The area yielding samples with detectable concentrations of plant effluents extends for roughly six miles up and down the western shore, with maximum values found at the plant discharge area. The radiation dose to an individual eating 29 doz oysters and 15 doz crabs (5 kg of each) taken from the plant discharge area would be about 4/1000 mrem whole body dose and 0.2 mrem gastrointestinal tract dose (about 0.007% and 0.5% of the applicable guidelines, respectively.) Comparison of these power plant-induced doses with the fluctuations in natural radiation dose already experienced by the public indicates that the power plant effects are insignificant. The natural variations are tens of times greater than the maximum doses resulting from Calvert Cliffs Power Plant. Although operations to date provide an insufficient basis to predict radiological impact of the Calvert Cliffs Plant over its operational lifetime, available data indicate that the plant should continue to operate with insignificant radiological impact, well within all applicable guidelines

MEMO radiology

International Nuclear Information System (INIS)

Wagner-Manslau, C.

1989-01-01

This radiology volume is a concise handbook of imaging techniques, nuclear medicine, and radiation therapy, albeit that the main emphasis is on classic radiology. It offers, for instance, a survey of radiological findings for the most frequent pathological conditions, many overviews of differential diagnosis, a glossary of the technical bases of radiology and so forth. The contents are divided into the following chapters: Physical and biological bases; skeleton; thorax with the subdivisions lungs, heart, mediastinum, and pleura; gastrointestinal tract with the subsections esophagus, small and large intestine; liver; biliary tract; pancreas; retroperitoneal space; kidney; suprarenal glands; bladder; blood vessels, lymph nodes, spleen; mammary glands; female genitals; prostate and scrotum, epididymis and seminal vesicle. (orig./MG) With 23 figs [de

The Vaalputs radiological environmental monitoring programme

International Nuclear Information System (INIS)

Van As, D.; Posnik, S.J.; Bain, C.A.R.

1986-01-01

An environmental monitoring programme was initiated two years before radioactive waste was due to be disposed of at the Vaalputs site. During this time a database was established against which future changes in the radiation levels of the environment could be measured. The monitoring network included the measurement of radiation doses, radioactivity levels in soil, vegetation, groundwater, and agricultural produce. A natural radiation dose to the average individual of 2,2 mSv per annum was established. Meteorological parameters were collected and used to assess the potential release and transport of radioactivity through the environment. A survey of the habits of the surrounding population was conducted to identify the principal food chains. In addition to complying with the licensing requirements for the waste disposal site, the environmental monitoring programme is contributing valuable scientific information on evapotranspiration and percolation in semi-arid environments

Neuroradiology in the ocular motility disorders : II. nuclear and infranuclear pathway

International Nuclear Information System (INIS)

Kim, Hyung Jin; Kim, Jae Hyoung; Ha, Choong Gun; Lim, Myung Kwan; Cho, Young Kuk; Suh, Chang Hae

1999-01-01

The nuclear and infranuclear pathway of eye movement begins from the ocular motor nuclei situated in the brain stem, where the axons originate and form three ocular motor nerves. Although each of the ocular motor nerves follows a distinct route to reach the end organ, the extraocular muscles, they also have common housings in the cavernous sinus and at the orbital apex, where part or all of them are frequently and simultaneously affected by a common disease process. Since the fine details of normal and diseased structures can frequently be seen on radiologic imaging, especially magnetic resonance (MR) imaging, a knowledge of the basic anatomy involved in nuclear and infranuclear eye movement is important. In this description, in addition to the normal nuclear and infranuclear pathway of eye movement, we have noted the radiologic findings of typical diseases involving each segment of the nuclear and infranuclear pathway, particularly as seen on magnetic resonance images. Brief comments on ocular motor pseudopalsy, which mimics ocular motor palsy, are also included

Simplified life cycle assessment models: methodological framework and applications to energy pathways

International Nuclear Information System (INIS)

Padey, Pierryves

2013-01-01

The energy transition debate is a key issue for today and the coming years. One of the challenges is to limit the environmental impacts of electricity production. Decision support tools, sufficiently accurate, simple to use, accounting for environmental aspects and favoring future energetic choices, must be implemented. However, the environmental assessment of the energy pathways is complex, and it means considering a two levels characterization. The 'energy pathway' is the first level and corresponds to its environmental distribution, to compare overall pathways. The 'system pathway' is the 2. level and compares environmental impacts of systems within each pathway. We have devised a generic methodology covering both necessary characterization levels by estimating the energy pathways environmental profiles while allowing a simple comparison of its systems environmental impacts. This methodology is based on the definition of a parameterized Life Cycle Assessment model and considers, through a Global Sensitivity Analysis, the environmental impacts of a large sample of systems representative of an energy pathway. As a second step, this methodology defines simplified models based on few key parameters identified as inducing the largest variability in the energy pathway environmental impacts. These models assess in a simple way the systems environmental impacts, avoiding any complex LCAs. This reduction methodology has been applied to the onshore wind power energy pathway in Europe and the photovoltaic energy pathway in France. (author)

Assessing environmental risk of the retired filter bed area, Battelle West Jefferson

International Nuclear Information System (INIS)

Miller, S.F.; Thompson, M.D.; Glennon, M.A.

1997-04-01

Initial investigations conducted by the U.S. Department of Energy, Chicago Operations Office, and by Argonne National Laboratory used seismic refraction profiling, electrical resistivity depth sounding, conductivity profiling, magnetic gradiometry, and ground-penetrating radar to study environmental geophysics in the area of the Battelle West Jefferson site's radiologically contaminated retired filter beds. The investigators used a combination of nonintrusive technologies and innovative drilling techniques to assess environmental risk at the filter beds and to improve understanding of the geology of the Big Darby Creek floodplain. The geophysical investigation, which showed that the preferred groundwater pathway is associated with a laterally extensive deposit of silty sand to sand that is less than 12 ft deep in the floodplain area, also guided the location of cone penetrometer test sites and piezometer installation. Cone penetrometer testing was useful for comparing continuous logging data with surface geophysical data in establishing correlations among unconsolidated materials

Virtual pilot course in radiological protection

International Nuclear Information System (INIS)

Gonzalez Romero, Angela Maria; Plazas, Maria Cristina

2008-01-01

Full text: The radiological protection performs vital importance in the fields medically, industrially and environmental. The X-rays and the radioactive materials used in medicine have allowed to realize important progresses and to develop new technologies skills for the diagnosis, the therapy and the prevention of diseases. Having in it counts tells the risks associated with the ionizing radiations, it is required legally that the personnel that intervenes in the different procedures has the necessary knowledge of radiological protection to assure that the use of radiations in the medical practice should carry out of ideal form, at the right moment and adopting all the necessary measures to guarantee the best protection, so much of the occupationally exposed personnel, since as, like of the patients and the public in general. The virtual environments for the construction of the knowledge like it is the virtual university, allows presenting an effective alternative in the learning of different areas and in this particular case of the radiological protection. With the aim lens to give response to these needs there is implemented this pilot virtual course year based on the current course of radiological protection that is dictated in the Mastery in Medical Physics of the National University of Colombia, sedate Bogota. The purpose of this virtual course is to use as academic and bibliographical support on radiological protection, as well as to answer to the needs of initial formation that the professionals have, to acquire a solid base in the mentioned matter. It has been conceived so that it provides theoretical formation, so much scientific as technology and that contemplates the recommendations and international and national procedure on radiological protection and some applications. Given the incorporation of the technologies of information and communication that in the academic area it has brought with it not only to give support to the curricular activities but

Offsite emergency radiological monitoring system and technology

International Nuclear Information System (INIS)

Mao Yongze

1994-01-01

The study and advance of the offsite radiological monitoring system and technology which is an important branch in the field of nuclear monitoring technology are described. The author suggests that the predicting and measuring system should be involved in the monitoring system. The measuring system can further be divided into four sub-systems, namely plume exposure pathway, emergency worker, ingestion exposure pathway and post accident recovery measuring sub-systems. The main facilities for the monitoring system are concluded as one station, one helicopter, one laboratory and two vehicles. The instrumentation for complement of the facilities and their good performance characteristics, up-to-date technology are also introduced in brief. The offsite emergency radiation monitoring system and technology are compared in detail with those recommended by FEMA U.S.A.. Finally the paper discusses some trends in development of emergency radiation monitoring system and technology in the developed countries

Some issues on radiological consequences analysis in site selection for nuclear power stations

International Nuclear Information System (INIS)

Chen Xiaoqiu; Yue Huiguo

2006-01-01

The three considerations, Site safety and environmental protection and emergency preparedness, are the focus of attention in the evaluation of the suitability of a site for nuclear power station. This paper summarized the basic regulatory requirements for the siting of nuclear power station, described the existing problems on radiological consequences analyses during the siting stage and discussed the is- sues that need to concern in the reviewing of the radiological consequences analyses in the siting appraisal stage. (authors)

Radiology and fine art.

Science.gov (United States)

Marinković, Slobodan; Stošić-Opinćal, Tatjana; Tomić, Oliver

2012-07-01

The radiologic aesthetics of some body parts and internal organs have inspired certain artists to create specific works of art. Our aim was to describe the link between radiology and fine art. We explored 13,625 artworks in the literature produced by 2049 artists and found several thousand photographs in an online image search. The examination revealed 271 radiologic artworks (1.99%) created by 59 artists (2.88%) who mainly applied radiography, sonography, CT, and MRI. Some authors produced radiologic artistic photographs, and others used radiologic images to create artful compositions, specific sculptures, or digital works. Many radiologic artworks have symbolic, metaphoric, or conceptual connotations. Radiology is clearly becoming an original and important field of modern art.

Soil radiological characterisation and remediation at CIEMAT

International Nuclear Information System (INIS)

Correa, Cristina; Garcia Tapias, Esther; Leganes, Jose

2012-01-01

Located in Madrid, CIEMAT is the Spanish Centre for Energy-Related, Environmental and Technological Research. It used to have more than 60 facilities in operation that allowed a wide range of activities in the nuclear field and in the application of ionising radiations. At present, the centre includes several facilities; some of them are now obsolete, shut down and in dismantling phases. In 2000 CIEMAT started the 'Integrated plan for the improvement of CIEMAT facilities (PIMIC)', which includes activities for the decontamination, dismantling, rehabilitation of obsolete installations and soil remediation activities. A small contaminated area named with the Spanish word 'Lenteja' (Lentil), has had to be remediate and restored. In the 70's, an incidental leakage of radioactive liquid occurred during a transference operation from the Reprocessing Plant to the Liquid Treatment Installation, and contaminated about 1000 m 3 of soil. Remediation activities in this area started with an exhaustive radiological characterisation of the soil, including surface samples and up to 16 meters boreholes, and the development of a comprehensive radiological characterization methodology for pre-classification of materials. Once the framework was defined the following tasks were being carried out: preparation of the area, soil extraction activities and final radiological characterisation for release purposes. Next step will be the refilling of the resulting hole from the removal soil activities. This paper will describe the soil radiological characterization and remediation activities at the Lentil Zone in Ciemat Research Centre. (authors)

Radiological protection of patients in diagnostic and interventional radiology, nuclear medicine and radiotherapy. Contributed papers

International Nuclear Information System (INIS)

2001-01-01

An International Conference on the Radiological Protection of Patients in Diagnostic and Interventional Radiology, Nuclear Medicine and Radiotherapy organized by the International Atomic Energy Agency and co-sponsored by the European Commission, the Pan American Health Organization and the World Health Organization was held in Malaga, Spain, from 26 to 30 March 2001. The Government of Spain hosted this Conference through the Ministerio de Sanidad y Consumo, the Consejo de Seguridad Nuclear, the Junta de Andalucia, the Universidad de Malaga and the Grupo de Investigacion en Proteccion Radiologica de la Universidad de Malaga (PRUMA). The Conference was organized in co-operation with the United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR), the International Commission on Radiological Protection (ICRP) and the following professional societies: International Organization of Medical Physicists (IOMP), International Radiation Protection Association (IRPA), International Society of Radiation Oncology (ISRO), International Society of Radiology (ISR), International Society of Radiographers and Radiological Technologists (ISRRT) and World Federation of Nuclear Medicine and Biology (WFNMB). This publication contains contributed papers submitted to the Conference Programme Committee. The papers are in one of the two working languages of this Conference, English and Spanish. The topics covered by the Conference are as follows: Radiological protection of patients in general diagnostic radiology (radiography), Radiological protection of patients in general diagnostic radiology (fluoroscopy), Radiological protection issues in specific uses of diagnostic radiology, such as mammography and computed tomography (with special consideration of the impact of digital techniques), Radiological protection in interventional radiology, including fluoroscopy not carried out by radiologists, Radiological protection of patients in nuclear medicine, Developing and

Radiological protection of patients in diagnostic and interventional radiology, nuclear medicine and radiotherapy. Contributed papers

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-03-01

An International Conference on the Radiological Protection of Patients in Diagnostic and Interventional Radiology, Nuclear Medicine and Radiotherapy organized by the International Atomic Energy Agency and co-sponsored by the European Commission, the Pan American Health Organization and the World Health Organization was held in Malaga, Spain, from 26 to 30 March 2001. The Government of Spain hosted this Conference through the Ministerio de Sanidad y Consumo, the Consejo de Seguridad Nuclear, the Junta de Andalucia, the Universidad de Malaga and the Grupo de Investigacion en Proteccion Radiologica de la Universidad de Malaga (PRUMA). The Conference was organized in co-operation with the United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR), the International Commission on Radiological Protection (ICRP) and the following professional societies: International Organization of Medical Physicists (IOMP), International Radiation Protection Association (IRPA), International Society of Radiation Oncology (ISRO), International Society of Radiology (ISR), International Society of Radiographers and Radiological Technologists (ISRRT) and World Federation of Nuclear Medicine and Biology (WFNMB). This publication contains contributed papers submitted to the Conference Programme Committee. The papers are in one of the two working languages of this Conference, English and Spanish. The topics covered by the Conference are as follows: Radiological protection of patients in general diagnostic radiology (radiography), Radiological protection of patients in general diagnostic radiology (fluoroscopy), Radiological protection issues in specific uses of diagnostic radiology, such as mammography and computed tomography (with special consideration of the impact of digital techniques), Radiological protection in interventional radiology, including fluoroscopy not carried out by radiologists, Radiological protection of patients in nuclear medicine, Developing and

Actinide discharges from Sellafield - a summary of behaviour in the environment and the radiological implications

International Nuclear Information System (INIS)

Coughtrey, P.J.; Jackson, D.; Martin, A.; Thorne, M.C.

1985-05-01

This report provides a summary of: information on the quantities of actinides discharged from Sellafield, their distribution in the environment and the radiological implications; potential long-term trends and exposure pathways that may require investigation; and research in progress and requirements for further research. (author)

History, heresy and radiology in scientific discovery.

Science.gov (United States)

McCredie, J

2009-10-01

Nowadays, most drugs reach the market after research has established their pharmacology, safety and efficacy. That was not always the case 50 years ago. Thalidomide was used before its target cell or mode of action were known. Commencing with the thalidomide catastrophe--an epidemic of gross birth defects (1958-1962)--thalidomide's origins are revisited to show how this drug came to be made and sold in the 1950s. Thalidomide intersected with Australian radiology in the 1970s. The site and mode of action of the drug was deduced from X-rays of thalidomide-induced bone defects, which have classical radiological signs of sensory neuropathic osteoarthropathy. The longitudinal reduction deformities follow the distribution of segmental sensory innervation of the limb skeleton, indicating neural crest as the target organ. Injury to one level of neural crest halts normal neurotrophism and deletes the dependent segment--a previously unrecognised embryonic mechanism that explains most non-genetic birth defects. The final common pathway is neural crest injury and failure of normal neurotrophism to result in longitudinal reduction deformities, for example, phocomelia.

Radiology and the mobile device: Radiology in motion

Directory of Open Access Journals (Sweden)

Sridhar G Panughpath

2012-01-01

Full Text Available The use of mobile devices is revolutionizing the way we communicate, interact, are entertained, and organize our lives. With healthcare in general and radiology in particular becoming increasingly digital, the use of such devices in radiologic practice is inevitable. This article reviews the current status of the use of mobile devices in the clinical practice of radiology, namely in emergency teleradiology. Technical parameters such as luminance and resolution are discussed. The article also discusses the benefits of such mobility vis-à-vis the current limitations of the technologies available.

Radiology and the mobile device: Radiology in motion

International Nuclear Information System (INIS)

Panughpath, Sridhar G; Kalyanpur, Arjun

2012-01-01

The use of mobile devices is revolutionizing the way we communicate, interact, are entertained, and organize our lives. With healthcare in general and radiology in particular becoming increasingly digital, the use of such devices in radiologic practice is inevitable. This article reviews the current status of the use of mobile devices in the clinical practice of radiology, namely in emergency teleradiology. Technical parameters such as luminance and resolution are discussed. The article also discusses the benefits of such mobility vis-à-vis the current limitations of the technologies available

Bacteriological Monitoring of Radiology Room Apparatus in the Department of Radiological Technology and Contamination on Hands of Radiological Technologists

International Nuclear Information System (INIS)

Kim, Seon Chil

2008-01-01

Distribution of microorganisms were examined for the bucky tables in the radiology rooms of the department of radiological technology, the aprons, handles of various apparatus, handles of mobile radiological apparatus, and hands of the radiological technologists. As a result, relatively larger amounts of bacteria were found on the handles of the mobile radiological apparatus and the aprons. Among the isolated bacteria, Acinetobacter baumanni (7.3%), Klebsiella pneumoniae (6.7%), Staphylococcus aureus (3.9%), Serratia liquefaciens (1.7%), Enterobacter cloaceae (0.6%), Providenica rettgeri (0.6%) are known as the cause of nosocomial infection (hospital acquired infection). In addition, similar colonies were also found on the hands of the radiological technologists such as microorganisms of Klebsiella pneumoniae (8.4%), Staphylococcus aureus (6.6%), Yersinia enterocolotica (5.4%), Acinetobacter baumanni (4.2%), Enterobacter cloaceae (2.4%), Serratia liquefaciens (1.8%), Yersinia pseuotuberculosis (18%), Enterobacter sakazakii (1.2%), and Escherichia coli (0.6%). In particular, this result indicates clinical significance since Staphylococcus aureus and Escherichia coli show strong pathogenicity. Therefore, a continuous education is essential for the radiological technologists to prevent the nosocomial infection.

Bacteriological Monitoring of Radiology Room Apparatus in the Department of Radiological Technology and Contamination on Hands of Radiological Technologists

Energy Technology Data Exchange (ETDEWEB)

Kim, Seon Chil [Dept. of Radiologic Technology, Daegu Health College, Daegu (Korea, Republic of)

2008-12-15

Distribution of microorganisms were examined for the bucky tables in the radiology rooms of the department of radiological technology, the aprons, handles of various apparatus, handles of mobile radiological apparatus, and hands of the radiological technologists. As a result, relatively larger amounts of bacteria were found on the handles of the mobile radiological apparatus and the aprons. Among the isolated bacteria, Acinetobacter baumanni (7.3%), Klebsiella pneumoniae (6.7%), Staphylococcus aureus (3.9%), Serratia liquefaciens (1.7%), Enterobacter cloaceae (0.6%), Providenica rettgeri (0.6%) are known as the cause of nosocomial infection (hospital acquired infection). In addition, similar colonies were also found on the hands of the radiological technologists such as microorganisms of Klebsiella pneumoniae (8.4%), Staphylococcus aureus (6.6%), Yersinia enterocolotica (5.4%), Acinetobacter baumanni (4.2%), Enterobacter cloaceae (2.4%), Serratia liquefaciens (1.8%), Yersinia pseuotuberculosis (18%), Enterobacter sakazakii (1.2%), and Escherichia coli (0.6%). In particular, this result indicates clinical significance since Staphylococcus aureus and Escherichia coli show strong pathogenicity. Therefore, a continuous education is essential for the radiological technologists to prevent the nosocomial infection.

Radiological safety methodology in radioactive tracer applications for hydrodynamics and environmental studies; Metodologia de la seguridad radiologica en el empleo de trazadores radiactivos en estudios hidrodinamicos e ingenieria ambiental

Energy Technology Data Exchange (ETDEWEB)

Suarez, R; Badano, A; Dellepere, A; Artucio, G; Bertolotti, A [Nuclear Technology National Direction, Montevideo (Uruguay)

1995-07-01

The use of radioactive tracer techniques as control sewage disposal contamination in Montevideo Estuarine and Carrasco beach has been studied for the Nuclear Technology National Direction. Hydrodynamic models simulation has been introduced as work methodology. As well as radiological safety and radioactive material applications in the environmental studies has been evaluated mainly in the conclusions and recommendations in this report. maps.

Understanding Mechanisms of Radiological Contamination

Energy Technology Data Exchange (ETDEWEB)

Rick Demmer; John Drake; Ryan James, PhD

2014-03-01

Over the last 50 years, the study of radiological contamination and decontamination has expanded significantly. This paper addresses the mechanisms of radiological contamination that have been reported and then discusses which methods have recently been used during performance testing of several different decontamination technologies. About twenty years ago the Idaho Nuclear Technology Engineering Center (INTEC) at the INL began a search for decontamination processes which could minimize secondary waste. In order to test the effectiveness of these decontamination technologies, a new simulated contamination, termed SIMCON, was developed. SIMCON was designed to replicate the types of contamination found on stainless steel, spent fuel processing equipment. Ten years later, the INL began research into methods for simulating urban contamination resulting from a radiological dispersal device (RDD). This work was sponsored by the Defense Advanced Research Projects Agency (DARPA) and included the initial development an aqueous application of contaminant to substrate. Since 2007, research sponsored by the US Environmental Protection Agency (EPA) has advanced that effort and led to the development of a contamination method that simulates particulate fallout from an Improvised Nuclear Device (IND). The IND method diverges from previous efforts to create tenacious contamination by simulating a reproducible “loose” contamination. Examining these different types of contamination (and subsequent decontamination processes), which have included several different radionuclides and substrates, sheds light on contamination processes that occur throughout the nuclear industry and in the urban environment.

Offsite dose calculation manual guidance: Standard radiological effluent controls for boiling water reactors

International Nuclear Information System (INIS)

Meinke, W.W.; Essig, T.H.

1991-04-01

This report contains guidance which may be voluntarily used by licensees who choose to implement the provision of Generic Letter 89-- 01, which allows Radiological Effluent Technical Specifications (RETS) to be removed from the main body of the Technical Specifications and placed in the Offsite Dose Calculation Manual (ODCM). Guidance is provided for Standard Effluent Controls definitions, Controls for effluent monitoring instrumentation, Controls for effluent releases, Controls for radiological environmental monitoring, and the basis for Controls. Guidance on the formulation of RETS has been available in draft form for a number of years; the current effort simply recasts those RETS into Standard Radiological Effluent Controls for application to the ODCM. 11 tabs

Portrayal of radiology in a major medical television series: How does it influence the perception of radiology among patients and radiology professionals?

International Nuclear Information System (INIS)

Heye, T.; Merkle, E.M.; Boll, D.T.; Leyendecker, J.R.; Gupta, R.T.

2016-01-01

To assess how the portrayal of Radiology on medical TV shows is perceived by patients and radiology professionals. In this IRB-approved study with patient consent waived, surveys were conducted among adult patients scheduled for radiological examinations and radiology professionals. The questionnaire investigated medical TV watching habits including interest in medical TV shows, appearance of radiological examination/staff, radiology's role in diagnosis-making, and rating of the shows' accuracy in portraying radiology relative to reality. One hundred and twenty-six patients and 240 professionals (133 technologists, 107 radiologists) participated. 63.5 % patients and 63.2 % technologists rated interest in medical TV shows ≥5 (scale 1-10) versus 38.3 % of radiologists. All groups noted regular (every 2nd/3rd show) to >1/show appearance of radiological examinations in 58.5-88.2 % compared to 21.0-46.2 % for radiological staff appearance. Radiology played a role in diagnosis-making regularly to >1/show in 45.3-52.6 %. There is a positive correlation for interest in medical TV and the perception that radiology is accurately portrayed for patients (r = 0.49; P = 0.001) and technologists (r = 0.38; P = 0.001) but not for radiologists (r = 0.01). The majority of patients perceive the portrayed content as accurate. Radiologists should be aware of this cultivation effect to understand their patients' behaviour which may create false expectations towards radiological examinations and potential safety hazards. (orig.)

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

Environmental protection

International Nuclear Information System (INIS)

Hull, A.P.

1979-01-01

Environmental Studies and Internal Dosimetry projects include: Environmental Protection; 1977 Environmental Monitoring Report; Sewage Sludge Disposal on the Sanitary Landfill; Radiological Analyses of Marshall Islands Environmental Samples, 1974 to 1976; External Radiation Survey and Dose Predictions for Rongelap, Utirik, Rongerik, Ailuk, and Wotje Atolls; Marshall Islands - Diet and Life Style Study; Dose Reassessment for Populations on Rongelap and Utirik Following Exposure to Fallout from BRAVO Incident (March 1, 1954); Whole Body Counting Results from 1974 to 1979 for Bikini Island Residents; Dietary Radioactivity Intake from Bioassay Data, a Model Applied to 137 Cs Intake by Bikini Island Residents; and External Exposure Measurements at Bikini Atoll

Radiological monitoring related to the operation of PUSPATI's Triga Reactor

International Nuclear Information System (INIS)

Fatimah Mohamad Amin; Mohamad Yusof Mohamad Ali; Lau How Mooi; Idris Besar.

1983-01-01

Reactor operation is one of the main activities carried out at the Tun Ismail Atomic Research Centre (PUSPATI) which requires radiological monitoring. This paper describes the programme for radiological monitoring which is related to the operation of the 1 MW Triga MK II research reactor which was commissioned in July, 1982. This programme includes monitoring of the radiation and contamination levels of the reactor and its associated facilities and environmental monitoring of PUSPATI's site and its environs. The data presented in this paper covers the period between 1982 to 1983 which includes both the pre-operational and operational phases of the monitoring programme. (author)

Semi-portable whole body counter deployable during post-radiological accident

International Nuclear Information System (INIS)

Panchal, C.G.; Bansode, P.Y.; Vinod, M.; Sarade, Bhagyashree; Jain, R.K.; Jakati, R.K.; Pithawa, C.K.

2012-01-01

A versatile whole body counter with the state of art electronics has been indigenously designed and developed which can be readily deployed for use during nuclear emergency. This instrument is designed to quickly identify and quantify the activity of high energy photon emitters accumulated particularly in vital organs like thyroid, lungs besides the body of the victims of the radiological incident or accident. Special features of the instruments are swivel type detectors assembly mountable on a wall or table top and detachable collimator configurable to assess the internal contamination selectively to meet protective measures of the radiological accidents, mechanically rugged and functionally reliable to perform in contaminated environmental field conditions. (author)

Current radiology. Volume 5

International Nuclear Information System (INIS)

Wilson, G.H.; Hanafee, W.N.

1984-01-01

This book contains 10 selections. They are: Nuclear Magnetic Resonance Imaging, Interventional Vascular Radiology, Genitourinary Radiology, Skeletal Radiology, Digital Subtraction Angiography, Neuroradiology, Computed Tomographic Evaluation of Degenerative Diseases of the Lumbar Spine, The Lung, Otolaringology and Opthalmology, and Pediatric Radiology: Cranial, Facial, Cervical, Vertebral, and Appendicular

Medical Ethics in Radiology

International Nuclear Information System (INIS)

Kim, Kyung Won; Park, Jae Hyung; Yoon, Soon Ho

2010-01-01

According to the recent developments in radiological techniques, the role of radiology in the clinical management of patients is ever increasing and in turn, so is the importance of radiology in patient management. Thus far, there have been few open discussions about medical ethics related to radiology in Korea. Hence, concern about medical ethics as an essential field of radiology should be part of an improved resident training program and patient management. The categories of medical ethics related with radiology are ethics in the radiological management of patient, the relationship of radiologists with other medical professionals or companies, the hazard level of radiation for patients and radiologists, quality assurance of image products and modalities, research ethics, and other ethics issues related to teleradiology and fusion imaging. In order to achieve the goal of respectful progress in radiology as well as minimizing any adverse reaction from other medical professions or society, we should establish a strong basis of medical ethics through the continuous concern and self education

Critical pathway studies for selected radionuclides. Part of a coordinated programme on environmental monitoring for radiological protection in Asia and the Far East

International Nuclear Information System (INIS)

Bhat, I.S.

1980-04-01

The programme carried out critical pathway studies for selected radionuclides ( 60 Co, 63 Ni, 59 Fe, 54 Mn, sup(110m)Ag, 106 Ru and 144 Ce) and assessed population exposure in the vicinity of Tarapur Atomic Power Station. The following topics are covered under the programme. (i) Demographic study of dietary habits and consumption data for Tarapur population. (ii) Concentration and accumulation of radionuclides in food products. (iii) Determination of radionuclides in sea water, silt, marine algae and marine organisms at Tarapur Atomic Power Station (TAPS) Site. (iv) Behaviour of radionuclides released to marine environment. (v) Evaluation of critical exposure pathway. (vi) Population exposure in the vicinity of Tarapur Atomic Power Station

Analysis of papers in radiological journals in recent years: a comparison of journal of Korean radiologic society and radiology

International Nuclear Information System (INIS)

Kim, Jin Suh; Kim, Jae Kyun; Han, Dong Bok; Lim, Tae Hwan

1997-01-01

The purpose of this study was to determine current trends and the mode of future development in the field of medical radiology and to promote research among the nation's radiologists by analyzing the contents of the Journal of the Korean Radiologic Society(JKRS) and Radiology. The number of articles published in JKRS each year between 1990 and 1994 was counted. The research articles in JKRS(n=740) and in Radiology(n=1748) between 1992 and 1994 were categorized according to the objective, type, topic, materials, and radiologic techniques of their contents on the basis of predetermined criteria. Domestic Masters theses(n=126) and doctoral dissertations(n=75) accepted between 1990 and 1994, and domestic materials published in international journals (n=416) between 1986 and 1994 were also categorized using the same criteria. The greatest increase in the number of articles published in JKRS was seen during 1994. The majority of these aimed to retrospectively analyse the findings of diseases while the majority of articles published in Radiology dealt prospectively with the development and/or evaluation of diagnostic methods. More variety of topics and issues was seen in Radiology than in JKRS. The number of articles of domestic materials published in international journals increased from 1986 to 1994, while the number of articles of foreign materials published in Korea was relatively stationary : A significant number of theses and dissertations dealt, mostly prospectively, with studies of pathophysiologic and/or pharmacologic mechanisms using animal models. In order to understand both current trends and the direction and mode of future developments in the field of radiology, and to be able to actively deal with challenges at the forefront of radiologic development, it is essential to review research articles published in radiology-related journals

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).

Portsmouth annual environmental report for 2003, Piketon, Ohio

Energy Technology Data Exchange (ETDEWEB)

none, none

2004-11-30

The Portsmouth & Gaseous Diffusion Plant (PORTS) is located on a 5.8-square-mile site in a rural area of Pike County, Ohio. U.S. Department of Energy (DOE) activities at PORTS include environmental restoration, waste 'management, and long-term'stewardship of nonleased facilities: Production facilities for the separation of uranium isotopes are leased to the United States Enrichment Corporation (USEC), but most activities associated with the uranium enrichment process ceased in 2001. USEC activities are not covered by this document, with the exception of some environmental compliance information provided in Chap. 2 and radiological and non-radiological environmental monitoring program information discussed in Chaps. 4 and 5.

Determination of Radiological Hazard Associated with the use of ...

African Journals Online (AJOL)

Journal of Applied Sciences and Environmental Management ... calculated to be 17.41nGyhr-1 with mean annual effective dose rate of 0.022mSvyr-1The values of the radiological indicators were found to be within the limits recommended for safety, indicating that the use of the sediment of the river as building material does ...

Machine Learning and Radiology

Science.gov (United States)

Wang, Shijun; Summers, Ronald M.

2012-01-01

In this paper, we give a short introduction to machine learning and survey its applications in radiology. We focused on six categories of applications in radiology: medical image segmentation, registration, computer aided detection and diagnosis, brain function or activity analysis and neurological disease diagnosis from fMR images, content-based image retrieval systems for CT or MRI images, and text analysis of radiology reports using natural language processing (NLP) and natural language understanding (NLU). This survey shows that machine learning plays a key role in many radiology applications. Machine learning identifies complex patterns automatically and helps radiologists make intelligent decisions on radiology data such as conventional radiographs, CT, MRI, and PET images and radiology reports. In many applications, the performance of machine learning-based automatic detection and diagnosis systems has shown to be comparable to that of a well-trained and experienced radiologist. Technology development in machine learning and radiology will benefit from each other in the long run. Key contributions and common characteristics of machine learning techniques in radiology are discussed. We also discuss the problem of translating machine learning applications to the radiology clinical setting, including advantages and potential barriers. PMID:22465077

Annual report of National Institute of Radiological Sciences, April 1989 - March 1990

International Nuclear Information System (INIS)

1990-07-01

This annual report is a compilation of the research activities and achievement in the National Institute of Radiological Sciences (NIRS) in Japan during the fiscal year 1990 (from April 1989 through March 1990). Efforts at the NIRS are particularly aimed at three long term projects: 'risk due to low level radiation exposure to the general population', 'assessment of radiation exposure of the public to radioactivities as related to the environment', and 'food chain and medical use of accelerated heavy ions'. The research covers a wide range of radiological sciences from molecular to environmental studies and medicine including engineering. Topics consists of physics, chemistry, bio-medical science, clinical research, and environmental sciences, covering a total of 80 titles. A list of publications by staff members, activities of research divisions, and organization chart of the NIRS are given in Appendix. (N.K.)

Critical evaluation of German regulatory specifications for calculating radiological exposure

Energy Technology Data Exchange (ETDEWEB)

Koenig, Claudia; Walther, Clemens [Hannover Univ. (Germany). Inst. of Radioecology; Smeddinck, Ulrich [Technische Univ. Braunschweig (Germany). Inst. of Law

2015-07-01

The assessment of radiological exposure of the public is an issue at the interface between scientific findings, juridical standard setting and political decision. The present work revisits the German regulatory specifications for calculating radiological exposure, like the already existing calculation model General Administrative Provision (AVV) for planning and monitoring nuclear facilities. We address the calculation models for the recent risk assessment regarding the final disposal of radioactive waste in Germany. To do so, a two-pronged approach is pursued. One part deals with radiological examinations of the groundwater-soil-transfer path of radionuclides into the biosphere. Processes at the so-called geosphere-biosphere-interface are examined, especially migration of I-129 in the unsaturated zone. This is necessary, since the German General Administrative Provision does not consider radionuclide transport via groundwater from an underground disposal facility yet. Especially data with regard to processes in the vadose zone are scarce. Therefore, using I-125 as a tracer, immobilization and mobilization of iodine is investigated in two reference soils from the German Federal Environment Agency. The second part of this study examines how scientific findings but also measures and activities of stakeholders and concerned parties influence juridical standard setting, which is necessary for risk management. Risk assessment, which is a scientific task, includes identification and investigation of relevant sources of radiation, possible pathways to humans, and maximum extent and duration of exposure based on dose-response functions. Risk characterization identifies probability and severity of health effects. These findings have to be communicated to authorities, who have to deal with the risk management. Risk management includes, for instance, taking into account acceptability of the risk, actions to reduce, mitigate, substitute or monitor the hazard, the setting of

Cursory radiological assessment: Battelle Columbus Laboratory Decommissioning and Decontamination Project

International Nuclear Information System (INIS)

Smith, W.H.; Munyon, W.J.; Mosho, G.D.; Robinet, M.J.; Wynveen, R.A.

1988-10-01

This document reports on the results obtained from a cursory radiological assessment of various properties at the Battelle Columbus Laboratory, Columbia, Ohio. The cursory radiological assessment is part of a preliminary investigation for the Battelle Columbus Laboratory Decommissioning and Decontamination Project. The radiological assessment of Battelle Columbus Laboratory's two sites included conducting interior and exterior building surveys and collecting and analyzing air, sewer system, and soil samples. Direct radiological surveys were made of floor, wall, and overhead areas. Smear surveys were made on various interior building surfaces as well as the exterior building vents. Air samples were collected in select areas to determine concentrations of Rn-222, Rn-220, and Rn-219 daughters, in addition to any long-lived radioactive particulates. Radon-222 concentrations were continuously monitored over a 24-hr period at several building locations using a radon gas monitoring system. The sanitary sewer systems at King Avenue, West Jefferson-North, and West Jefferson-South were each sampled at select locations. All samples were submitted to the Argonne Analytical Chemistry Laboratory for various radiological and chemical analyses. Environmental soil corings were taken at both the King Avenue and West Jefferson sites to investigate the potential for soil contamination within the first 12-inches below grade. Further subsurface investigations at the West Jefferson-North and West Jefferson-South areas were conducted using soil boring techniques. 4 refs., 10 figs., 10 tabs

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.

Pediatric radiology malpractice claims - characteristics and comparison to adult radiology claims

Energy Technology Data Exchange (ETDEWEB)

Breen, Micheal A.; Taylor, George A. [Boston Children' s Hospital, Department of Radiology, Boston, MA (United States); Dwyer, Kathy; Yu-Moe, Winnie [CRICO Risk Management Foundation, Boston, MA (United States)

2017-06-15

Medical malpractice is the primary method by which people who believe they have suffered an injury in the course of medical care seek compensation in the United States and Canada. An increasing body of research demonstrates that failure to correctly diagnose is the most common allegation made in malpractice claims against radiologists. Since the 1994 survey by the Society of Chairmen of Radiology in Children's Hospitals (SCORCH), no other published studies have specifically examined the frequency or clinical context of malpractice claims against pediatric radiologists or arising from pediatric imaging interpretation. We hypothesize that the frequency, character and outcome of malpractice claims made against pediatric radiologists differ from those seen in general radiology practice. We searched the Controlled Risk Insurance Co. (CRICO) Strategies' Comparative Benchmarking System (CBS), a private repository of approximately 350,000 open and closed medical malpractice claims in the United States, for claims related to pediatric radiology. We further queried these cases for the major allegation, the clinical environment in which the claim arose, the clinical severity of the alleged injury, indemnity paid (if payment was made), primary imaging modality involved (if applicable) and primary International Classification of Diseases, 9th revision (ICD-9) diagnosis underlying the claim. There were a total of 27,056 fully coded claims of medical malpractice in the CBS database in the 5-year period between Jan. 1, 2010, and Dec. 31, 2014. Of these, 1,472 cases (5.4%) involved patients younger than 18 years. Radiology was the primary service responsible for 71/1,472 (4.8%) pediatric cases. There were statistically significant differences in average payout for pediatric radiology claims ($314,671) compared to adult radiology claims ($174,033). The allegations were primarily diagnosis-related in 70% of pediatric radiology claims. The most common imaging modality

Pediatric radiology malpractice claims - characteristics and comparison to adult radiology claims

International Nuclear Information System (INIS)

Breen, Micheal A.; Taylor, George A.; Dwyer, Kathy; Yu-Moe, Winnie

2017-01-01

Medical malpractice is the primary method by which people who believe they have suffered an injury in the course of medical care seek compensation in the United States and Canada. An increasing body of research demonstrates that failure to correctly diagnose is the most common allegation made in malpractice claims against radiologists. Since the 1994 survey by the Society of Chairmen of Radiology in Children's Hospitals (SCORCH), no other published studies have specifically examined the frequency or clinical context of malpractice claims against pediatric radiologists or arising from pediatric imaging interpretation. We hypothesize that the frequency, character and outcome of malpractice claims made against pediatric radiologists differ from those seen in general radiology practice. We searched the Controlled Risk Insurance Co. (CRICO) Strategies' Comparative Benchmarking System (CBS), a private repository of approximately 350,000 open and closed medical malpractice claims in the United States, for claims related to pediatric radiology. We further queried these cases for the major allegation, the clinical environment in which the claim arose, the clinical severity of the alleged injury, indemnity paid (if payment was made), primary imaging modality involved (if applicable) and primary International Classification of Diseases, 9th revision (ICD-9) diagnosis underlying the claim. There were a total of 27,056 fully coded claims of medical malpractice in the CBS database in the 5-year period between Jan. 1, 2010, and Dec. 31, 2014. Of these, 1,472 cases (5.4%) involved patients younger than 18 years. Radiology was the primary service responsible for 71/1,472 (4.8%) pediatric cases. There were statistically significant differences in average payout for pediatric radiology claims ($314,671) compared to adult radiology claims ($174,033). The allegations were primarily diagnosis-related in 70% of pediatric radiology claims. The most common imaging modality implicated in

Pediatric radiology malpractice claims - characteristics and comparison to adult radiology claims.