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Sample records for recommended environmental dose

  1. Recommended environmental dose calculation methods and Hanford-specific parameters

    International Nuclear Information System (INIS)

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

    1993-03-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1993-03-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1993-03-01

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

  4. Analyse of the international recommendations on the calculation of absorbed dose in the biota

    International Nuclear Information System (INIS)

    Pereira, Wagner de S.; Py Junior, Delcy de A.; Universidade Federal Fluminense; Kelecom, Alphonse

    2011-01-01

    This paper evaluates the recommendations of ICRP which has as objective the environmental radioprotection. It was analysed the recommendations 26, 60, 91, 103 and 108 of the ICRP. The ICRP-103 defined the concept of animal and plant of reference (APR) to be used in the RAP based on the calculation of absorbed dose based on APR concept. This last view allows to build a legal framework of environmental protection with a etic, moral and scientific visualization, more defensible than the anthropomorphic concept

  5. Environmental dose reconstruction: Approaches to an inexact science

    International Nuclear Information System (INIS)

    Hoffman, F.O.

    1991-01-01

    The endpoints of environmental dose reconstruction are quantitative yet the science is inexact. Four problems related to this issue are described. These problems are: (1) Defining the scope of the assessment and setting logical priorities for detailed investigations, (2) Recognizing the influence of investigator judgment of the results, (3) Selecting an endpoint other than dose for the assessment of multiple contaminants, and (4) Resolving the conflict between credibility and expertise in selecting individuals responsible for dose reconstruction. Approaches are recommended for dealing with each of these problems

  6. Hanford environmental dose reconstruction project - an overview

    International Nuclear Information System (INIS)

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

    1996-01-01

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

  7. Analyse of the international recommendations on the calculation of absorbed dose in the biota; Analise das recomendacoes internacionais sobre calculo de dose absorvida na biota

    Energy Technology Data Exchange (ETDEWEB)

    Pereira, Wagner de S.; Py Junior, Delcy de A., E-mail: wspereira@inb.gov.b, E-mail: delcy@inb.gov.b [Industrias Nucleares do Brasil (UTM/INB), Pocos de Caldas, MG (Brazil). Unidade de Tratamento de Minerios; Universidade Federal Fluminense (LARARA/UFF), Niteroi, RJ (Brazil). Lab. de Radiobiologia e Radiometria; Kelecom, Alphonse [Universidade Federal Fluminense (UFF), Niteroi, RJ (Brazil). Programa de Pos-Graduacao em Ciencia Ambiental

    2011-10-26

    This paper evaluates the recommendations of ICRP which has as objective the environmental radioprotection. It was analysed the recommendations 26, 60, 91, 103 and 108 of the ICRP. The ICRP-103 defined the concept of animal and plant of reference (APR) to be used in the RAP based on the calculation of absorbed dose based on APR concept. This last view allows to build a legal framework of environmental protection with a etic, moral and scientific visualization, more defensible than the anthropomorphic concept

  8. International recommendations for managing environmental risk from nuclear energy production

    International Nuclear Information System (INIS)

    Clarke, R.H.

    1996-01-01

    The establishment of any recommendations relating to the control of radiation exposure requires decisions on the management of the associated risk. Those decisions must reflect attitudes towards the acceptable levels of risk for both workers and the public. The environmental impact of nuclear energy principally concerns radiation doses and risks to members of the public. The author shows how the considerations of risk and acceptability are used internationally to set standards for protection. The results differ as between limiting doses for normal operations, for restricting the likelihood of accidents, intervening after an accident, or reducing doses from a chronic exposure situation. It is concluded that there is a coherent pattern in the resulting protection system

  9. Hanford Environmental Dose Reconstruction Project

    International Nuclear Information System (INIS)

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

    1992-10-01

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

  10. Hanford Environmental Dose Reconstruction Project

    International Nuclear Information System (INIS)

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

    1991-04-01

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

  11. ICRP-recommendations on dose limits for workers

    International Nuclear Information System (INIS)

    Beninson, D.J.

    1976-01-01

    Dose limits proposed by the ICRP have been incorporated in most national and international standards and their respect has caused a distribution of doses with a average not exceeding 1/10 of the maximum permissible dose. This distribution corresponds to a risk which is well within the risks in 'safe industries'. There are at present some inconsistancies in the current system of recommended limits, for example having the same limit of 5 rem for the whole-body and also for some organs. Hopefully, this incosistancy will be removed in the next recommendation of the ICRP. But the whole-body limit of 5 rem in a year has been safe and there is little ground to reduce this limit on the basis of comparisons with 'safe industries'. (orig./HP) [de

  12. Hanford Environmental Dose Reconstruction Project

    International Nuclear Information System (INIS)

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

    1992-06-01

    The objective of the Hanford Environmental Dose Reconstruction Project is to estimate the radiation doses that individuals and populations could have received from nuclear operations at Hanford since 1944. The project is being managed and conducted by the Battelle Pacific Northwest Laboratories under contract with the Centers for Disease Control. The independent Technical Steering Panel (TSP) provides technical direction. The project is divided into the following technical tasks. These tasks correspond to the path radionuclides followed, from release to impact on humans (dose estimates): source terms; environmental transport; environmental monitoring data; demography, food consumption, and agriculture; environmental pathways and dose estimates

  13. Hanford Environmental Dose Reconstruction Project

    International Nuclear Information System (INIS)

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

    1992-07-01

    The objective of the Hanford Environmental Dose Reconstruction (HEDR) Project is to estimate the radiation doses that individuals and populations could have received from nuclear operations at Hanford since 1944. The TSP consists of experts in environmental pathways, epidemiology, surface-water transport, ground-water transport, statistics, demography, agriculture, meteorology, nuclear engineering, radiation dosimetry, and cultural anthropology. Included are appointed technical members representing the states of Oregon, Washington, and Idaho, a representative of Native American tribes, and an individual representing the public. The project is divided into the following technical tasks. These tasks correspond to the path radionuclides followed from release to impact on humans (dose estimates): Source terms, environmental transport, environmental monitoring data, demography, food consumption, and agriculture, and environmental pathways and dose estimates. Progress is discussed

  14. Animal data on GI-tract uptake of plutonium - implications for environmental dose assessments

    International Nuclear Information System (INIS)

    Kocher, D.C.; Ryan, M.T.

    1983-01-01

    A selection of published data on GI-tract uptake of ingested plutonium in animals is reviewed for the purpose of estimating an uptake fraction which would be appropriate for environmental dose assessments in adult humans. Recent data in the adult rat and guinea pig suggest that a GI-tract uptake fraction of 10 -3 would be a reasonable and prudent choice for ingestion of environmental plutonium by adults. This value is a factor of ten larger than the value currently recommended by the International Commission on Radiological Protection for assessing doses from occupational exposures. (author)

  15. On revision of definition of doses for radiation protection in ICRP 1990 recommendations

    International Nuclear Information System (INIS)

    Yoshizawa, Michio

    1995-01-01

    The recommendation of ICRP is to give the guideline to the organizations and experts concerned to radiation protection including regulatory authorities on the basic rule which becomes the basis of proper radiation protection, and the radiation protection in respective countries has been carried out, respecting this ICRP recommendation. In 1990, ICRP revised this basic recommendation, and published as Publication 60. In this 1990 recommendation, as the matters that give impact to the dose evaluation of external exposure, the introduction of the new concept of dose, namely radiation weighting factor and equivalent dose, the revision of radiation quality factor and so on are enumerated. As to the 1990 recommendation, absorbed dose and organ dose, radiation weighting factor, equivalent dose, effective dose, quality factor-LET relation, the summation with the former quantities and the operational quantity of ICRU are described. The reason why radiation weighting factor and equivalent dose were introduced are discussed, including the inference of the author. (K.I.)

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

    International Nuclear Information System (INIS)

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

    1998-01-01

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

  17. Recommendations for the Preparation of Environmental Assessments and Environmental Impact Statements, 2nd edition

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2004-12-01

    This document provides recommendations for the Department of Energy’s (DOE’s) preparation of environmental assessments and environmental impact statements under the National Environmental Policy Act of 1969 (NEPA). The Office of NEPA Policy and Compliance prepared these recommendations in consultation with the Office of the Assistant General Counsel for Environment and following coordination with the DOE NEPA Community. The recommendations should materially aid those responsible for preparing and reviewing NEPA documents to focus on significant environmental issues, adequately analyze environmental impacts, and effectively present the analysis to decisionmakers and the public. The recommendations are not all-encompassing, however; preparers must apply independent judgment to determine the appropriate scope and analytical requirements of NEPA for each proposal. These recommendations do not constitute legal requirements, but are intended to enhance compliance with existing NEPA regulations (40 CFR Parts 1500-1508, 10 CFR Part 1021).

  18. Hanford Environmental Dose Reconstruction Project monthly report

    International Nuclear Information System (INIS)

    Finch, S.M.

    1991-10-01

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

  19. Environmental dose-assessment methods for normal operations at DOE nuclear sites

    International Nuclear Information System (INIS)

    Strenge, D.L.; Kennedy, W.E. Jr.; Corley, J.P.

    1982-09-01

    Methods for assessing public exposure to radiation from normal operations at DOE facilities are reviewed in this report. The report includes a discussion of environmental doses to be calculated, a review of currently available environmental pathway models and a set of recommended models for use when environmental pathway modeling is necessary. Currently available models reviewed include those used by DOE contractors, the Environmental Protection Agency (EPA), the Nuclear Regulatory Commission (NRC), and other organizations involved in environmental assessments. General modeling areas considered for routine releases are atmospheric transport, airborne pathways, waterborne pathways, direct exposure to penetrating radiation, and internal dosimetry. The pathway models discussed in this report are applicable to long-term (annual) uniform releases to the environment: they do not apply to acute releases resulting from accidents or emergency situations

  20. Hanford Environmental Dose Reconstruction Project monthly report

    International Nuclear Information System (INIS)

    Finch, S.M.

    1990-12-01

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

  1. Application of ICRP recommendations relevant to internal dose

    International Nuclear Information System (INIS)

    Cowser, K.E.; Snyder, W.S.; Struxness, E.G.

    1969-01-01

    The intent of this paper is to review several of the basic concepts of radiation protection (with emphasis on internal dose) currently recommended by the International Commission on radiological Protection (ICRP), to summarize the assumptions and methods used in the calculation of internal dose, and to illustrate by example the practical application of the pertinent guidelines. Two broad subject areas are considered: (1) standards of radiation protection and (2) bases of internal dose estimation. Topics discussed within the framework of radiation protection standards include maximum permissible dose, categories of radiation exposure, maximum permissible dose commitment, simultaneous internal and external exposure, multiple organ exposure, and size of the exposed group. Discussion of internal dose estimation is limited to selected items that include the body burden of radionuclides and the calculation of absorbed dose, the dose equivalent, the derivation of maximum permissible concentration (MPC), the relationship of stable element intake to the MPC, and short term and chronic exposure situations. (author)

  2. Application of ICRP recommendations relevant to internal dose

    Energy Technology Data Exchange (ETDEWEB)

    Cowser, K E; Snyder, W S; Struxness, E G [Health Physics Division, Oak Ridge National Laboratory, Oak Ridge, TN (United States)

    1969-07-01

    The intent of this paper is to review several of the basic concepts of radiation protection (with emphasis on internal dose) currently recommended by the International Commission on radiological Protection (ICRP), to summarize the assumptions and methods used in the calculation of internal dose, and to illustrate by example the practical application of the pertinent guidelines. Two broad subject areas are considered: (1) standards of radiation protection and (2) bases of internal dose estimation. Topics discussed within the framework of radiation protection standards include maximum permissible dose, categories of radiation exposure, maximum permissible dose commitment, simultaneous internal and external exposure, multiple organ exposure, and size of the exposed group. Discussion of internal dose estimation is limited to selected items that include the body burden of radionuclides and the calculation of absorbed dose, the dose equivalent, the derivation of maximum permissible concentration (MPC), the relationship of stable element intake to the MPC, and short term and chronic exposure situations. (author)

  3. Maximum tolerable radiation doses recommended by the Israel Advisory Committee on nuclear safety

    International Nuclear Information System (INIS)

    Tadmor, J.; Litai, D.; Lubin, E.

    1978-01-01

    Maximum tolerable doses have been recommended by the Israel Advisory Committee on Nuclear Safety. The recommendations which are based on a comparison with risks tolerated in other human activities, are for doses to radiation workers, for individual members of the population at the fence of a nuclear installation, and for the population at large, for both normal operating and accident conditions. Tolerable whole-body doses and doses to different critical organs are listed

  4. Hanford Environmental Dose Reconstruction Project monthly report

    International Nuclear Information System (INIS)

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

    1992-09-01

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

  5. Current status on preparation of dose conversion factors based on 1990 ICRP recommendations

    International Nuclear Information System (INIS)

    Yoshizawa, Michio

    1996-01-01

    The current status of arrangement of dose conversion factors for operational quantities are explained on the basis of 1995 ICRP-ICRU recommendations. The dose conversion factors of photon, neutron and electron were recommended by ICRP Publ. 74. It's contents are described. The relation between new dose conversion factors and the laws in connection with protecting radiation are explained. The dose conversion factors of 1 cm-, 3 mm- and 70 μm - dose equivalent which were introduced into the laws connected therewith in Japan are accepted the same values of ICRP Publ. 51 for photon and neutron. I mentioned the points of discussing about new dose conversion factors which are expected to be recommended. The laws have to show the dose conversion factors to be used by calculation and estimation of radiation shield, etc. The limit of energy of ICRU individual dose equivalent for photon is now until 1 MeV, but the value is insufficient and necessary to 10 MeV as same as the ambient dose equivalent in due consideration of atomic energy facilities. JAERI is preparing these dose conversion factors now. (S.Y.)

  6. Hanford Environmental Dose Reconstruction Project monthly report, August 1992

    International Nuclear Information System (INIS)

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

    1992-01-01

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

  7. Correspondence of the ICRP database of dose coefficients (1996) to 2007 recommendations of the ICRP

    International Nuclear Information System (INIS)

    Kadatskaya, M.M.

    2012-01-01

    The new IAEA international safety standards, issued in 2011, recommend in practical implementation of the 2007 Recommendations of the ICRP continue to use dosimetric database developed in 1996. This article presents method and results of the calculation of committed effective dose of internal exposure in accordance with the new definition of this quantity given in 2007 Recommendations of the ICRP. It is shown that in the control of internal doses in accordance with the 2007 Recommendations of the ICRP it is allowed to use dose factors which were released in 1996. (authors)

  8. Yellow Fever Vaccine Booster Doses: Recommendations of the Advisory Committee on Immunization Practices, 2015.

    Science.gov (United States)

    Staples, J Erin; Bocchini, Joseph A; Rubin, Lorry; Fischer, Marc

    2015-06-19

    On February 26, 2015, the Advisory Committee on Immunization Practices (ACIP) voted that a single primary dose of yellow fever vaccine provides long-lasting protection and is adequate for most travelers. ACIP also approved recommendations for at-risk laboratory personnel and certain travelers to receive additional doses of yellow fever vaccine (Box). The ACIP Japanese Encephalitis and Yellow Fever Vaccines Workgroup evaluated published and unpublished data on yellow fever vaccine immunogenicity and safety. The evidence for benefits and risks associated with yellow fever vaccine booster doses was evaluated using the Grading of Recommendations, Assessment, Development, and Evaluation (GRADE) framework. This report summarizes the evidence considered by ACIP and provides the updated recommendations for yellow fever vaccine booster doses.

  9. The Hanford Environmental Dose Reconstruction Project: Overview

    International Nuclear Information System (INIS)

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

    1990-01-01

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

  10. Low and very low doses, new recommendations?

    International Nuclear Information System (INIS)

    Foucher, N.

    1999-01-01

    The topic of the seminar organized by the world council of nuclear workers (WONUC) was the effects of low or very low doses on human health. Discussions centred round the linearity of the relation between dose and effect in the evaluation and management of the health hazard. The recommendations proposed by ICPR (international commission for radiological protection) are based on this linearity as a precaution. On the one hand it is remembered that low dose irradiation might be beneficial. It has been proved that the irradiation of the whole body is efficient in case of Hodgkin lymphoma. On the other hand it is remembered that doses as low as 10 mSv in utero have led to an excess of cancer in children. Studies based on experimentally radio-induced cancers have been carried out in Japan, China, Canada and France.Their results seem to be not consistent with the hypothesis of linearity. During the last decade a lot of work has been made but a conclusion is far to be reached, it is said that the American department of energy (DOE) has invited bids in 1999 to launch research programs in order to clarify the situation. (A.C.)

  11. Recommended de minimis radiation dose rates for Canada

    International Nuclear Information System (INIS)

    1990-07-01

    A de minimis dose or dose rate as used in this report represents a level of risk which is generally accepted as being of no significance to an individual, or in the case of a population, of no significance to society. The doses corresponding to these levels of risk are based on current scientific knowledge. Dose rates recommended in this report are as follows: a de minimis individual dose rate of 10 μSv a -1 , based on a risk level that would generally be regarded as negligible in comparison with other risks; and a de minimis collective dose rate of 1 person-Sv a -1 , based on an imperceptible increase above the normal incidences of cancer and genetic defects in the exposed population. The concept of de minimis is to be distinguished from 'exempt from regulation' (below regulatory concern). The latter involves broader social and economic factors which encompass but are not limited to the purely risk-based factors addressed by the de minimis dose. De minimis is one of the factors that determine the exemption of sources or practices that may result in doses below or above the de minimis level. Although these de minimis dose rates should be considered in developing criteria and guidelines for deriving quantities and concentrations of radioactive substances that may be exempted from regulation, this document is only concerned with establishing de minimis dose rates, not with exempting sources and practices

  12. The incidence of phlebitis with intravenous amiodarone at guideline dose recommendations.

    Science.gov (United States)

    Slim, Ahmad M; Roth, Jason E; Duffy, Benjamin; Boyd, Sheri Y N; Rubal, Bernard J

    2007-12-01

    Postoperative atrial fibrillation following cardiothoracic surgery is common and frequently managed with intravenous (IV) amiodarone. Phlebitis is the most common complication with peripheral infusion of this agent. Current practice guidelines for peripheral IV administration of phlebitis. The present study examines the incidence of phlebitis in a postoperative patient population given current dose recommendations. A total of 273 patient charts were reviewed. The incidence of phlebitis in patients given IV amiodarone (n = 36) was 13.9% (95% confidence interval, 2.6-25.2%; p = 0.001). Logistic regression analysis with backward elimination of other therapeutic risk factors suggests that the odds ratio for phlebitis using current dose regimens without IV filters is 19-fold greater than baseline risk in this population. Phlebitis remains a significant complication associated with peripheral infusion of amiodarone within recommended dosing limits.

  13. Study of response of radiation monitors for environmental dose equivalent measurements

    International Nuclear Information System (INIS)

    Souza, Macilene N.; Khoury, H.J.

    2005-01-01

    The environmental dose equivalent H * (10), is the magnitude recommended by ICRU 39 for environmental monitoring in fields of radiation of photons. Most of the equipment used for area monitoring, only quantifies the magnitudes exposure or dose not being designed to this new magnitude. In Brazil, particularly, is not yet regulated the use of H * (10). However, with the revision of the standard 3.01 it will necessary the use of monitors that allow the achievement of measures according to H * (10). The transition for using new magnitudes will be a slow process and the contribution that the laboratories of metrology of ionizing radiation in the country can give is, at first, promote and create the habit of using the unit Sievert (Sv) in the calibration of the instruments, and that is the unit recommended for H * (10). In a second step, the tests for determining the response of the instruments for H * (10) should be made and this is the harder step, taking into account the large number of area monitors around the country. These tests will provide information about the limitations of the instrument to the new magnitude, that is, the range where the instrument will have the best performance in quantification of new magnitude. This paper evaluates the performance for H * (10), with the variation of energy and angle of incidence of radiation, of three of the most used monitors in the country

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

    International Nuclear Information System (INIS)

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

    1993-01-01

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

  15. Recommendations to avoid gross errors of dose in radiotherapeutic treatments

    International Nuclear Information System (INIS)

    Souza, Cleber Nogueira de; Monti, Carlos Roberto; Sibata, Claudio Hissao

    2001-01-01

    Human mistakes are an important source of errors in radiotherapy and may occur at every step of the radiotherapy planning and treatment. To reduce this level of uncertainties, several specialized organizations have recommended a comprehensive quality assurance program. In Brazil, the requirement for these programs has been strongly stressed, and most radiotherapy services have pursued this goal regarding radiation units and dosimetry equipment, as well as the verification of the calculations of the patient's dose and the revision of the plan charts. As a contribution to the improvement of quality control, we present some recommendations to avoid failure of treatment due to error in the delivered dose, such as redundant check of the manual or computer calculations, weekly check of the total dose for each patient, and prevention of inadvertent access to any safety system of the equipment by any staff member that is only supposed to operate the machine. Moreover, the use of a computerized treatment record and verification system should be considered in order to eliminate errors due to incorrect selection of the treatment parameters, in a daily basis. We report four radioactive incidents with patient injuries occurred throughout the world and some gross errors of dose. (author)

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

    International Nuclear Information System (INIS)

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

    2009-01-01

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

  17. Comparison of Radiation Dose Rates with the Flux to Dose Conversion Factors Recommended in ICRP-74 and ICRP-116

    International Nuclear Information System (INIS)

    Jeong, Hae Sun; Kil, A Reum; Lee, Jo Eun; Jeong, Hyo Joon; Kim, Eun Han; Han, Moon Hee; Hwang, Won Tae

    2016-01-01

    The evaluation of radiation shielding has been performed for the design and maintenance of various facilities using radioactive sources such as nuclear fuel, accelerator, and radionuclide. The conversion of flux to dose mainly used in nuclear and radiation fields has been generally made with the dose coefficients presented in ICRP Publication 74 (ICRP- 74), which are produced based on ICRP Publication 60. On the other hand, ICRP Publication 116 (ICRP-116), which adopts the protection system of ICRP Publication 103, has recently been published and provides the dose conversion coefficients calculated with a variety of Monte Carlo codes. The coefficients have more than an update of those in ICRP-74, including new particle types and a greatly expanded energy range. In this study, a shielding evaluation of a specific container for neutron and gamma sources was performed with the MCNP6 code. The dose rates from neutron and gamma-ray sources were calculated using the MCNP6 codes, and these results were based on the flux to dose conversion factors recommended in ICRP-74 and ICRP-116. As a result, the dose rates evaluated with ICRP-74 were generally shown higher than those with ICRP-116. For neutrons, the difference is mainly occurred by the decrease of radiation weighting factors in a part of energy ranges in the ICRP-116 recommendations. For gamma-rays, the ICRP-74 recommendation applied with the kerma approximation leads to overestimated results than the other assessment

  18. Comparison of effective doses using tissue-weighting factors in the 1977, 1990, and 2007 recommendations of the ICRP

    International Nuclear Information System (INIS)

    Matsunaga, Yuta; Kawaguchi, Ai; Suzuki, Shoichi

    2013-01-01

    The International Commission on Radiological Protection (ICRP) has established recommended tissue-weighting factors. Although there have been international reports on effective doses using the factors listed in the 1977, 1990, and 2007 recommendations of the ICRP, there have been no papers in Japan. The aim of this study was to evaluate effective doses using the tissue-weighting factors listed in each recommendation of the ICRP under 2011 exposure conditions in Japan. We used a human body phantom to estimate patient exposure doses during chest, abdomen, lumbar spine (anteroposterior and lateral), and head radiographs. With thermoluminescence dosimeters placed at various positions on and in the phantom, radiation doses were determined. There was little change in the effective doses to the chest and head from each recommendation. However, the effective doses recommended in 1977 were 0.2 mSv to the abdomen, 0.1 mSv to the lumbar spine anteroposteriorally, and 0.1 mSv to the lumbar spine laterally; these values are lower than those recommended in 1990 and 2007, which were 0.5 mSv to the abdomen, 0.4 mSv to the lumbar spine anteroposteriorally, and 0.6 mSv to the lumbar spine laterally. We could evaluate the effective doses using each recommendation and 2011 exposure conditions in Japan. (author)

  19. Environmental impact statement analysis: dose methodology

    International Nuclear Information System (INIS)

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

    1981-01-01

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

  20. Characteristics of environmental gamma-rays and dose assessment

    International Nuclear Information System (INIS)

    Saito, Kimiaki; Moriuchi, Shigeru

    1986-01-01

    Environmental radioactivity has attracted much attention in terms of exposure to the population, although its exposure doses are minimal. This paper presents problems encountered in the assessment of exposure doses using model and monitoring systems, focusing on the characteristics, such as energy distribution, direction distribution, and site, of environmental gamma-rays. The assessment of outdoor and indoor exposure doses of natural gamma-rays is discussed in relation to the shielding effect of the human body. In the assessment of artificial gamma-rays, calculation of exposure doses using build-up factor, the shielding effect of the human body, and energy dependency of the measuring instrument are covered. A continuing elucidation about uncertainties in dose assessment is emphasized. (Namekawa, K.)

  1. Evaluation of effective dose equivalent from environmental gamma rays

    International Nuclear Information System (INIS)

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

    1991-01-01

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

  2. Survey of environmental radiation dose rates in Tokushima prefecture

    International Nuclear Information System (INIS)

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

    2004-01-01

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

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

    Directory of Open Access Journals (Sweden)

    Andrew F Brouwer

    2017-04-01

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

  4. Literature-based recommendations for treatment planning and execution in high-dose radiotherapy for lung cancer

    International Nuclear Information System (INIS)

    Senan, Suresh; De Ruysscher, Dirk; Giraud, Philippe; Mirimanoff, Rene; Budach, Volker

    2004-01-01

    Background and purpose: To review the literature on techniques used in high-dose radiotherapy of lung cancer in order to develop recommendations for clinical practice and for use in research protocols. Patients and methods: A literature search was performed for articles and abstracts that were considered both clinically relevant and practical to use. The relevant information was arbitrarily categorized under the following headings: patient positioning, CT scanning, incorporating tumour mobility, definition of target volumes, radiotherapy planning, treatment delivery, and scoring of response and toxicity. Results: Recommendations were made for each of the above steps from the published literature. Although most of the recommended techniques have yet to be evaluated in multicenter clinical trials, their use in high-dose radiotherapy to the thorax appears to be rational on the basis of current evidence. Conclusions: Recommendations for the clinical implementation of high-dose conformal radiotherapy for lung tumours were identified in the literature. Procedures that are still considered to be investigational were also highlighted

  5. 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.

  6. Assessment of dose homogeneity in conformal interstitial breast brachytherapy with special respect to ICRU recommendations

    Directory of Open Access Journals (Sweden)

    Tibor Major

    2011-09-01

    Full Text Available Purpose: To present the results of dose homogeneity analysis for breast cancer patients treated with image-basedconformal interstitial brachytherapy, and to investigate the usefulness of the ICRU recommendations. Material and methods: Treatment plans of forty-nine patients who underwent partial breast irradiation with interstitialbrachytherapy were analyzed. Quantitative parameters were used to characterize dose homogeneity. Dose nonuniformityratio (DNR, dose homogeneity index (DHI, uniformity index (UI and quality index (QI were calculated.Furthermore, parameters recommended by the ICRU 58 such as minimum target dose (MTD, mean central dose (MCD,high dose volume, low dose volume and the spread between local minimum doses were determined. Correlationsbetween the calculated homogeneity parameters and usefulness of the ICRU parameters in image-based brachytherapywere investigated. Results: Catheters with mean number of 15 (range: 6-25 were implanted in median 4 (range: 3-6 planes. The volu -me of the PTV ranged from 15.5 cm3 to 176 cm3. The mean DNR was 0.32, the DHI 0.66, the UI 1.49 and the QI 1.94. Relatedto the prescribed dose, the MTD was 69% and the MCD 135%. The mean high dose volume was 8.1 cm3 (10%, whilethe low dose volume was 63.8 cm3 (96%. The spread between minimum doses in central plane ranged from –14% to+20%. Good correlation was found between the DNR and the DHI (R2 = 0.7874, and the DNR correlated well with theUI (R2 = 0.7615 also. No correlation was found between the ICRU parameters and any other volumetric parameters. Conclusions: To characterize the dose uniformity in high-dose rate breast implants, DVH-related homogeneityparameters representing the full 3D dose distributions are mandatory to be used. In many respects the current re commendationsof the ICRU Report 58 are already outdated, and it is well-timed to set up new recommendations, whichare more feasible for image-guided conformal interstitial brachytherapy.

  7. The American Brachytherapy Society recommendations for low-dose-rate brachytherapy for carcinoma of the cervix

    International Nuclear Information System (INIS)

    Nag, Subir; Chao, Clifford; Erickson, Beth; Fowler, Jeffery; Gupta, Nilendu; Martinez, Alvaro; Thomadsen, Bruce

    2002-01-01

    Purpose: This report presents guidelines for using low-dose-rate (LDR) brachytherapy in the management of patients with cervical cancer. Methods: Members of the American Brachytherapy Society (ABS) with expertise in LDR brachytherapy for cervical cancer performed a literature review, supplemented by their clinical experience, to formulate guidelines for LDR brachytherapy of cervical cancer. Results: The ABS strongly recommends that radiation treatment for cervical carcinoma (with or without chemotherapy) should include brachytherapy as a component. Precise applicator placement is essential for improved local control and reduced morbidity. The outcome of brachytherapy depends, in part, on the skill of the brachytherapist. Doses given by external beam radiotherapy and brachytherapy depend upon the initial volume of disease, the ability to displace the bladder and rectum, the degree of tumor regression during pelvic irradiation, and institutional practice. The ABS recognizes that intracavitary brachytherapy is the standard technique for brachytherapy for cervical carcinoma. Interstitial brachytherapy should be considered for patients with disease that cannot be optimally encompassed by intracavitary brachytherapy. The ABS recommends completion of treatment within 8 weeks, when possible. Prolonging total treatment duration can adversely affect local control and survival. Recommendations are made for definitive and postoperative therapy after hysterectomy. Although recognizing that many efficacious LDR dose schedules exist, the ABS presents suggested dose and fractionation schemes for combining external beam radiotherapy with LDR brachytherapy for each stage of disease. The dose prescription point (point A) is defined for intracavitary insertions. Dose rates of 0.50 to 0.65 Gy/h are suggested for intracavitary brachytherapy. Dose rates of 0.50 to 0.70 Gy/h to the periphery of the implant are suggested for interstitial implant. Use of differential source activity or

  8. Overview of the Hanford Environmental Dose Reconstruction Project

    International Nuclear Information System (INIS)

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

    1992-04-01

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

  9. Evaluating the environmental impacts of dietary recommendations.

    Science.gov (United States)

    Behrens, Paul; Kiefte-de Jong, Jessica C; Bosker, Thijs; Rodrigues, João F D; de Koning, Arjan; Tukker, Arnold

    2017-12-19

    Dietary choices drive both health and environmental outcomes. Information on diets come from many sources, with nationally recommended diets (NRDs) by governmental or similar advisory bodies the most authoritative. Little or no attention is placed on the environmental impacts within NRDs. Here we quantify the impact of nation-specific NRDs, compared with an average diet in 37 nations, representing 64% of global population. We focus on greenhouse gases (GHGs), eutrophication, and land use because these have impacts reaching or exceeding planetary boundaries. We show that compared with average diets, NRDs in high-income nations are associated with reductions in GHG, eutrophication, and land use from 13.0 to 24.8%, 9.8 to 21.3%, and 5.7 to 17.6%, respectively. In upper-middle-income nations, NRDs are associated with slight decrease in impacts of 0.8-12.2%, 7.7-19.4%, and 7.2-18.6%. In poorer middle-income nations, impacts increase by 12.4-17.0%, 24.5-31.9%, and 8.8-14.8%. The reduced environmental impact in high-income countries is driven by reductions in calories (∼54% of effect) and a change in composition (∼46%). The increased environmental impacts of NRDs in low- and middle-income nations are associated with increased intake in animal products. Uniform adoption of NRDs across these nations would result in reductions of 0.19-0.53 Gt CO 2 eq⋅a -1 , 4.32-10.6 Gt [Formula: see text] eq⋅a -1 , and 1.5-2.8 million km 2 , while providing the health cobenefits of adopting an NRD. As a small number of dietary guidelines are beginning to incorporate more general environmental concerns, we anticipate that this work will provide a standardized baseline for future work to optimize recommended diets further. Copyright © 2017 the Author(s). Published by PNAS.

  10. Real-life effectiveness of omalizumab in severe allergic asthma above the recommended dosing range criteria.

    Science.gov (United States)

    Hew, M; Gillman, A; Sutherland, M; Wark, P; Bowden, J; Guo, M; Reddel, H K; Jenkins, C; Marks, G B; Thien, F; Rimmer, J; Katsoulotos, G P; Cook, M; Yang, I; Katelaris, C; Bowler, S; Langton, D; Wright, C; Bint, M; Yozghatlian, V; Burgess, S; Sivakumaran, P; Yan, K Y; Kritikos, V; Peters, M; Baraket, M; Aminazad, A; Robinson, P; Jaffe, A; Powell, H; Upham, J W; McDonald, V M; Gibson, P G

    2016-11-01

    Omalizumab (Xolair) dosing in severe allergic asthma is based on serum IgE and bodyweight. In Australia, patients eligible for omalizumab but exceeding recommended ranges for IgE (30-1500 IU/mL) and bodyweight (30-150 kg) may still receive a ceiling dose of 750 mg/4 weeks. About 62% of patients receiving government-subsidized omalizumab are enrolled in the Australian Xolair Registry (AXR). To determine whether AXR participants above the recommended dosing ranges benefit from omalizumab and to compare their response to within-range participants. Data were stratified according to dose range status (above-range or within-range). Further sub-analyses were conducted according to the reason for being above the dosing range (IgE only vs. IgE and weight). Data for 179 participants were analysed. About 55 (31%) were above recommended dosing criteria; other characteristics were similar to within-range participants. Above-range participants had higher baseline IgE [812 (IQR 632, 1747) IU/mL vs. 209 (IQR 134, 306) IU/mL] and received higher doses of omalizumab [750 (IQR 650, 750) mg] compared to within-range participants [450 (IQR, 300, 600) mg]. At 6 months, improvements in Juniper 5-item Asthma Control Questionnaire (ACQ-5, 3.61 down to 2.01 for above-range, 3.47 down to 1.93 for within-range, P omalizumab have significantly improved symptom control, quality of life and lung function to a similar degree to within-range participants, achieved without dose escalation above 750 mg. © 2016 John Wiley & Sons Ltd.

  11. Skin dose from distributed radioactive sources and hot particles - Regulations and recommendations

    International Nuclear Information System (INIS)

    Porter, S.W.

    1991-01-01

    The issues concerning Beta Dosimetry, Hot Particle Dosimetry, and associated dose to skin have been highlighted since the 1979 TMI-2 accident report of the Presidential Commission. The conclusions drawn from the DOE/EML International Beta Dosimetry Symposium of 1983 are still valid. The questions of location(s) of the radiosensitive layer of human skin, the most valid method of skin dose measurement and interpretation of associated radiobiological data are still lingering. The need for improving beta calculation standards and procedures are more evident now than in 1983. This paper will discuss the newest ICRP and NCRP recommendations, as well as the regulations and guidelines from the NRC. I would expect that the draft recommendations published in this paper will be considerably changed by the time of the January, 1991 presentation of this paper

  12. Recommendations to the Technical Steering Panel regarding approach for estimating individual radiation doses resulting from releases of radionuclides to the Columbia River

    International Nuclear Information System (INIS)

    Napier, B.A.; Brothers, A.J.

    1992-07-01

    At the direction of the Technical Steering Panel (TSP) of the Hanford Environmental Dose Reconstruction (HEDR) Project, Battelle staff have reviewed and analyzed available data regarding possible historical radiation doses to individuals resulting from radionuclide releases to the Columbia River. The objective of this review was to recommend to the TSP the spatial and temporal scope and level of effort on Columbia River work to most effectively extend work performed in Phase I of the project (PNL 1991a, PNL 1991b) to meet the project objectives. A number of options were analyzed. Four stretches of the Columbia River and adjacent Pacific coastal waters were defined and investigated for four time periods. Radiation doses arising from ten potentially major exposure pathways were evaluated for each of the time/location combinations, and several alternative methods were defined for estimating the doses from each pathway. Preliminary cost estimates were also developed for implementing dose estimation activities for each of the possible combinations

  13. Status report : Terra Nova project environmental assessment panel : recommendations

    International Nuclear Information System (INIS)

    2002-01-01

    An application to the Canada-Newfoundland Offshore Petroleum Board (CNOPB) was submitted by Petro-Canada on August 5, 1996, notifying of its intent to develop the petroleum resources located at the Terra Nova field. The provincial and federal governments jointly appointed the Terra Nova Project Environmental Panel, and the board of the CNOPB referred to it the application documents for review. The environmental effects, considerations of human safety incorporated into the design and operation of the Project, the general approach to the development and exploitation of the petroleum resources, and the employment and industrial benefits expected to be derived from the Project were the issues under review by the Panel. On April 22, 1997, public hearings into the review began, and the final report was submitted to governments and the Board in August 1997. The report included 75 recommendations. The Project was approved in Decision 97.02 in December 1997, and the Board dealt with each of the recommendations. The respective positions of the Governments of Canada and Newfoundland and Labrador with regard to the recommendations that fell outside the jurisdiction of the Board were made public. A status report on every one of the 75 recommendations is provided in the present report. The recommendation is repeated, the verbatim response taken from Decision 97.02 included, followed by the status of the response. The production operations phase of the Project accounts for approximately 65 per cent of the recommendations. January 20, 2002 was the date the Project was begun

  14. Optimization of radiological protection and dose constraints in the new draft ICRP Recommendations 2006

    International Nuclear Information System (INIS)

    Klener, V.

    2007-01-01

    The overall concept of the new ICRP Recommendations 2006 is analyzed, the concept of dose constraints as a basic tool of radiological protection management is described, arguments and criticisms against the current proposal are cited and points of dispute highlighted, and perspectives of the Recommendations are assessed. (author)

  15. Acute liver failure after recommended doses of acetaminophen in patients with myopathies

    NARCIS (Netherlands)

    I. Ceelie (Ilse); L.P. James (Laura); V.M.G.J. Gijsen (Violette); R.A.A. Mathôt (Ron); S. Ito (Shinya); C.D. Tesselaar (Coranne); D. Tibboel (Dick); G. Koren (Gideon); S.N. de Wildt (Saskia)

    2011-01-01

    textabstractObjective: To determine the likelihood that recommended doses of acetaminophen are associated with acute liver failure in patients with myopathies. Design: Retrospective analysis. Setting: Level III pediatric intensive care unit. Patients: Two pediatric patients with myopathies and acute

  16. Acute liver failure after recommended doses of acetaminophen in patients with myopathies

    NARCIS (Netherlands)

    Ceelie, Ilse; James, Laura P.; Gijsen, Violette; Mathot, Ron A. A.; Ito, Shinya; Tesselaar, Coranne D.; Tibboel, Dick; Koren, Gideon; de Wildt, Saskia N.

    2011-01-01

    To determine the likelihood that recommended doses of acetaminophen are associated with acute liver failure in patients with myopathies. Retrospective analysis. Level III pediatric intensive care unit. Two pediatric patients with myopathies and acute liver failure. CLINICAL INVESTIGATIONS: We

  17. Empiric guideline-recommended weight-based vancomycin dosing and mortality in methicillin-resistant Staphylococcus aureus bacteremia: a retrospective cohort study

    Directory of Open Access Journals (Sweden)

    Hall Ronald G

    2012-04-01

    Full Text Available Abstract Background No studies have evaluated the effect of guideline-recommended weight-based dosing on in-hospital mortality of patients with methicillin-resistant Staphylococcus aureus bacteremia. Methods This was a multicenter, retrospective, cohort study of patients with methicillin-resistant Staphylococcus aureus bacteremia receiving at least 48 hours of empiric vancomycin therapy between 01/07/2002 and 30/06/2008. We compared in-hospital mortality for patients treated empirically with weight-based, guideline-recommended vancomycin doses (at least 15 mg/kg/dose to those treated with less than 15 mg/kg/dose. We used a general linear mixed multivariable model analysis with variables identified a priori through a conceptual framework based on the literature. Results A total of 337 patients who were admitted to the three hospitals were included in the cohort. One-third of patients received vancomycin empirically at the guideline-recommended dose. Guideline-recommended dosing was not associated with in-hospital mortality in the univariable (16% vs. 13%, OR 1.26 [95%CI 0.67-2.39] or multivariable (OR 0.71, 95%CI 0.33-1.55 analysis. Independent predictors of in-hospital mortality were ICU admission, Pitt bacteremia score of 4 or greater, age 53 years or greater, and nephrotoxicity. Conclusions Empiric use of weight-based, guideline-recommended empiric vancomycin dosing was not associated with reduced mortality in this multicenter study.

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

    International Nuclear Information System (INIS)

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

    2009-01-01

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

  19. Environmental monitoring system with TLD

    International Nuclear Information System (INIS)

    Aguerre, L.; Carelli, J.; Gregori, B.

    2006-01-01

    Presently work the methodology used by the Laboratory of Thermoluminescent Dosimetry (TLD) of the Nuclear Regulatory Authority (RNA) to gauge it system of environmental monitoring in function of the media absorbed dose rate in free air and the environmental dose equivalent, H * (10), according to the recommendation ICRU Report 47 is described. It was studied the response of the environmental dosemeter (DA) in fields of photonic radiation of energies W60, Wl 10, W200 and 137 Cs. The irradiations were carried out following the recommendations of the standard ISO:4037. It was analyzed the response in the DA of the detectors LiF: Mg, Ti and CaF 2 : Dy for the different radiation qualities and the relative response at 137 Cs of both. The methodology used in the evaluation of the dose includes: the correction of the readings of both detectors by fading, gotten experimentally, the witness of transfers, the energy answer and the value of the zero. The dose is calculated applying the average pondered in uncertainty of the dose obtained for each type of detector. Its were analyzed and calculated the uncertainties that affect to the measurement following the recommendation of the Argentine standard IRAM 35050. The detection limit of the absorbed dose rate in free air of this system it is 3.5 n Gy/h for a period of sampling of 3 months. With this detection limit environmental dose equivalent rates of the order of 70 n Sv/h are measured with an expanded uncertainty of the order of 10% with a cover factor k = 2. (Author)

  20. American brachytherapy society recommends no change for prostate permanent implant dose prescriptions using iodine-125 or palladium-103

    International Nuclear Information System (INIS)

    Rivard, M.J.; Butler, W.M.; Merrick, G.S.; Devlin, P.M.; Hayes, J.K.; Hearn, R.A.; Lief, E.P.; Meigooni, A.S.; Williamson, J.F.

    2008-01-01

    Purpose - In 2004, the American Association of Physicists in Medicine (AAPM) issued a report outlining recommended 125 I and 103 Pd datasets for consistency in calculating brachytherapy dose distributions. In 2005, to aid evaluating the clinical impact of implementing these datasets, the AAPM assessed the historical dependence of how prescribed doses differed from administered doses for 125 I and 103 Pd for permanent implantation of the prostate. Consequently, the American Brachytherapy Society (ABS) considered the nature of these changes towards issuing recommended dose prescriptions for 125 I and 103 Pd interstitial brachytherapy implants for mono-therapy and standard boosts. Methods and materials - An investigation was performed of the 2005 AAPM analysis to determine changes in administered dose while affixing prescribed dose using 2004 AAPM 125 I and 103 Pd brachytherapy dosimetry datasets for prostate implants. For 125 I and 103 Pd, administered dose would change by +1.4% and +4.2%, respectively. The biological and societal impact of changing prescribed dose was considered. Results - Based on the need for clinical constancy and in recognition of overall uncertainties, the ABS recommends immediate implementation of the 2004 AAPM consensus brachytherapy dosimetry datasets and no changes to 125 I and 103 Pd dose prescriptions at this time. Conclusions - Radiation oncologists should continue to prescribe mono-therapy doses of 145 Gy and 125 Gy for 125 I and 105 Pd, respectively, and standard boost doses of 100-110 Gy and 90-100 Gy for 125 I and 103 Pd, respectively. (authors)

  1. Statistical analysis of environmental dose data for Trombay environment

    International Nuclear Information System (INIS)

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

    1993-01-01

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

  2. New recommendations for dose equivalent

    International Nuclear Information System (INIS)

    Bengtsson, G.

    1985-01-01

    In its report 39, the International Commission on Radiation Units and Measurements (ICRU), has defined four new quantities for the determination of dose equivalents from external sources: the ambient dose equivalent, the directional dose equivalent, the individual dose equivalent, penetrating and the individual dose equivalent, superficial. The rationale behind these concepts and their practical application are discussed. Reference is made to numerical values of these quantities which will be the subject of a coming publication from the International Commission on Radiological Protection, ICRP. (Author)

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

    International Nuclear Information System (INIS)

    Nagaoka, Kazunori; Honda, Kouichirou; Miyano, Keiji

    1996-01-01

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

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

    International Nuclear Information System (INIS)

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

    1990-01-01

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

  5. Can we safely administer the recommended dose of phenobarbital in very low birth weight infants?

    Science.gov (United States)

    Oztekin, Osman; Kalay, Salih; Tezel, Gonul; Akcakus, Mustafa; Oygur, Nihal

    2013-08-01

    We investigated whether the recommended phenobarbital loading dose of 15-20 mg/kg with maintenance of 3-4 mg/kg/day can safely be administered to very low birth weight preterm newborns with seizures. Twenty-four convulsive preterms of Phenobarbital was administered intravenously with a loading dose of 15 mg/kg in approximately 10-15 min. After 24 h, the maintenance dose of 3 mg/kg/day was administered as a single injection. Blood samples were obtained 2, 24, 48, 72, and 96 h after the phenobarbital loading dose was administered, immediately before the next phenobarbital dose was injected. None of the cases had plasma phenobarbital concentrations above the therapeutic upper limit of 40 μg/mL on the 2nd hour; one case (4.7%), on the 24th; 11 cases (45.8%), on the 48th; 15 cases (62.5%), on the 72nd; and 17 cases (70.8%), on the 96th hour. A negative correlation was detected between the serum concentrations of phenobarbital and gestational age on the 72th (p, 0.036; r, -0.608) and 96th hour (p, 0.043; r, -0.769). We suggest that particular attention should be done while administering phenobarbital in preterms, as blood levels of phenobarbital are higher than the reference ranges that those are often reached with the recommended doses in these groups of babies.

  6. Radiological environmental dose assessment methods and compliance dose results for 2015 operations at the Savannah River Site

    Energy Technology Data Exchange (ETDEWEB)

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

    2016-09-01

    This report presents the environmental dose assessment methods and the estimated potential doses to the offsite public from 2015 Savannah River Site (SRS) atmospheric and liquid radioactive releases. Also documented are potential doses from special-case exposure scenarios - such as the consumption of deer meat, fish, and goat milk.

  7. Radiological environmental dose assessment methods and compliance dose results for 2015 operations at the Savannah River Site

    International Nuclear Information System (INIS)

    Jannik, G. T.; Dixon, K. L.

    2016-01-01

    This report presents the environmental dose assessment methods and the estimated potential doses to the offsite public from 2015 Savannah River Site (SRS) atmospheric and liquid radioactive releases. Also documented are potential doses from special-case exposure scenarios - such as the consumption of deer meat, fish, and goat milk.

  8. ICRP recommendations on 'managing patient dose in digital radiology'

    International Nuclear Information System (INIS)

    Vano, E.

    2005-01-01

    The International Commission on Radiological Protection (ICRP) approved the publication of a document on 'Managing patient dose in digital radiology' in 2003. The paper describes the content of the report and some of its key points, together with the formal recommendations of the Commission on this topic. With digital techniques exists not only the potential to improve the practice of radiology but also the risk to overuse radiation. The main advantages of digital imaging: wide dynamic range, post-processing, multiple viewing options, electronic transfer and archiving possibilities are clear but overexposures can occur without an adverse impact on image quality. It is expected that the ICRP report helps to profit from the benefits of this important technological advance in medical imaging with the best management of radiation doses to the patients. It is also expected to promote training actions before the digital techniques are introduced in the radiology departments and to foster the industry to offer enough technical and dosimetric information to radiologists, radiographers and medical physicists to help in the optimisation of the imaging. (authors)

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

    International Nuclear Information System (INIS)

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

    2008-01-01

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

  10. Radiological assessment. A textbook on environmental dose analysis

    Energy Technology Data Exchange (ETDEWEB)

    Till, J.E.; Meyer, H.R. (eds.)

    1983-09-01

    Radiological assessment is the quantitative process of estimating the consequences to humans resulting from the release of radionuclides to the biosphere. It is a multidisciplinary subject requiring the expertise of a number of individuals in order to predict source terms, describe environmental transport, calculate internal and external dose, and extrapolate dose to health effects. Up to this time there has been available no comprehensive book describing, on a uniform and comprehensive level, the techniques and models used in radiological assessment. Radiological Assessment is based on material presented at the 1980 Health Physics Society Summer School held in Seattle, Washington. The material has been expanded and edited to make it comprehensive in scope and useful as a text. Topics covered include (1) source terms for nuclear facilities and Medical and Industrial sites; (2) transport of radionuclides in the atmosphere; (3) transport of radionuclides in surface waters; (4) transport of radionuclides in groundwater; (5) terrestrial and aquatic food chain pathways; (6) reference man; a system for internal dose calculations; (7) internal dosimetry; (8) external dosimetry; (9) models for special-case radionuclides; (10) calculation of health effects in irradiated populations; (11) evaluation of uncertainties in environmental radiological assessment models; (12) regulatory standards for environmental releases of radionuclides; (13) development of computer codes for radiological assessment; and (14) assessment of accidental releases of radionuclides.

  11. Radiological assessment. A textbook on environmental dose analysis

    International Nuclear Information System (INIS)

    Till, J.E.; Meyer, H.R.

    1983-09-01

    Radiological assessment is the quantitative process of estimating the consequences to humans resulting from the release of radionuclides to the biosphere. It is a multidisciplinary subject requiring the expertise of a number of individuals in order to predict source terms, describe environmental transport, calculate internal and external dose, and extrapolate dose to health effects. Up to this time there has been available no comprehensive book describing, on a uniform and comprehensive level, the techniques and models used in radiological assessment. Radiological Assessment is based on material presented at the 1980 Health Physics Society Summer School held in Seattle, Washington. The material has been expanded and edited to make it comprehensive in scope and useful as a text. Topics covered include (1) source terms for nuclear facilities and Medical and Industrial sites; (2) transport of radionuclides in the atmosphere; (3) transport of radionuclides in surface waters; (4) transport of radionuclides in groundwater; (5) terrestrial and aquatic food chain pathways; (6) reference man; a system for internal dose calculations; (7) internal dosimetry; (8) external dosimetry; (9) models for special-case radionuclides; (10) calculation of health effects in irradiated populations; (11) evaluation of uncertainties in environmental radiological assessment models; (12) regulatory standards for environmental releases of radionuclides; (13) development of computer codes for radiological assessment; and (14) assessment of accidental releases of radionuclides

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

    International Nuclear Information System (INIS)

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

    1991-01-01

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

  13. Determination of environmental radioactivity for dose assessment

    International Nuclear Information System (INIS)

    Nakoaka, A.; Fukushima, M.; Takagi, S.

    1980-01-01

    A method was devised to determine detection limits for radioactivity in environmental samples. The method is based on the 5 mrem/yr whole-body dose objective established by the Japan Atomic Enerty Commission and is valid for assessing the internal dose from radionuclides in the environment around a nuclear facility. Eleven samples and 15 radionuclides were considered. Internal dose was assumed to be one-half of the total dose (5 mrem/yr) and was assessed using the critical pathway method. Needed detection limits (NDLs) were established to confirm the dose of 5 mrem/yr when there was more than one radionuclide per sample. The NDLs for γ-emitters were 10 -5 pCi/l. for air; 10 -3 pCi/l. for seawater; 10 -1 pCi/l. for drinking water; 10 0 pCi/kg for vegetables and fish; 10 0 pCi/l. for milk; and 10 1 pCi/kg for molluscs, crustaceans, seaweeds, soil and submarine sediments. The NDLs for β-emitters were 1-1/100 of those for γ-emitters. (author)

  14. Dose Rate of Environmental Gamma Radiation in Java Island

    International Nuclear Information System (INIS)

    Gatot Suhariyono; Buchori; Dadong Iskandar

    2007-01-01

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

  15. Dose assessment in environmental radiological protection: State of the art and perspectives.

    Science.gov (United States)

    Stark, Karolina; Goméz-Ros, José M; Vives I Batlle, Jordi; Lindbo Hansen, Elisabeth; Beaugelin-Seiller, Karine; Kapustka, Lawrence A; Wood, Michael D; Bradshaw, Clare; Real, Almudena; McGuire, Corynne; Hinton, Thomas G

    2017-09-01

    Exposure to radiation is a potential hazard to humans and the environment. The Fukushima accident reminded the world of the importance of a reliable risk management system that incorporates the dose received from radiation exposures. The dose to humans from exposure to radiation can be quantified using a well-defined system; its environmental equivalent, however, is still in a developmental state. Additionally, the results of several papers published over the last decade have been criticized because of poor dosimetry. Therefore, a workshop on environmental dosimetry was organized by the STAR (Strategy for Allied Radioecology) Network of Excellence to review the state of the art in environmental dosimetry and prioritize areas of methodological and guidance development. Herein, we report the key findings from that international workshop, summarise parameters that affect the dose animals and plants receive when exposed to radiation, and identify further research needs. Current dosimetry practices for determining environmental protection are based on simple screening dose assessments using knowledge of fundamental radiation physics, source-target geometry relationships, the influence of organism shape and size, and knowledge of how radionuclide distributions in the body and in the soil profile alter dose. In screening model calculations that estimate whole-body dose to biota the shapes of organisms are simply represented as ellipsoids, while recently developed complex voxel phantom models allow organ-specific dose estimates. We identified several research and guidance development priorities for dosimetry. For external exposures, the uncertainty in dose estimates due to spatially heterogeneous distributions of radionuclide contamination is currently being evaluated. Guidance is needed on the level of dosimetry that is required when screening benchmarks are exceeded and how to report exposure in dose-effect studies, including quantification of uncertainties. Further

  16. Does intravenous induction dosing among patients undergoing gastrointestinal surgical procedures follow current recommendations: a study of contemporary practice.

    Science.gov (United States)

    Akhtar, Shamsuddin; Liu, Jia; Heng, Joseph; Dai, Feng; Schonberger, Robert B; Burg, Matthew M

    2016-09-01

    It is recommended to correct intravenous induction doses by up to 50% for patients older than 65 years. The objectives were to determine (a) the degree to which anesthesia providers correct induction doses for age and (b) additionally adjust for American Society of Anesthesiologists physical status (ASA-PS) class (severity of illness) and (c) whether postinduction hypotension is more common among patients aged >65. Retrospective chart review. Academic medical center. A total of 1869 adult patients receiving general anesthesia for GI surgical procedures from February 2013 to January 2014. Patients were divided into 3 age groups (age 80, which was still in less than the recommendations. An inverse relationship was observed between propofol dosing and ASA-PS class, but no consistent relationship was noted for fentanyl and midazolam. There were a significantly larger drop in mean arterial pressure and a greater likelihood of hypotension following induction in patients aged 65-79 years and >80 years as compared with those aged <65 years. This study shows that the administered dose of anesthetic induction agents is significantly higher than that recommended for patients older than 65 years. This failure to age-adjust dose may contribute to hypotensive episodes. Copyright © 2016 Elsevier Inc. All rights reserved.

  17. Recommendations related to the strategic environmental assessment. Methodological note

    International Nuclear Information System (INIS)

    Le Bris, Charlotte; Brivadier, Isabelle; Fournie, Sebastien; Godart, Angelique; Hubert, Severine; Ille, Yann-Mikiel; Le Mitouard, Eric; Phelep, Michele; Delduc, Paul; Poitevin, Florent; Lemaitre, Valery; Bataille, Tristan; Noulin, Alice; Fevre, Cecile; Kervella, Frederic; Orefici, Christine; Rambaud, Lucile; Antoine, Stephanie; Wormser, Veronique; Garrigou, Olivier; Vinay, Catherine; Cretin, Benedicte; Le Saout, Michaele; Pagnucco, Fabrice; Meinier, Yves; Nicolas, Veronique; Thiolliere, Blandine; Guilbert, Sebastien; Billant, Claude; Saingenest, Patrick

    2015-05-01

    This methodological note aims at giving commissioners and project managers of plans, schemes and programmes or other planning documents related to strategic environmental assessment a comprehensive vision of the approach to be adopted, as well as useful advices and operational recommendations. The first part recalls the main principles of environmental assessment, addresses general issues of organisation of the approach, and clarifies its articulation with the plan/scheme/programme elaboration or other approaches such as the assessment of incidences on the Natura 2000 network. The second part addresses the different chapters which are foreseen by the regulation for the environmental report. Some sheets are proposed on SDAGEs (Water Development and Management Master Plans) and PGIRs (flood risk management plans), on SRCs (quarry regional plan) and SAGEs (Water Development and Management Scheme)

  18. The ICRP 2007 recommendations

    International Nuclear Information System (INIS)

    Streffer, C.

    2007-01-01

    The last comprehensive International Commission on Radiological Protection (ICRP) recommendations have been published in 1991(1). Since that time new data in physics and biology that are relevant for radiological protection have appeared in the scientific literature. Also, the general thinking about safety standards at the workplace as well as for the protection of the public has developed. Thus, a review of the recommendations is needed. However, as the present standards have worked well, these new recommendations should build on the present ones. Only a process of further development should take place allowing for the following key points: - new biological and physical information and trends in the setting of safety standards; - improvement in the presentation of the recommendations; as much stability in the recommendations as is consistent with the new information and environmental aspects will be included. The fundamental principles of radiological protection will remain the same as they have been described in ICRP publication 60(1): Justification: Actions involving new exposures or changes in exposures of individuals have to be justified in advance. A positive net benefit must result. Optimisation: Exposures should be as low as reasonably achievable and should be optimised in relation to with dose constraints. Dose limits: The values will not to be changed from Publication 60. Dose constraints: Development of the concept proposed in Publication 60 will be explained. The ICRP Committees have prepared foundation documents in the fields for which they are responsible and their members have the corresponding expertise. These foundation documents will support the decisions and explain the various statements of the Main Commission in a broader sense. Some of them will be published as Annexes to the recommendations (Annex A: Biological and Epidemiological Information on Health Risks Attributable to Ionising Radiation; Annex B: Quantities used in Radiological

  19. The ICRP 2007 recommendations

    Energy Technology Data Exchange (ETDEWEB)

    Streffer, C. [Chairman of ICRP Committee 2, Institute of Science and Ethics, University Duisburg-Essen, 45117 Essen (Germany)

    2007-07-01

    The last comprehensive International Commission on Radiological Protection (ICRP) recommendations have been published in 1991(1). Since that time new data in physics and biology that are relevant for radiological protection have appeared in the scientific literature. Also, the general thinking about safety standards at the workplace as well as for the protection of the public has developed. Thus, a review of the recommendations is needed. However, as the present standards have worked well, these new recommendations should build on the present ones. Only a process of further development should take place allowing for the following key points: - new biological and physical information and trends in the setting of safety standards; - improvement in the presentation of the recommendations; as much stability in the recommendations as is consistent with the new information and environmental aspects will be included. The fundamental principles of radiological protection will remain the same as they have been described in ICRP publication 60(1): Justification: Actions involving new exposures or changes in exposures of individuals have to be justified in advance. A positive net benefit must result. Optimisation: Exposures should be as low as reasonably achievable and should be optimised in relation to with dose constraints. Dose limits: The values will not to be changed from Publication 60. Dose constraints: Development of the concept proposed in Publication 60 will be explained. The ICRP Committees have prepared foundation documents in the fields for which they are responsible and their members have the corresponding expertise. These foundation documents will support the decisions and explain the various statements of the Main Commission in a broader sense. Some of them will be published as Annexes to the recommendations (Annex A: Biological and Epidemiological Information on Health Risks Attributable to Ionising Radiation; Annex B: Quantities used in Radiological

  20. Stake holders' views on the implications of the new ICRP recommendations: an environmental perspective

    International Nuclear Information System (INIS)

    Carroll, S.

    2003-01-01

    The development of the new ICRP Recommendations are of significant interest to environmental organisations. There are several issues of particular interest: 1. whether the 'approach and the numbers are right'? in the general recommendations; 2. to what extent the understandings being developed for both human and non-human species will effectively address concerns regarding protecting the health of people and the environment; and 3. to what extent these new recommendations will inform the broader regulatory and policy debates, in particular those concerning the uses of nuclear power, fuel cycle developments and radioactive waste management practices. This presentation will explore various aspects of these issues from the perspectives of environmental organisations. (author)

  1. Recommendations to the Technical Steering Panel regarding approach for estimating individual radiation doses resulting from releases of radionuclides to the Columbia River

    International Nuclear Information System (INIS)

    Brothers, A.J.; Napier, B.A.

    1992-08-01

    At the direction of the Technical Steering Panel (TSP) of the Hanford Environmental Dose Reconstruction (HEDR) Project, Battelle staff have reviewed and analyzed available data regarding possible historical radiation doses to individuals resulting from radionuclide releases to the Columbia River. The objective of this review was to recommend to the TSP the spatial and temporal scope and level of effort on Columbia River work to most effectively extend work performed in Phase I of the project to meet the project objectives. Four stretches of the Columbia River and adjacent Pacific coastal waters were defined and investigated for four time periods. Radiation doses arising from ten potentially major exposure pathways were evaluated for each of the time/location combinations, and several alternative methods were defined for estimating the doses from each pathway. Preliminary cost estimates were also developed for implementing dose estimation activities for each of the possible combinations. The number of combinations of the alternatives is obviously very large. A ''value of information'' (VOI) decision analysis tool was developed and applied to the problem of selecting a few ''optimal'' sets of alternatives to consider. This VOI analysis relies on both available data and the judgement of technical experts. Input data and the algorithms used are described

  2. Recommendations to reduce extremity and eye lens doses in interventional radiology and cardiology

    International Nuclear Information System (INIS)

    Carinou, E.; Brodecki, M.; Domienik, J.; Donadille, L.; Koukorava, C.; Krim, S.; Nikodemová, D.; Ruiz-Lopez, N.; Sans-Merce, M.; Struelens, L.; Vanhavere, F.

    2011-01-01

    The main aim of the Work Package 1 (WP1) of the ORAMED project, Collaborative Project (2008–2011), supported by the European Commission within its 7th Framework Programme, was to obtain a set of standardized data on extremity and eye lens doses for staff in interventional radiology and cardiology (IR/IC) workplaces and to recommend a series of guidelines on radiation protection in order to both guarantee and optimize staff protection. Within the project, coordinated measurements were performed in 34 hospitals in 6 European countries. Furthermore, simulations of the most representative workplaces in IR and IC were performed to determine the main parameters that influence the extremity and eye lens doses. The work presented in this paper shows the recommendations that were formulated by the results obtained from both measurements and simulations. The presented guidelines are directed to operators, assistant personnel, radiation protection officers and medical physics experts. They concern radiation protection issues, such as the use of room protective equipment, as well as the positioning of the extremity and eye lens dosemeters for routine monitoring.

  3. Psychological, social, and environmental factors to meeting physical activity recommendations among Japanese adults

    Directory of Open Access Journals (Sweden)

    Harada Kazuhiro

    2009-08-01

    Full Text Available Abstract Background Although the benefits of the recommended level of physical activity on reducing chronic diseases are well-established, most of the Japanese population is not sufficiently active. Thus, examining correlates is an important prerequisite for designing relevant polices and effective programs. The present study investigated psychological, social, and environmental factors associated with meeting physical activity recommendations among Japanese adults. Methods Data were analyzed for 1,932 men and women (43.6 ± 13.0 years, who responded to an Internet-based cross-sectional survey. Self-reported measure of physical activity, psychological (self-efficacy, pros, and cons, social (social support, health professional advice, environmental (home fitness equipment, access to facilities, neighborhood safety, enjoyable scenery, frequently observing others exercising, residential area, and demographic (gender, age, marital status, educational level, household income level, employment status variables were obtained. Based on the current national guidelines for exercise in Japan (23 METs·hour per week, respondents were divided into two categories–recommended and not recommended (insufficient and inactive–according to their estimated weekly physical activity level. An adjusted logistic regression model was utilized. Results When adjusting for all other variables, self-efficacy (men: OR = 2.13; 95% CI: 1.55–2.94, women: OR = 2.72; 95% CI: 1.82–4.08 and possessing home fitness equipment (men: OR = 1.55; 95% CI: 1.14–2.10, women: OR = 1.41; 95% CI: 1.01–1.99 for both genders, social support (OR = 1.44; 95% CI: 1.06–1.97 for men, and enjoyable scenery (OR = 1.60; 95% CI: 1.09–2.36 for women were positively associated with attaining the recommended level of physical activity. In women, cons (OR = 0.47; 95% CI: 0.33–0.67 and living in rural areas (OR = 0.50; 95% CI: 0.25–0.97 were negatively associated with meeting the physical

  4. Psychological, social, and environmental factors to meeting physical activity recommendations among Japanese adults.

    Science.gov (United States)

    Shibata, Ai; Oka, Koichiro; Harada, Kazuhiro; Nakamura, Yoshio; Muraoka, Isao

    2009-08-28

    Although the benefits of the recommended level of physical activity on reducing chronic diseases are well-established, most of the Japanese population is not sufficiently active. Thus, examining correlates is an important prerequisite for designing relevant polices and effective programs. The present study investigated psychological, social, and environmental factors associated with meeting physical activity recommendations among Japanese adults. Data were analyzed for 1,932 men and women (43.6 +/- 13.0 years), who responded to an Internet-based cross-sectional survey. Self-reported measure of physical activity, psychological (self-efficacy, pros, and cons), social (social support, health professional advice), environmental (home fitness equipment, access to facilities, neighborhood safety, enjoyable scenery, frequently observing others exercising, residential area), and demographic (gender, age, marital status, educational level, household income level, employment status) variables were obtained. Based on the current national guidelines for exercise in Japan (23 METs.hour per week), respondents were divided into two categories-recommended and not recommended (insufficient and inactive)-according to their estimated weekly physical activity level. An adjusted logistic regression model was utilized. When adjusting for all other variables, self-efficacy (men: OR = 2.13; 95% CI: 1.55-2.94, women: OR = 2.72; 95% CI: 1.82-4.08) and possessing home fitness equipment (men: OR = 1.55; 95% CI: 1.14-2.10, women: OR = 1.41; 95% CI: 1.01-1.99) for both genders, social support (OR = 1.44; 95% CI: 1.06-1.97) for men, and enjoyable scenery (OR = 1.60; 95% CI: 1.09-2.36) for women were positively associated with attaining the recommended level of physical activity. In women, cons (OR = 0.47; 95% CI: 0.33-0.67) and living in rural areas (OR = 0.50; 95% CI: 0.25-0.97) were negatively associated with meeting the physical activity recommendations. In the psychological, social, and

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

    Directory of Open Access Journals (Sweden)

    I.P. Susila

    2017-08-01

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

  6. System for prediction of environmental emergency dose information

    International Nuclear Information System (INIS)

    Moriuchi, Shigeru

    1989-01-01

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

  7. Editorial: New operational dose equivalent quantities

    International Nuclear Information System (INIS)

    Harvey, J.R.

    1985-01-01

    The ICRU Report 39 entitled ''Determination of Dose Equivalents Resulting from External Radiation Sources'' is briefly discussed. Four new operational dose equivalent quantities have been recommended in ICRU 39. The 'ambient dose equivalent' and the 'directional dose equivalent' are applicable to environmental monitoring and the 'individual dose equivalent, penetrating' and the 'individual dose equivalent, superficial' are applicable to individual monitoring. The quantities should meet the needs of day-to-day operational practice, while being acceptable to those concerned with metrological precision, and at the same time be used to give effective control consistent with current perceptions of the risks associated with exposure to ionizing radiations. (U.K.)

  8. 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.

  9. 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

  10. SPEEDI: system for prediction of environmental emergency dose information

    International Nuclear Information System (INIS)

    Chino, Masamichi; Ishikawa, Hirohiko; Kai, Michiaki

    1984-03-01

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

  11. Evaluation of environmental radiation dose in Ibaraki Prefecture

    International Nuclear Information System (INIS)

    Koike, Ryoji

    1977-01-01

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

  12. Nonparametric estimation of benchmark doses in environmental risk assessment

    Science.gov (United States)

    Piegorsch, Walter W.; Xiong, Hui; Bhattacharya, Rabi N.; Lin, Lizhen

    2013-01-01

    Summary An important statistical objective in environmental risk analysis is estimation of minimum exposure levels, called benchmark doses (BMDs), that induce a pre-specified benchmark response in a dose-response experiment. In such settings, representations of the risk are traditionally based on a parametric dose-response model. It is a well-known concern, however, that if the chosen parametric form is misspecified, inaccurate and possibly unsafe low-dose inferences can result. We apply a nonparametric approach for calculating benchmark doses, based on an isotonic regression method for dose-response estimation with quantal-response data (Bhattacharya and Kong, 2007). We determine the large-sample properties of the estimator, develop bootstrap-based confidence limits on the BMDs, and explore the confidence limits’ small-sample properties via a short simulation study. An example from cancer risk assessment illustrates the calculations. PMID:23914133

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1993-07-01

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

  14. Diclofenac pharmacokinetic meta-analysis and dose recommendations for surgical pain in children aged 1-12 years.

    Science.gov (United States)

    Standing, Joseph F; Tibboel, Dick; Korpela, Reijo; Olkkola, Klaus T

    2011-03-01

    Diclofenac is an effective, opiate-sparing analgesic for acute pain in children, which is commonly used in pediatric surgical units. Recently, a Cochrane review concluded the major knowledge gap in diclofenac use is dosing information. A pharmacokinetic meta-analysis has been undertaken with the aim of recommending a dose for children aged 1-12 years. Studies containing diclofenac pharmacokinetic data were identified during a Cochrane systematic review, and authors were asked to provide raw data. A pooled population analysis was undertaken in NONMEM to define the pharmacokinetics of intravenous, oral, and rectal diclofenac in children. Simulations were performed to recommend a dose yielding an equivalent area under diclofenac concentration-time curve (AUC) to a 50-mg dispersible tablet in adults. Data from 111 children aged 1-14 years consisting of 375 samples following intravenous, oral suspension, and suppositories were used. Adult dispersible tablet and suspension data were added to provide a reference AUC and support the absorption modeling, respectively. A three-compartment model described disposition, a dual-absorption compartment model was used for suspension and dispersible tablet data, and single-absorption compartment model for suppositories. The estimate of clearance was 16.5 l·h(-1) ·70 kg(-1) and bioavailabilities were 0.36, 0.63, and 0.35 for suspension, suppository, and dispersible tablets, respectively. Single doses of 0.3 mg·kg(-1) for intravenous, 0.5 mg·kg(-1) for suppositories, and 1 mg·kg(-1) for oral diclofenac in children aged 1-12 years are recommended as they yield a similar AUC to 50 mg in adults. © 2011 Blackwell Publishing Ltd.

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

    International Nuclear Information System (INIS)

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

    1979-01-01

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

  16. Work plan for the Hanford Environmental Dose Reconstruction Project

    Energy Technology Data Exchange (ETDEWEB)

    1989-12-01

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

  17. Environmental dose measurement with microprocessor based portable TLD reader

    International Nuclear Information System (INIS)

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

    1996-01-01

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

  18. Significance of BETA and GAMMA dose on environmental qualification of components

    International Nuclear Information System (INIS)

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

    1999-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1993-03-01

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

  20. Quantitative Evaluation of Compliance with Recommendation for Sulfonylurea Dose Co-Administered with DPP-4 Inhibitors in Japan

    Directory of Open Access Journals (Sweden)

    Motonobu Sakaguchi

    2012-09-01

    Full Text Available After the launch of dipeptidyl peptidase-4 (DPP-4, a new oral hypoglycemic drug (OHD, in December 2009, severe hypoglycemia cases were reported in Japan. Although the definite cause was unknown, co-administration with sulfonylureas (SU was suspected as one of the potential risk factors. The Japan Association for Diabetes Education and Care (JADEC released a recommendation in April 2010 to lower the dose of three major SUs (glimepiride, glibenclamide, and gliclazide when adding a DPP-4 inhibitor. To evaluate the effectiveness of this risk minimization action along with labeling changes, dispensing records for 114,263 patients prescribed OHDs between December 2008 and December 2010 were identified in the Nihon-Chouzai pharmacy claims database. The adherence to the recommended dosing of SU co-prescribed with DPP-4 inhibitors increased from 46.3% before to 63.8% after the JADEC recommendation (p < 0.01 by time-series analysis, while no change was found in those for SU monotherapy and SU with other OHD co-prescriptions. The adherence was significantly worse for those receiving a glibenclamide prescription. The JADEC recommendation, along with labeling changes, appeared to have a favorable effect on the risk minimization action in Japan. In these instances, a pharmacy claims database can be a useful tool to evaluate risk minimization actions.

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

    International Nuclear Information System (INIS)

    Kanematsu, Seiko

    1999-01-01

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

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

    International Nuclear Information System (INIS)

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

    1994-05-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1994-05-01

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

  4. Standards, options and recommends for the external radiotherapy of patients reached by prostate carcinoma: evaluation of dose effect

    International Nuclear Information System (INIS)

    Pommier, P.; Fervers, B.; Villers, A.; Bataillard, A.

    2002-01-01

    The 'Standards, Options and Recommendations' (SOR) collaborative project was initiated in 1993 by the Federation of the French Cancer Centres (FNCLCC), with the 20 French Regional Cancer Centres (FNCCLCC), with the 20 French Regional Cancer Centres, several French public university and general hospitals, as well as private clinics and medical specialty societies. Its main objective is the development of serviceable clinical practice guidelines in order to improve the quality of health care and the outcome of cancer patients. The methodology is based on a literature review, followed by critical appraisal by a multidisciplinary group of experts. Draft guidelines for the radiotherapy of prostate cancer using the methodology developed by the Standards, Options and Recommendations project. The FNCLCC and the French Urology Association (AFU) designated the multidisciplinary group of experts. Available data were collected by a search of Medline and lists selected by experts in the group A first draft of the guidelines was written, they validated by independent reviewers. The main recommendations are: a minimal dose of 70 Gy; patients with intermediate prognosis are the ones who benefit most from the dose escalation effect over 74 Gy, provided they receive exclusive radiation therapy; whenever possible, patients should be included in controlled trials designed to assess the effects of dose escalation and hormonotherapy. (author)

  5. Environmental monitoring system with TLD; Sistema de monitoreo ambiental con TLD

    Energy Technology Data Exchange (ETDEWEB)

    Aguerre, L.; Carelli, J.; Gregori, B. [Autoridad Regulatoria Nuclear Argentina (Argentina)]. e-mail: laguerre@cae.arn.gov.ar

    2006-07-01

    Presently work the methodology used by the Laboratory of Thermoluminescent Dosimetry (TLD) of the Nuclear Regulatory Authority (RNA) to gauge it system of environmental monitoring in function of the media absorbed dose rate in free air and the environmental dose equivalent, H{sup *}(10), according to the recommendation ICRU Report 47 is described. It was studied the response of the environmental dosemeter (DA) in fields of photonic radiation of energies W60, Wl 10, W200 and {sup 137} Cs. The irradiations were carried out following the recommendations of the standard ISO:4037. It was analyzed the response in the DA of the detectors LiF: Mg, Ti and CaF{sub 2}: Dy for the different radiation qualities and the relative response at {sup 137} Cs of both. The methodology used in the evaluation of the dose includes: the correction of the readings of both detectors by fading, gotten experimentally, the witness of transfers, the energy answer and the value of the zero. The dose is calculated applying the average pondered in uncertainty of the dose obtained for each type of detector. Its were analyzed and calculated the uncertainties that affect to the measurement following the recommendation of the Argentine standard IRAM 35050. The detection limit of the absorbed dose rate in free air of this system it is 3.5 n Gy/h for a period of sampling of 3 months. With this detection limit environmental dose equivalent rates of the order of 70 n Sv/h are measured with an expanded uncertainty of the order of 10% with a cover factor k = 2. (Author)

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

    International Nuclear Information System (INIS)

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

    2001-01-01

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

  7. Integration of models for the Hanford Environmental Dose Reconstruction Project

    International Nuclear Information System (INIS)

    Napier, B.A.

    1991-01-01

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

  8. Volumes and doses for external radiotherapy - Definitions and recommendations; Volum og doser i ekstern straaleterapi - Definisjoner og anbefalinger

    Energy Technology Data Exchange (ETDEWEB)

    Levernes, Sverre (ed.)

    2012-07-01

    The report contains definitions of volume and dose parameters for external radiotherapy. In addition the report contains recommendations for use, documentation and minimum reporting for radiotherapy of the individual patient.(Author)

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

    International Nuclear Information System (INIS)

    Nagaoka, Toshi; Saito, Kimiaki; Moriuchi, Shigeru

    1991-05-01

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

  10. Nuclear health and safety. Status of GAO's environmental, safety, and health recommendations to DOE

    International Nuclear Information System (INIS)

    England-Joseph, Judy; Bannerman, Carl J.; Fenzel, William F.; Brack, David L.; Harter, Frederick A.

    1990-04-01

    DOE's operations are carried out at many contractor-operated sites around the country, including major sites within the nuclear weapons complex that are involved in the production of nuclear material for weapons and naval fuel. At these sites DOE contractors routinely use and generate large quantities of a wide range of hazardous and radioactive materials. Because these materials require special handling by workers. Also pursuant to Mar. 15, 1989, request, we provided you a report entitled Nuclear Health and Safety: Need for Improved Responsiveness to Problems at DOE Sites (GAO/RCED-90-101, Mar. 28, 1990). to prevent exposure to themselves or releases into the environment, DOE's weapons complex, considered in its entirety, is among the potentially more dangerous industrial operations in the world. Over the last decade, at the request of the Congress, we have carried out a series of assessments and evaluations of various aspects of the complex. In over 60 reports and testimonies published since 1990, we have called attention to the mounting problems facing DOE's nuclear weapons complex. This body of work includes (1) identifying serious, costly, and widespread environmental, safety, and health problems at DOE facilities, (2) calling for outside independent oversight of DOE's nuclear operations, and (3) making recommendations to DOE to strengthen its oversight, providing more detailed information and plans to the Congress, and improving its management and accounting practices. In total, our reports and testimonies have included 54 recommendations to DOE, in addition to recommendations to the Congress, concerning environmental, safety, and health matters at the complex. We consider 23 of the 54 recommendations to be still open. The open recommendations call for improvements such as tighter program controls and clearer standards and policies related to environmental, safety, and health matters

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2016-12-15

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

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

    International Nuclear Information System (INIS)

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

    2016-01-01

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

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

    International Nuclear Information System (INIS)

    Glantz, C.S.

    1989-01-01

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

  14. Risk and environmental impact assessment: nuclear and environmental licensing interface

    International Nuclear Information System (INIS)

    Costa, Eduardo M.; Monteiro, Iara A.

    1997-01-01

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

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

    International Nuclear Information System (INIS)

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

    2008-01-01

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

  16. Education in Environmental Chemistry: Setting the Agenda and Recommending Action. A Workshop Report Summary

    Science.gov (United States)

    Zoller, Uri

    2005-08-01

    Worldwide, the essence of the current reform in science education is a paradigm shift from algorithmic, lower-order cognitive skills (LOCS) teaching to higher-order cognitive skills (HOCS) learning. In the context of education in environmental chemistry (EEC), the ultimate goal is to educate students to be science technology environment society (STES)-literate, capable of evaluative thinking, decision making, problem solving and taking responsible action accordingly. Educators need to translate this goal into effective courses that can be implemented: this includes developing teaching strategies and assessment methodologies that are consonant with the goal of HOCS learning. An international workshop—"Environmental Chemistry Education in Europe: Setting the Agenda"—yielded two main recommendations for those undertaking educational reform in science education, particularly to promote meaningful EEC. The first recommendation concerns integration of environmental sciences into core chemistry courses as well as the development and implementation of HOCS-promoting teaching strategies and assessment methodologies in chemical education. The second emphasizes the development of students' HOCS for transfer, followed by performance assessment of HOCS. This requires changing the way environmental chemistry is typically taught, moving from a narrowly focused approach (applied analytical, ecotoxicological, or environmental engineering chemistry) to an interdisciplinary and multidisciplinary approach.

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

    International Nuclear Information System (INIS)

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

    1983-12-01

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

  18. Analysis of the new ICRP recommendations from the point of view of environmental impact

    International Nuclear Information System (INIS)

    Gonzalez, A.J.

    1978-01-01

    The paper analyses the implications of the new ICRP recommendations referring optimization and justification as they apply to the nuclear power industry, in particular referring to its environmental impact. It also discusses the possible effects of applying this requirements on regional nuclear power programmes. The possibility of extrapolating the ICRP recommendations for use as a basis for nuclear safety aspects of nuclear power reactors is also analyzed. (author)

  19. International recommendations

    International Nuclear Information System (INIS)

    Lindell, Bo

    1986-01-01

    Full text: This short presentation will indicate the general radiation protection background to protective measures against foodstuffs contaminated with radioactive substances. A number of international organizations are involved in various aspects of radiation protection, for example, the International Atomic Energy Agency (IAEA), the United Nations Food and Agriculture Organization (FAO), the United Nations Environment Programme (UNEP), and the World Health Organization (WHO). Two international organizations, however, provide the basic background. These are the International Commission on Radiological Protection (ICRP) and the United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR). UNSCEAR provides the scientific information on radiation levels and effects. It consists of 21 member countries, with truly international coverage. It issues reports to the UN General Assembly, including comprehensive scientific annexes. Its latest comprehensive report was issued in 1982, the next is expected to be published in 1988. That report will include an assessment of the radiological consequences of the Chernobyl accident. The ICRP is a non-governmental organization. It has issued recommendations on radiation protection since 1928. The postulated biological basis for radiation protection recommendations involves two types of biological effects. The so-called non-stochastic effects, mainly due to cell death, appear only when the radiation doses exceed a certain threshold value. These effects, therefore, can only appear after high accidental exposures. After the Chernobyl accident, they only affected about 200 individuals involved in fire extinction and rescue work at the damaged nuclear power plant. Stochastic effects, with some simplification, may be seen as the result of initial changes in the genetic code of some surviving cells. If these cells are germ cells, this may lead to hereditary harm. If they are somatic cells, the result could be cancer

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

    International Nuclear Information System (INIS)

    Shipler, D.B.

    1992-04-01

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

  1. 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)

  2. Communication tools for the Hanford Environmental Dose Reconstruction Project

    International Nuclear Information System (INIS)

    Blazek, Mary Lou; Power, Max S.

    1992-01-01

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

  3. Phase 1 of the Hanford Environmental Dose Reconstruction Project

    International Nuclear Information System (INIS)

    1991-08-01

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

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

    International Nuclear Information System (INIS)

    Bahreyni Toossi, M.T.; Bayani, S.H.; Abdolrahimi, A.; Yarahmadi, M.; Aghamir, A.; Jomehzadeh, A.; Hagh Parast, M.; Tamjidi, A.

    2008-01-01

    Natural radiation environment and it's biological impacts on human life has not received appreciable attention in Iran. Before 1996 only a few sporadic studies had been carried out, but no systematic study of normal back ground had been conducted. Since 1996 assessment of environmental gamma radiation dose in residential areas of Iranian towns and cities was defined as a long term goal in our center. Till now measurements of annual dose rates have been accomplished for 10 counties. As a practical method and based on the results of a pilot study, in order to attribute the final results to the whole residential area of a town five stations were selected for every town. The location of individual station was studied closely to comply with recommended conditions in the literature. RDS-110 was employed to measure gamma dose rate for one hour. Practically huge numbers of dose rate figures were recorded, they were substantially summarized to estimate average dose rate. Average annual dose rates plus conversion coefficients were employed to estimate gonad, bone marrow, equivalent and effective dose. In the vast studied area average out-door gamma dose rate is varying from 35 nSvh -1 to 205 nSvh -1 . Minimum and maximum annual bone marrow and gonad dose equivalent attributed to environmental gamma are 0.24 mSvy -1 (for both tissues) and 1.44 and 1.46 mSvy -1 respectively. Effective dose of inhabitants arising from out-door gamma is varying by 6 folds from 0.21 to 1.26 mSvy -1 . The largest and smallest population weighted dose are equal to 0.35 and 1.00 mSvy -1 . Average gonad and bone marrow doses for north Khorasan, Boshehr and Hormozgan are less than the corresponding values for normal area. On the other hand inhabitants of the studied area receive a dose higher than the world average, except those who live in Hormozgan and Boshehr. (author)

  5. A recommendation for revised dose calibrator measurement procedures for 89Zr and 124I.

    Directory of Open Access Journals (Sweden)

    Bradley J Beattie

    Full Text Available Because of their chemical properties and multiday half lives, iodine-124 and zirconium-89 are being used in a growing number of PET imaging studies. Some aspects of their quantitation, however, still need attention. For (89Zr the PET images should, in principle, be as quantitatively accurate as similarly reconstructed 18F measurements. We found, however, that images of a 20 cm well calibration phantom containing (89Zr underestimated the activity by approximately 10% relative to a dose calibrator measurement (Capintec CRC-15R using a published calibration setting number of 465. PET images of (124I, in contrast, are complicated by the contribution of decays in cascade that add spurious coincident events to the PET data. When these cascade coincidences are properly accounted for, quantitatively accurate images should be possible. We found, however, that even with this correction we still encountered what appeared to be a large variability in the accuracy of the PET images when compared to dose calibrator measurements made using the calibration setting number, 570, recommended by Capintec. We derive new calibration setting numbers for (89Zr and (124I based on their 511 keV photon peaks as measured on an HPGe detector. The peaks were calibrated relative to an 18F standard, the activity level of which was precisely measured in a dose calibrator under well-defined measurement conditions. When measuring (89Zr on a Capintec CRC-15R we propose the use of calibration setting number 517. And for (124I, we recommend the use of a copper filter surrounding the sample and the use of calibration setting number 494. The new dose calibrator measurement procedures we propose will result in more consistent and accurate radioactivity measurements of (89Zr and (124I. These and other positron emitting radionuclides can be accurately calibrated relative to 18F based on measurements of their 511 keV peaks and knowledge of their relative positron abundances.

  6. Regulatory Forum Opinion Piece*: Retrospective Evaluation of Doses in the 26-week Tg.rasH2 Mice Carcinogenicity Studies: Recommendation to Eliminate High Doses at Maximum Tolerated Dose (MTD) in Future Studies.

    Science.gov (United States)

    Paranjpe, Madhav G; Denton, Melissa D; Vidmar, Tom J; Elbekai, Reem H

    2015-07-01

    High doses in Tg.rasH2 carcinogenicity studies are usually set at the maximum tolerated dose (MTD), although this dose selection strategy has not been critically evaluated. We analyzed the body weight gains (BWGs), mortality, and tumor response in control and treated groups of 29 Tg.rasH2 studies conducted at BioReliance. Based on our analysis, it is evident that the MTD was exceeded at the high and/or mid-doses in several studies. The incidence of tumors in high doses was lower when compared to the low and mid-doses of both sexes. Thus, we recommend that the high dose in male mice should not exceed one-half of the estimated MTD (EMTD), as it is currently chosen, and the next dose should be one-fourth of the EMTD. Because females were less sensitive to decrements in BWG, the high dose in female mice should not exceed two-third of EMTD and the next dose group should be one-third of EMTD. If needed, a third dose group should be set at one-eighth EMTD in males and one-sixth EMTD in females. In addition, for compounds that do not show toxicity in the range finding studies, a limit dose should be applied for the 26-week carcinogenicity studies. © 2014 by The Author(s).

  7. Decision management for the Hanford Environmental Dose Reconstruction Project

    Energy Technology Data Exchange (ETDEWEB)

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

    1992-04-01

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

  8. Decision management for the Hanford Environmental Dose Reconstruction Project

    International Nuclear Information System (INIS)

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

    1992-04-01

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

  9. Implementation of ICRP-60 recommendations on dose limits to radiation workers in India

    International Nuclear Information System (INIS)

    Parthasarathy, K.S.

    2000-01-01

    The handling of radioactive material and radiation generating plants in India is regulated by the Atomic Energy Act, 1962 and rules issued under the Act. The Atomic Energy Regulatory Board enforces the rules. Currently, there are about 40,000 radiation workers in the country. Nearly half of them are employed in nuclear installations. During 1989, the Board considered the impact of restricting the maximum individual exposure to different values of dose limits. Through this analysis, the Board alerted all radiation users including persons responsible for radiation safety in nuclear facilities. When ICRP published ICRP-60, the Board issued directives to all radiation installations reducing the dose limit to occupational workers in a phased manner (40 mSv for 1991, 35 mSv for 1992 and 30 mSv for 1993). To meet the recommendations of ICRP-60, AERB issued a directive for the five year block 1994-1998, restricting the cumulative effective dose constraint to one hundred milliSievert (100 mSv) for individual radiation workers. Also, the annual effective dose to individual workers in any calendar year during the five-year block was restricted to thirty milliSievert (30 mSv). The stipulations of AERB are thus more conservative than those of ICRP. There was near total compliance with the dose limits by radiation installations in the country. For instance, in 1989, the number of radiation workers in nuclear power plants, who exceeded the dose level of 20 mSv/year was 9% of the total. This declined gradually to 2.2% in 1993 and 0.3% in 1997. During 1998, only 9 out of 10,145 exceeded 20 mSv/year. This has been achieved by the concerted efforts of the management, health physics staff and radiation workers. The health physicists regulated the radiation doses to workers by issuing work permits when the workers are assigned any job in high radiation areas. Appropriate training programmes are also in place. The broad guidelines to regulate radiation exposures in nuclear facilities

  10. Recommendations of the French academy of medicine

    International Nuclear Information System (INIS)

    The, G. de; Tubiana, M.

    2002-01-01

    Recently the French academy of medicine (FAM) decided to make a point concerning radiological protection and issued the 6 following recommendations and statements: 1) FAM recommends the global reduction of the radiation dose received by patients during medical examination; 2) FAM recommends to promote and develop the research work concerning the biological effects of doses lower than 100 mSv; 3) FAM recommends to reject the linear-non threshold model for low dose radiation; 4) FAM agrees with the UNSCEAR report about the consequences of the Chernobyl accident, apart from the early fatalities in rescue workers, the main health effect is an increase risk of thyroid cancer in children, in particular, there has been no evidence of increase in other cancer incidence or in congenital malformation; 5) FAM recommends the introduction of the dari as a practical dose sub-unit, 1 dari represents the dose received by the whole body for 1 year due to natural radioactivity; and 6) FAM recommends that the European directive concerning the annual limit dose, maintains its value to 100 mSv a year. (A.C.)

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

    International Nuclear Information System (INIS)

    White, M.G.

    1995-01-01

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

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

    International Nuclear Information System (INIS)

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

    1997-01-01

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

  13. A comparison of dose versus risk at environmental restoration sites

    International Nuclear Information System (INIS)

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

    1996-01-01

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

  14. Monitoring of dose rates and radiation flux density in working rooms

    International Nuclear Information System (INIS)

    Krajtor, S.N.

    1980-01-01

    The problems of determining the neutron field characteristics (dose equivalent rate and flux density) in relation to the environmental monitoring by radiation protection services. The measurement devices used for measuring dose equivalent rate and neutron flux density RUS-U8 multi-purpose scintillation radiometer and RUP-1 multi-purpose transportable radiometer as well as measurement technique are described. Recommendations are given for checking measuring devices calibration, registering measurement results [ru

  15. 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

  16. How to understand the radiation effects of small dose - some critical comments on ICRP recommendations

    Energy Technology Data Exchange (ETDEWEB)

    Matsuura, T. [Radiation Education Forum, Minato-ku, Tokyo (Japan)

    1997-10-01

    The widespread feeling of `radiophobia` by the general public has its basis on the ICRP`s `linear no-threshold` hypothesis in dose-response relationship for low dose radiation from the standpoint of radiation protection. Although this common feeling served as a merit for constructing the `safety culture` of society, it has now become a large obstacle for the development of peaceful uses of nuclear technology as a demerit. Recently many data have been accumulated for the radiation effects of low dose, both epidemiologically and experimentally. Although in general it is very difficult to obtain clear evidence of presence or absence of threshold, it seems to be true that the risk by radiation exposure at low level (the definition of which is below 0.2 Gy) is not so large as that of extrapolation from the high or medium dose range. In fact, many data suggest that some quite different mechanisms are working in low dose from high dose, such as `adaptive response`, and a new concept, `radiation hormesis`, has emerged, that the low level radiation is not only quite harmless but is rather necessary for living cells or beneficial for human health. In this paper, some critical comments on ICRP recommendations are given as a personal view by the author. These include: (1) a question of exact assessment of exposed dose by A-bomb survivors used for the epidemiological data, which are regarded to be the most authentic and important; (2) a brief summary of effects at the natural radiation level, including the high background area data; (3) the importance of dose rate effect, which reflects the living matter`s repairability from radiation injury, and (4) the proposal of new paradigm by adopting the reasonable `de minimis` level (below which there is no harm) both for low dose and at low dose rate. A simple mathematical analysis for representative data of dose rate effect was shown as an appendix 50 refs., 2 tabs., 4 figs.

  17. How to understand the radiation effects of small dose - some critical comments on ICRP recommendations

    International Nuclear Information System (INIS)

    Matsuura, T.

    1997-01-01

    The widespread feeling of 'radiophobia' by the general public has its basis on the ICRP's 'linear no-threshold' hypothesis in dose-response relationship for low dose radiation from the standpoint of radiation protection. Although this common feeling served as a merit for constructing the 'safety culture' of society, it has now become a large obstacle for the development of peaceful uses of nuclear technology as a demerit. Recently many data have been accumulated for the radiation effects of low dose, both epidemiologically and experimentally. Although in general it is very difficult to obtain clear evidence of presence or absence of threshold, it seems to be true that the risk by radiation exposure at low level (the definition of which is below 0.2 Gy) is not so large as that of extrapolation from the high or medium dose range. In fact, many data suggest that some quite different mechanisms are working in low dose from high dose, such as 'adaptive response', and a new concept, 'radiation hormesis', has emerged, that the low level radiation is not only quite harmless but is rather necessary for living cells or beneficial for human health. In this paper, some critical comments on ICRP recommendations are given as a personal view by the author. These include: (1) a question of exact assessment of exposed dose by A-bomb survivors used for the epidemiological data, which are regarded to be the most authentic and important; (2) a brief summary of effects at the natural radiation level, including the high background area data; (3) the importance of dose rate effect, which reflects the living matter's repairability from radiation injury, and (4) the proposal of new paradigm by adopting the reasonable 'de minimis' level (below which there is no harm) both for low dose and at low dose rate. A simple mathematical analysis for representative data of dose rate effect was shown as an appendix

  18. Endocrine-Disrupting Chemicals and Oil and Natural Gas Operations: Potential Environmental Contamination and Recommendations to Assess Complex Environmental Mixtures.

    Science.gov (United States)

    Kassotis, Christopher D; Tillitt, Donald E; Lin, Chung-Ho; McElroy, Jane A; Nagel, Susan C

    2016-03-01

    Hydraulic fracturing technologies, developed over the last 65 years, have only recently been combined with horizontal drilling to unlock oil and gas reserves previously deemed inaccessible. Although these technologies have dramatically increased domestic oil and natural gas production, they have also raised concerns for the potential contamination of local water supplies with the approximately 1,000 chemicals that are used throughout the process, including many known or suspected endocrine-disrupting chemicals. We discuss the need for an endocrine component to health assessments for drilling-dense regions in the context of hormonal and antihormonal activities for chemicals used. We discuss the literature on a) surface and groundwater contamination by oil and gas extraction operations, and b) potential human exposure, particularly in the context of the total hormonal and antihormonal activities present in surface and groundwater from natural and anthropogenic sources; we also discuss initial analytical results and critical knowledge gaps. In light of the potential for environmental release of oil and gas chemicals that can disrupt hormone receptor systems, we recommend methods for assessing complex hormonally active environmental mixtures. We describe a need for an endocrine-centric component for overall health assessments and provide information supporting the idea that using such a component will help explain reported adverse health trends as well as help develop recommendations for environmental impact assessments and monitoring programs.

  19. Endocrine-disrupting chemicals and oil and natural gas operations: Potential environmental contamination and recommendations to assess complex environmental mixtures

    Science.gov (United States)

    Kassotis, Christopher D.; Tillitt, Donald E.; Lin, Chung-Ho; McElroy, Jane A.; Nagel, Susan C.

    2016-01-01

    Background: Hydraulic fracturing technologies, developed over the last 65 years, have only recently been combined with horizontal drilling to unlock oil and gas reserves previously deemed inaccessible. While these technologies have dramatically increased domestic oil and natural gas production, they have also raised concerns for the potential contamination of local water supplies with the approximately 1,000 chemicals used throughout the process, including many known or suspected endocrine-disrupting chemicals.Objectives: We discuss the need for an endocrine component to health assessments for drilling-dense regions in the context of hormonal and anti-hormonal activities for chemicals used.Methods: We discuss the literature on 1) surface and ground water contamination by oil and gas extraction operations, and 2) potential human exposure, particularly in context of the total hormonal and anti-hormonal activities present in surface and ground water from natural and anthropogenic sources, with initial analytical results and critical knowledge gaps discussed.Discussion: In light of the potential for environmental release of oil and gas chemicals that can disrupt hormone receptor systems, we recommend methods for assessing complex hormonally active environmental mixtures.Conclusions: We describe a need for an endocrine-centric component for overall health assessments and provide supporting information that using this may help explain reported adverse health trends as well as help develop recommendations for environmental impact assessments and monitoring programs.

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

    International Nuclear Information System (INIS)

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

    1986-02-01

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

  1. Evaluation of nuclear power plant environmental impact prediction, based on monitoring programs. Summary and recommendations

    International Nuclear Information System (INIS)

    Gore, K.L.; Thomas, J.M.; Kannberg, L.D.; Watson, D.G.

    1977-02-01

    An evaluation of the effectivenss of non-radiological environmental monitoring programs is presented. The monitoring programs for Monticello, Haddam Neck, and Millstone Nuclear Generating Plants are discussed. Recommendations for improvements in monitoring programs are presented

  2. Amikacin Dosing and Monitoring in Spinal Cord Injury Patients: Variation in Clinical Practice Between Spinal Injury Units and Differences in Experts' Recommendations

    Directory of Open Access Journals (Sweden)

    Subramanian Vaidyanathan

    2006-01-01

    Full Text Available The objective of this article was to determine the current practice on amikacin dosing and monitoring in spinal cord injury patients from spinal cord physicians and experts. Physicians from spinal units and clinical pharmacologists were asked to provide protocol for dosing and monitoring of amikacin therapy in spinal cord injury patients. In a spinal unit in Poland, amikacin is administered usually 0.5 g twice daily. A once-daily regimen of amikacin is never used and amikacin concentrations are not determined. In Belgium, Southport (U.K., Spain, and the VA McGuire Medical Center (Richmond, Virginia, amikacin is given once daily. Whereas peak and trough concentrations are determined in Belgium, only trough concentration is measured in Southport. In both these spinal units, modification of the dose is not routinely done with a nomogram. In Spain and the VA McGuire Medical Center, monitoring of serum amikacin concentration is not done unless a patient has renal impairment. In contrast, the dose/interval of amikacin is adjusted according to pharmacokinetic parameters at the Edward Hines VA Hospital (Hines, Illinois, where amikacin is administered q24h or q48h, depending on creatinine clearance. Spinal cord physicians from Denmark, Germany, and the Kessler Institute for Rehabilitation (West Orange, New Jersey state that they do not use amikacin in spinal injury patients. An expert from Canada does not recommend determining serum concentrations of amikacin, but emphasizes the value of monitoring ototoxicity and nephrotoxicity. Experts from New Zealand recommend amikacin in conventional twice- or thrice-daily dosing because of the theoretical increased risk of neuromuscular blockade and apnea with larger daily doses in spinal cord injury patients. On the contrary, experts from Greece, Israel, and the U.S. recommend once-daily dosing and determining amikacin pharmacokinetic parameters for each patient. As there is considerable variation in clinical

  3. An environmental dose experiment

    Science.gov (United States)

    Peralta, Luis

    2017-11-01

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

  4. An environmental dose experiment

    International Nuclear Information System (INIS)

    Peralta, Luis

    2017-01-01

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

  5. Development of internal dose calculation programing via food ingestion

    International Nuclear Information System (INIS)

    Kim, H. J.; Lee, W. K.; Lee, M. S.

    1998-01-01

    Most of dose for public via ingestion pathway is calculating for considering several pathways; which start from radioactive material released from a nuclear power plant to diffusion and migration. But in order to model these complicate pathways mathematically, some assumptions are essential and lots of input data related with pathways are demanded. Since there is uncertainty related with environment in these assumptions and input data, the accuracy of dose calculating result is not reliable. To reduce, therefore, these uncertain assumptions and inputs, this paper presents exposure dose calculating method using the activity of environmental sample detected in any pathway. Application of dose calculation is aim at peoples around KORI nuclear power plant and the value that is used to dose conversion factor recommended in ICRP Publ. 60

  6. Intrapersonal, behavioral, and environmental factors associated with meeting recommended physical activity among rural Latino youth.

    Science.gov (United States)

    Perry, Cynthia K; Saelens, Brian E; Thompson, Beti

    2011-11-01

    This study aimed to identify intrapersonal, behavioral, and environmental factors associated with engaging in recommended levels of physical activity among rural Latino middle school youth. Data were from an anonymous survey of 773 Latino youth (51% female) about level of and barriers and motivators to physical activity, risk behaviors, and park use. Logistic regression models identified factors correlated with meeting recommended levels of physical activity (5 days or more 3 60 min/day). Thirty-four percent of girls and 41% of boys reported meeting this physical activity recommendation. Participation in an organized after school activity (p < .001) and in physical education (PE) classes 5 days a week (p < .001) were strongly associated with meeting recommended physical activity level. Making PE available 5 days a week and creating opportunities for organized after school physical activity programs may increase the number of rural Latino middle school youth who meet recommended physical activity level.

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

    Energy Technology Data Exchange (ETDEWEB)

    Heeb, C.M.

    1994-05-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2003-05-01

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

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

    CERN Document Server

    Taki, M; Kobayashi, H; Yamaguchi, T

    2003-01-01

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

  10. Integrated numerical platforms for environmental dose assessments of large tritium inventory facilities

    International Nuclear Information System (INIS)

    Castro, P.; Ardao, J.; Velarde, M.; Sedano, L.; Xiberta, J.

    2013-01-01

    Related with a prospected new scenario of large inventory tritium facilities [KATRIN at TLK, CANDUs, ITER, EAST, other coming] the prescribed dosimetric limits by ICRP-60 for tritium committed-doses are under discussion requiring, in parallel, to surmount the highly conservative assessments by increasing the refinement of dosimetric-assessments in many aspects. Precise Lagrangian-computations of dosimetric cloud-evolution after standardized (normal/incidental/SBO) tritium cloud emissions are today numerically open to the perfect match of real-time meteorological-data, and patterns data at diverse scales for prompt/early and chronic tritium dose assessments. The trends towards integrated-numerical-platforms for environmental-dose assessments of large tritium inventory facilities under development.

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

    International Nuclear Information System (INIS)

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

    2004-01-01

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

  12. Recommendations to designers aimed at minimizing radiation dose incurred in operation, maintenance, inspection and repair of light-water reactors

    International Nuclear Information System (INIS)

    1978-01-01

    In the framework of the exchange of experience between nuclear power plant operators organized by the services of the Commission of the European Communities an ad-hoc working party elaborated recommendations particularly directed to those concerned with design of light water reactor plants. The necessary design measures which should be followed to minimize radiation dose incurred in operation, maintenance, inspection and repair of such reactors are listed. The recommendations are based on recent views expressed by operating utilities within the Community. It is intended to revise these recommendations at suitable intervals in order to make use of the most recent experience and to keep the report up to date with the actual state of art in nuclear technology

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

    International Nuclear Information System (INIS)

    Brennan, B.J.

    2001-01-01

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

  14. Radiation protection recommendations on dose limits: the role of the NCRP and the ICRP and future developments

    International Nuclear Information System (INIS)

    Sinclair, Warren K.

    1995-01-01

    The purpose of this paper is to review the role of the National Council on Radiation Protection and Measurements (NCRP) and the International Commission on Radiological Protection (ICRP) in making recommendations on dose limits for ionizing radiation exposure for workers and for the public. The text describes the new limits for workers and public recommended by ICRP in 1991 and NCRP in 1993 and the composition of the radiation health detriment on which they are based. The main component of this detriment is the risk of radiation induced cancer which is now estimated to be about three times greater than a decade or so earlier. Uncertainties in these risk estimates are discussed. Some special radiation protection problems, such as those for the embryo or fetus are described. The article also addresses future progress in radiation protection particularly with regard to future improvements in the scientific basis for radiation protection recommendations

  15. Recommendation on the Environmental Effect Report for the high-voltage transmission line between Netherlands and Norway

    International Nuclear Information System (INIS)

    1998-01-01

    The recommendation on the title subject was addressed to the Dutch Minister of Economic Affairs and concerns the environmental impact of the new high-voltage transmission line (NorNed cable) from Norway to the Eemshaven in Groningen, Netherlands. In planning this power cable the environmental impact on the Wadden Sea has to be taken into account. Therefore an environmental effect report (MER, abbreviated in Dutch) has been drafted by the Dutch cooperative of electric power generating companies, Sep, and commented by the WaddenAdviesRaad

  16. Comparison of current recommended regimens of atropinization in organophosphate poisoning.

    Science.gov (United States)

    Connors, Nicholas J; Harnett, Zachary H; Hoffman, Robert S

    2014-06-01

    Atropine is the mainstay of therapy in organophosphate (OP) toxicity, though research and consensus on dosing is lacking. In 2004, as reported by Eddleston et al. (J Toxicol Clin Toxicol 42(6):865-75, 2004), they noted variation in recommended regimens. We assessed revisions of original references, additional citations, and electronic sources to determine the current variability in atropine dosing recommendations. Updated editions of references from Eddleston et al.'s work, texts of Internal and Emergency Medicine, and electronic resources were reviewed for atropine dosing recommendations. For comparison, recommendations were assessed using the same mean dose (23.4 mg) and the highest dose (75 mg) of atropine as used in the original paper. Recommendations were also compared with the dosing regimen from the World Health Organization (WHO). Thirteen of the original recommendations were updated and 15 additional references were added giving a convenience sample of 28. Sufficient information to calculate time to targeted dose was provided by 24 of these samples. Compared to 2004, current recommendations have greatly increased the speed of atropinization with 13/24 able to reach the mean and high atropine dose within 30 min compared to 1/36 in 2004. In 2004, there were 13 regimens where the maximum time to reach 75 mg was over 18 h, whereas now, there are 2. While only one recommendation called for doubling the dose for faster escalation in 2004, 15 of the 24 current works include dose doubling. In 2004, Eddleston et al. called for an evidence-based guideline for the treatment of OP poisoning that could be disseminated worldwide. Many current recommendations can adequately treat patients within 1 h. While the WHO recommendations remain slow to treat patients with OP poisoning, other authorities are close to a consensus on rapid atropinization.

  17. Staff eye doses in a large medical centre in Saudi Arabia: are they meeting the new ICRP recommendations?

    International Nuclear Information System (INIS)

    Al-Haj, Abdalla N.; Al-Gain, Ibrahim; Lobriguito, Aida M.

    2015-01-01

    A 5-y retrospective analysis of the cardiology staff eye doses was performed on 34 staff from different categories (cardiologists, nurses and technologists) at King Faisal Specialist Hospital and Research Centre (KFSHRC) in Riyadh, Saudi Arabia. KFSHRC is a tertiary medical centre with 800-bed capacity having more than 5000 cardiac catheterisation procedures performed annually. The aim of the study is to derive staff doses to the lens of the eyes using the personal dose equivalent Hp(0.07) values from the annual TLD dose report for the years 2008-2012 and determine the category of staff with high estimated eye doses. The study also aims to investigate the causes for high doses and recommend dose-reduction techniques. The dose to the lens of the eye was estimated by using the ratio Hp(0.07) slab /H lens of 1.1 where Hp(0.07) values are the reported doses read from TLD badge worn at the collar level. The average annual eye dose of each category for the 5-y monitoring period was determined. Cardiologists tend to receive higher doses than the nurses by a factor of 2-4 and can exceed 5 mSv y -1 . No correlation exists between the eye doses of nurses and the cardiologists. There is a need to use a conversion coefficient in terms of eye lens dose per dose-area product for faster estimation of eye lens doses. However, there is a limitation on the use of the conversion coefficient because it will depend on the clinical procedure and the X-ray tube angulation. Further investigation on this limitation is needed. (authors)

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

    International Nuclear Information System (INIS)

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

    2008-01-01

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

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

    International Nuclear Information System (INIS)

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

    2005-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1999-06-01

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

  1. 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.

  2. Recommendations on dose buildup factors used in models for calculating gamma doses for a plume

    International Nuclear Information System (INIS)

    Hedemann Jensen, P.; Thykier-Nielsen, S.

    1980-09-01

    Calculations of external γ-doses from radioactivity released to the atmosphere have been made using different dose buildup factor formulas. Some of the dose buildup factor formulas are used by the Nordic countries in their respective γ-dose models. A comparison of calculated γ-doses using these dose buildup factors shows that the γ-doses can be significantly dependent on the buildup factor formula used in the calculation. Increasing differences occur for increasing plume height, crosswind distance, and atmospheric stability and also for decreasing downwind distance. It is concluded that the most accurate γ-dose can be calculated by use of Capo's polynomial buildup factor formula. Capo-coefficients have been calculated and shown in this report for γ-energies below the original lower limit given by Capo. (author)

  3. Ambient radioactivity levels and radiation doses. Annual report 2011

    International Nuclear Information System (INIS)

    Bernhard-Stroel, Claudia; Hachenburger, Claudia; Trugenberger-Schnabel, Angela; Peter, Josef

    2013-07-01

    The annual report 2011 on ambient radioactivity levels and radiation doses covers the following issues: Part A: Natural environmental radioactivity, artificial radioactivity in the environment, occupational radiation exposure, radiation exposure from medical applications, the handling of radioactive materials and sources of ionizing radiation, non-ionizing radiation. Part B; Current data and their evaluation: Natural environmental radioactivity, artificial radioactivity in the environment, occupational radiation exposure, radiation exposure from medical applications, the handling of radioactive materials and sources of ionizing radiation, non-ionizing radiation. The Appendix includes Explanations of terms, radiation doses and related units, external and internal radiation exposure, stochastic and deterministic radiation effects, genetic radiation effects, induction of malignant neoplasm, risk assessment, physical units and glossary, laws, ordinances, guidelines, recommendations and other regulations concerning radiation protection, list of selected radionuclides.

  4. Review of calculational models and computer codes for environmental dose assessment of radioactive releases

    International Nuclear Information System (INIS)

    Strenge, D.L.; Watson, E.C.; Droppo, J.G.

    1976-06-01

    The development of technological bases for siting nuclear fuel cycle facilities requires calculational models and computer codes for the evaluation of risks and the assessment of environmental impact of radioactive effluents. A literature search and review of available computer programs revealed that no one program was capable of performing all of the great variety of calculations (i.e., external dose, internal dose, population dose, chronic release, accidental release, etc.). Available literature on existing computer programs has been reviewed and a description of each program reviewed is given

  5. Review of calculational models and computer codes for environmental dose assessment of radioactive releases

    Energy Technology Data Exchange (ETDEWEB)

    Strenge, D.L.; Watson, E.C.; Droppo, J.G.

    1976-06-01

    The development of technological bases for siting nuclear fuel cycle facilities requires calculational models and computer codes for the evaluation of risks and the assessment of environmental impact of radioactive effluents. A literature search and review of available computer programs revealed that no one program was capable of performing all of the great variety of calculations (i.e., external dose, internal dose, population dose, chronic release, accidental release, etc.). Available literature on existing computer programs has been reviewed and a description of each program reviewed is given.

  6. CYP2B6 genotype-based efavirenz dose recommendations during rifampicin-based antituberculosis cotreatment for a sub-Saharan Africa population.

    Science.gov (United States)

    Mukonzo, Jackson K; Bisaso, Ronald K; Ogwal-Okeng, Jasper; Gustafsson, Lars L; Owen, Joel S; Aklillu, Eleni

    2016-04-01

    To assess genotype effect on efavirenz (EFV) pharmacokinetics, treatment outcomes and provide genotype-based EFV doses recommendations during for tuberculosis (TB)-HIV-1 cotreatment. EFV concentrations from 158 HIV-TB co-infected patients treated with EFV/lamivudine/zidovidine and rifampicin were analyzed. Genotype and CD4 and viral load data were analyzed using a population PK model. Simulated AUCs for 600 mg EFV dose were 1.2- and 2.4-times greater than the product label for Ugandans in general and CYP2B6*6/*6 genotypes respectively. EFV daily doses of 450 and 250 mg for Ugandans and CYP2B6*6/*6 genotypes, respectively, yielded simulated exposures comparable to the product label. Around 450 and 250 mg daily doses might meet EFV dosing needs of HIV-TB infected Ugandans in general and CYP2B6*6/*6 genotypes, respectively.

  7. Environmental radioactivity and dose evaluation in Taiwan after the Chernobyl accident

    International Nuclear Information System (INIS)

    Chung, C.E.

    1989-01-01

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

  8. Environmental impact of uranium mining and milling: an American view

    International Nuclear Information System (INIS)

    Momeni, M.H.

    1981-01-01

    The radiation dose rates to man from uranium milling activities are discussed. The sources of radiation, the radioisotopes involved, and the environmental exposure pathways are described. Risks of cancer to exposed individuals are presented and recommendations made for mitigation of contamination

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2006-07-01

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

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

    International Nuclear Information System (INIS)

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

    2006-01-01

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

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

    International Nuclear Information System (INIS)

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

    2000-01-01

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

  12. FY 1991 Task plans for the Hanford Environmental Dose Reconstruction Project

    International Nuclear Information System (INIS)

    1991-04-01

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

  13. Recomendações para se evitar grandes erros de dose em tratamentos radioterapêuticos Recommendations to avoid gross errors of dose in radiotherapeutic treatments

    Directory of Open Access Journals (Sweden)

    Cleber Nogueira de Souza

    2001-02-01

    Full Text Available Erros humanos são uma importante fonte de falhas em todos os passos do planejamento e do tratamento radioterapêutico. Com o objetivo de reduzir este grau de incerteza, várias organizações especializadas recomendam minuciosos programas de garantia da qualidade. No Brasil, programas deste tipo vêm tendo sua exigência intensificada, e a maioria dos serviços de radioterapia vem se orientando neste sentido, tanto em relação aos equipamentos de radiação e dosimetria, quanto em relação à verificação dos cálculos de dose em pacientes e das revisões das fichas de planejamento. Como uma contribuição a este esforço de qualidade, apresentam-se algumas recomendações para se evitar falhas de tratamento devidas a erros na dose de radiação recebida pelo paciente, como redundância nas verificações dos cálculos feitos manualmente ou por computador, e, também, a verificação da dose acumulada para cada paciente sob tratamento, semanalmente, além de se evitar a possibilidade de acesso a qualquer sistema de segurança do equipamento ao pessoal técnico treinado para apenas o operar. Além disso, deve-se considerar a possibilidade de se empregar um sistema computadorizado de verificação e registro do tratamento, dessa maneira prevenindo-se erros durante a aplicação diária devidos à seleção indevida dos diferentes parâmetros do tratamento. Reportam-se quatro incidentes radioativos recentes ocorridos no mundo, com injúrias em pacientes, e algumas ocorrências de erros grandes de dose.Human mistakes are an important source of errors in radiotherapy and may occur at every step of the radiotherapeutic planning and treatment. To reduce this level of uncertainties, several specialized organizations have recommended a comprehensive quality assurance program. In Brazil, the requirement for these programs has been strongly stressed, and most radiotherapy services have pursued this goal regarding radiation units and dosimetry equipment

  14. Review of ICRP recommendations

    International Nuclear Information System (INIS)

    Goldfinch, E.P.

    1987-01-01

    Events in both the scientific world and in the public domain have added pressure to review the recommendations of the ICRP on which radiation protection legislation in most countries is founded. A brief editorial pleads for clarity in ICRP recommendations, suggests the use solely of cumulative with age individual occupational dose limits, suggests that collective doses including both occupational and to the public should be kept as low as reasonably achievable, judged on quantitative economic grounds, and suggests the setting of a probability for serious accidents which may be disregarded in planning. (UK)

  15. Environmental monitoring report, 1978: Pinellas Plant

    International Nuclear Information System (INIS)

    1979-04-01

    Effluent and environmental monitoring programs maintained by the Pinellas Plant are designed to determine efficiencies of treatment and control mechanisms; to provide measurements of discharge concentrations for comparison with applicable standards; and to assess the concentrations of these discharges in the environment. Small quantities of tritium gas, tritium oxide and krypton-85 gas were released from the plant during the year. Average maximum ground level concentrations of these radioisotopes were all significantly less than 1/10 of 1 percent of the recommended guide for continuous nonoccupational exposure. Off-site releases of liquid effluents were analyzed for compliance with NPDES permit issues for this site by the U.S. Environmental protection Agency. Analyses were performed fo biochemical oxygen demand, suspended solids, fecal coliform bacteria, pH, nitrogen, phosphorus, arsenic, chlorides, chromium, copper, cyanides, detergents, fluorides, iron, lead, mercury, oil plus greases, phenols, turbidity and zinc. All results with the exception of suspended solids were well within permit limits. Site perimeter and off-site air samples for tritium gas and tritium oxide, as well as off-site surface water samples obtained to distances of 9.6 kilometers from the plant site and analyzed for tritium content, showed levels significantly less than 1/10 of 1 percent of the recommended guide for continuous nonoccupational exposure. Calculations were made to determine the radiation doses resulting from releases of tritium oxide and krypton-85 to: an individual at the site boundary; individuals in the closest residential area; and the population within 80 kilometers of the plant site. Calculated doses are exceedingly small when compared to the recommended standards. The total dose commitment to the population residing within 80 kilometers was determined to be 0.40 man-rem as compared to annual dose from natural radiation of 210,747 man-rem

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

    International Nuclear Information System (INIS)

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

    1991-01-01

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

  17. Suboptimal Antituberculosis Drug Concentrations and Outcomes in Small and HIV-Coinfected Children in India: Recommendations for Dose Modifications.

    Science.gov (United States)

    Guiastrennec, Benjamin; Ramachandran, Geetha; Karlsson, Mats O; Kumar, A K Hemanth; Bhavani, Perumal Kannabiran; Gangadevi, N Poorana; Swaminathan, Soumya; Gupta, Amita; Dooley, Kelly E; Savic, Radojka M

    2017-12-16

    This work aimed to evaluate the once-daily antituberculosis treatment as recommended by the new Indian pediatric guidelines. Isoniazid, rifampin, and pyrazinamide concentration-time profiles and treatment outcome were obtained from 161 Indian children with drug-sensitive tuberculosis undergoing thrice-weekly dosing as per previous Indian pediatric guidelines. The exposure-response relationships were established using a population pharmacokinetic-pharmacodynamic approach. Rifampin exposure was identified as the unique predictor of treatment outcome. Consequently, children with low body weight (4-7 kg) and/or HIV infection, who displayed the lowest rifampin exposure, were associated with the highest probability of unfavorable treatment (therapy failure, death) outcome (P unfavorable ). Model-based simulation of optimized (P unfavorable ≤ 5%) rifampin once-daily doses were suggested per treatment weight band and HIV coinfection status (33% and 190% dose increase, respectively, from the new Indian guidelines). The established dose-exposure-response relationship could be pivotal in the development of future pediatric tuberculosis treatment guidelines. © 2017, The Authors Clinical Pharmacology & Therapeutics published by Wiley Periodicals, Inc. on behalf of American Society for Clinical Pharmacology and Therapeutics.

  18. The new ICRP general recommendations

    International Nuclear Information System (INIS)

    Sasaki, Y.; Lochard, J.; Holm, L.E.; Niwa, O.; Ishigure, N.; Kosako, T.; Kai, M.

    2007-01-01

    The new draft ICRP recommendations was presented by the ICRP chair, Professor Lars-Eric Holm. His presentation was followed by presentations by Japanese members of the various (CRP committees, discussing their views of the draft recommendations based on their own technical experience. After these presentations, questions from the floor raised many of the key issues of the conference: dose constrains, the LNT hypothesis, dose bands, etc. This showed that the conference participants had carefully and completely read the draft, and were very interested in building a final ICRP recommendation that appropriately addresses all their concerns. These issues were also discussed throughout the entire conference. (author)

  19. 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

  20. Quantities for environmental monitoring

    International Nuclear Information System (INIS)

    1989-01-01

    It is recommended that if measurements are made with the objective of monitor radiation levels in the environment to elucidate long-term changes in these levels, then air kerma should be used. If the objective is to give an indication that levels from man-made sources are acceptable within specified limits for the exposure of people, then ambient dose equivalent should be used. It should be noted that radiation risks to individuals are best expressed by the quantity effective dose equivalent. If this latter quantity is to be accurately assessed, it may be necessary to obtain details of the quality of the environmental radiation that cannot be described adequately by simple measurements of either air kerma or ambient dose equivalent. If the above objectives pertain, the measurements should record both air kerma and ambient dose equivalent. If neutrons are measured in the environment then ambient dose equivalent is the appropriate quantity for both the above objectives. (author)

  1. Environmental and effluent monitoring at Lucas Heights Research Laboratories, 1994

    International Nuclear Information System (INIS)

    Hoffmann, E.L.; Camilleri, A.; Loosz, T.; Farrar, Y.

    1995-12-01

    Results are presented of environmental and effluent monitoring conducted in the vicinity of the Lucas Heights Research Laboratories (LHRL) during 1994. All low level liquid and gaseous effluent discharges complied with existing discharge authorisations and relevant environmental regulations. Potential effective doses to the general public from controlled airborne discharges during this period, were estimated to be less than 0.015 mSv/year for receptor locations on the 1.6 km buffer zone boundary around HIFAR. This value represents 1.5 % of the 1 mSv/year dose limit for long term exposure that is recommended by the National Health and Medical Research Council, and 5 % of the site dose constraint of 0.3 mSv/year adopted by ANSTO. 27 refs., 22 tabs., 6 figs

  2. Environmental and effluent monitoring at Lucas Heights Research Laboratories, 1994

    Energy Technology Data Exchange (ETDEWEB)

    Hoffmann, E L; Camilleri, A; Loosz, T; Farrar, Y

    1995-12-01

    Results are presented of environmental and effluent monitoring conducted in the vicinity of the Lucas Heights Research Laboratories (LHRL) during 1994. All low level liquid and gaseous effluent discharges complied with existing discharge authorisations and relevant environmental regulations. Potential effective doses to the general public from controlled airborne discharges during this period, were estimated to be less than 0.015 mSv/year for receptor locations on the 1.6 km buffer zone boundary around HIFAR. This value represents 1.5 % of the 1 mSv/year dose limit for long term exposure that is recommended by the National Health and Medical Research Council, and 5 % of the site dose constraint of 0.3 mSv/year adopted by ANSTO. 27 refs., 22 tabs., 6 figs.

  3. Environmental survey at Lucas Heights Research Laboratories, 1993

    International Nuclear Information System (INIS)

    Hoffmann, E.L.; Looz, T.

    1995-04-01

    Results are presented of the environmental survey conducted in the neighbourhood of the Lucas Heights Research Laboratories during 1993. No activity which could have originated from these laboratories was found in samples collected from possible human food chains. All low-level liquid and gaseous waste discharges were within authorised limits. The maximum possible annual dose to the general public from airborne discharges during this period is estimated to be less than 0.01 mSv, which is one per cent of the dose limit for long term exposure that is recommended by the National Health and Medical Research Council. A list of previous environmental survey reports is attached. 22 refs., 21 tabs., 4 figs

  4. Pantex Plant Cell 12-44-1 tritium release: Re-assessment of environmental doses for 1990 to 1992

    International Nuclear Information System (INIS)

    Snyder, S.F.; Hwang, S.T.

    1994-03-01

    A release of tritium gas occurred within Cell 12-44-1 at the Pantex Plant on May 17, 1989. The release was the result of a nuclear component containment failure. This document summarizes past assessments and characterization of the release. From 1990 to 1992, the average annual dose to the offsite maximally exposed individual (MEI), re-assessed using updated methods and data, ranged from 9E-6 to 2E-4 mrem/y. Doses at this level are well below the regulatory dose limit and support the discontinuation of the distinct calculation of the MEI doses from the cell's tritium releases in future Pantex Annual Site Environmental Reports. Additional information provides guidance for the evaluation of similar releases in the future. Improved Environmental Protection Department sampling plans and assessment goals will increase the value of the data collected during future incidents

  5. Estimation of collective effective dose equivalent from environmental radiation and radioactive materials in Japan. A preliminary study

    International Nuclear Information System (INIS)

    Maruyama, Takashi; Noda, Yutaka; Takeshita, Mitsue; Iwai, Kazuo.

    1994-01-01

    The peaceful uses of nuclear power and radiations have been developed into a stage of practical applications for human life. Radiation causes harmful effects to human beings, although human beings receives a number of invaluable benefits from the nuclear energy and the uses of radiation. In order to examine the optimization of radiation protection in these practices, collective effective dose equivalent from environmental exposures due to natural and artificial radiations have been preliminarily evaluated using most recent data. The resultant collective doses were compared with those from medical and occupational exposures. It is noted that, in Japan, the collective effective dose from environmental radiation sources can be approximately same to that from medical exposure. (author)

  6. Collective dose, conceptual basis and practical applications

    International Nuclear Information System (INIS)

    Bonka, H.

    1985-01-01

    In the ICRP Publications no. 22(1973) and no. 26(1977), the ICRP recommends that the maximum permissible whole-body dose by kept below the dose limits corresponding to the sum of all effective dose equivalents of the persons concerned, i.e. the collective dose. The effective dose equivalent is recommended by the ICRP for use as a new quantity for evaluating the stochastic radiation dose for individual persons. Examples are given by the author explaining cost-benefit analyses according to ICRP recommendations, especially discussing the definition of optimum local dose limits with regard to shielding design in nuclear installations. (DG) [de

  7. Tritium in air and environmental water in Jiuquan district and its dose to population

    International Nuclear Information System (INIS)

    Yang Ziwen; Zhang Yonghong; Guo Guizhi; Bai Guodong

    1993-01-01

    From July 1987 to November 1989, the monitoring of the tritium in air and environmental water in Jiuquan District was made for the first time. The results show that the average tritium concentrations of surface water in this region remained 4.6-9.6 Bq/1 in recent years. However, these values are still an order of magnitude higher than those before thermonuclear tests era in 1952. The tritium concentration in air was approximately twice as much as that of surface water. HTO values in air exhibit a higher peak in summer. The total tritium ingested by residents of Jiuquan was 1.12 x 10 4 Bq. The collective dose equivalent was equal to 0.25 man · Sv per year. Because of taking environmental tritium in the area, the annual committed effective dose equivalent was 0.19 μSv which is only one five thousandth of annual limited dose to the public proposed by ICRP and one ten thousandth of the natural background estimated by UNSCEAR in 1982

  8. Implication of new CEC recommendations for individual monitoring for external radiation doses to the skin and the extremities

    International Nuclear Information System (INIS)

    Christensen, P.; Julius, H.W.; Marshall, T.O.

    1991-01-01

    A drafting group consisting of the above authors has assisted the CEC in revising the CEC document Technical Recommendations for Monitoring the Exposure to Individuals to External Radiation, EUR 5287, published in 1975. The paper highlights sections of the revised version relating particularly to irradiation of the skin and the extremities and focusses on problems connected to exposure to weakly penetrating radiations. Concepts of individual monitoring for external radiation exposures to the skin of the whole body and to the extremities are discussed and guidance is given as regards dose quantities and dosemeter calibration procedures. A method of quantifying the overall accuracy of the dose measurements as a result of the various uncertainty components connected with the dosimetry system is suggested and requirements on the accuracy of the dose measurements complying with the ICRP requirements on overall accuracy for individual monitoring are specified. Moreover, implications of the accuracy requirements for the design and type testing of the dosemeter are discussed. (author)

  9. Dose and Dose-Rate Effectiveness Factor (DDREF); Der Dosis- und Dosisleistungs-Effektivitaetsfaktor (DDREF)

    Energy Technology Data Exchange (ETDEWEB)

    Breckow, Joachim [Fachhochschule Giessen-Friedberg, Giessen (Germany). Inst. fuer Medizinische Physik und Strahlenschutz

    2016-08-01

    For practical radiation protection purposes it is supposed that stochastic radiation effects a determined by a proportional dose relation (LNT). Radiobiological and radiation epidemiological studies indicated that in the low dose range a dependence on dose rates might exist. This would trigger an overestimation of radiation risks based on the LNT model. OCRP had recommended a concept to combine all effects in a single factor DDREF (dose and dose-Rate effectiveness factor). There is still too low information on cellular mechanisms of low dose irradiation including possible repair and other processes. The Strahlenschutzkommission cannot identify a sufficient scientific justification for DDREF and recommends an adaption to the actual state of science.

  10. What is correct: equivalent dose or dose equivalent

    International Nuclear Information System (INIS)

    Franic, Z.

    1994-01-01

    In Croatian language some physical quantities in radiation protection dosimetry have not precise names. Consequently, in practice either terms in English or mathematical formulas are used. The situation is even worse since the Croatian language only a limited number of textbooks, reference books and other papers are available. This paper compares the concept of ''dose equivalent'' as outlined in International Commission on Radiological Protection (ICRP) recommendations No. 26 and newest, conceptually different concept of ''equivalent dose'' which is introduced in ICRP 60. It was found out that Croatian terminology is both not uniform and unprecise. For the term ''dose equivalent'' was, under influence of Russian and Serbian languages, often used as term ''equivalent dose'' even from the point of view of ICRP 26 recommendations, which was not justified. Unfortunately, even now, in Croatia the legal unit still ''dose equivalent'' defined as in ICRP 26, but the term used for it is ''equivalent dose''. Therefore, in Croatian legislation a modified set of quantities introduced in ICRP 60, should be incorporated as soon as possible

  11. 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

  12. Hanford Environmental Dose Reconstruction Project independent direction and oversight

    International Nuclear Information System (INIS)

    Blazek, M.L.; Power, M.

    1991-01-01

    Hanford was selected in 1942 as one of the sites for the Manhattan Project. It produced plutonium for one of the world's first nuclear weapons. The US Department of Energy (DOE) and its predecessors continued to make plutonium for nuclear weapons at Hanford for more than four decades. In the early days of Hanford operations, radioactive materials routinely were released to the environment by many processes. The DOE disclosed documents about these releases in 1986. In 1987, Washington, Oregon, and regional Indian tribes gathered an independent panel of experts. This group recommended dose reconstruction and health effects feasibility studies. Later that year, DOE hired Battelle Pacific Northwest Laboratory (PNL) to reconstruct potential public radiation doses from Hanford's past releases of radioactive material. The DOE agreed with the states and tribes that project direction would come from an independent technical steering panel (TSP). This approach was critical to gain public credibility for the project and the science. The TSP directs the project and makes policy. That is now clear - but, it was hard-earned. Conducting science in an open public process is new, challenging, and clearly worthwhile. The panel's product is good science that is believed and accepted by the public - our client

  13. Environmental and effluent monitoring at Lucas Heights Science and Technology Centre, 1996

    International Nuclear Information System (INIS)

    Hoffmann, E.L.; Loosz, T.; Farrar, Y.

    1997-06-01

    Results are presented of environmental and effluent monitoring conducted in the vicinity of the Lucas Heights Science and Technology Centre during 1996. All low-level liquid and gaseous effluent discharges complied with existing discharge authorizations and relevant environmental regulations. Potential effective doses to the general public from controlled airborne discharges during this period, were estimated to be less than 0.010 mSv/year for receptor locations on the 1.6 km buffer zone boundary around HIFAR. This value represents 1% of the 1 mSv/year dose limit for long term exposure that is recommended by thr National Health and Medical Research Council and 3.3% of the site dose constraint of 0.3mSv/year adopted by ANSTO. Details of the environmental sample collection and analytical procedures are given in the appendices. (authors)

  14. Environmental and effluent monitoring at Lucas Heights Science and Technology Centre, 1996

    Energy Technology Data Exchange (ETDEWEB)

    Hoffmann, E.L.; Loosz, T.; Farrar, Y.

    1997-06-01

    Results are presented of environmental and effluent monitoring conducted in the vicinity of the Lucas Heights Science and Technology Centre during 1996. All low-level liquid and gaseous effluent discharges complied with existing discharge authorizations and relevant environmental regulations. Potential effective doses to the general public from controlled airborne discharges during this period, were estimated to be less than 0.010 mSv/year for receptor locations on the 1.6 km buffer zone boundary around HIFAR. This value represents 1% of the 1 mSv/year dose limit for long term exposure that is recommended by thr National Health and Medical Research Council and 3.3% of the site dose constraint of 0.3mSv/year adopted by ANSTO. Details of the environmental sample collection and analytical procedures are given in the appendices. (authors). 29 refs., 26 tabs., 6 figs.

  15. Evaluation of the use of ICRP 60 dose conversion factors in a postclosure assessment of a deep geological disposal system

    International Nuclear Information System (INIS)

    Palattao, M.V.B.; Hajas, W.C.; Goodwin, B.W.

    1997-05-01

    An Environmental Impact Statement (EIS) of the concept for disposal of Canada's nuclear fuel waste was completed in 1994 and is currently under review by an independent Review Panel. This EIS included a postclosure assessment case study to estimate the annual effective dose equivalent in sieverts per year to members of the public; these estimates were obtained using dose conversion factors (DCFS) based on the 1977 recommendations of the International Commission on Radiation Protection (ICRP). However, in 1990 the ICRP revised these recommendations based on additional biological information and developments in radiation protection. This report describes a study of how the more recent recommendations of the ICRP would affect the results of the postclosure assessment case study presented in the EIS. The report includes a theoretical description of how DCFs are used and a comparison of results from computer simulations using the 1977 and the 1990 ICRP recommendations. In the EIS case study, which was based on the 1977 ICRP recommendations, the total dose rate to a member of the critical group is more than six orders of magnitude below the dose rate associated with the regulatory criterion for individual radiological risk. The total dose rate to 10 4 years is dominated by 129 I, with smaller contributions from 36 C1 and 14 C. If the 1990 ICRP recommendations were implemented, the total dose rate would be mostly affected by the new DCF for 129 I, and would increase by about 67%. Even with this increase, the total dose rate would still remain many orders of magnitude lower than the dose rate associated with the regulatory risk criterion. (author)

  16. SSDL quality assurance for environmental dose/dose rate monitoring of photon radiation

    International Nuclear Information System (INIS)

    1987-01-01

    Member states of IAEA have recently approved an expanded Nuclear Safety Programme and two International Conventions have been signed. One concerns early notification of a nuclear accident, and the other concerns assistance in the case of a nuclear accident or radiological emergency. In the course of the implementation of these conventions an international system will be established by the Agency for the reception and dissemination of data following a nuclear accident. Such data should include the results of radiation measurements obtained by radiation monitoring. These data must be reliable, and comparable. This assures that numerical values of measured quantities obtained at different times, sites and countries, and with different instruments, can be compared in order that the competent authorities may draw conclusions. Such measurements may also have legal consequences. This implies that the instruments used for the measurement should comply with the relevant international specifications, and that the readings of these instruments be traceable to the international measurement system. At a meeting of an expert working group on International Cooperation in Nuclear Safety and Radiation Protection held in November 1986, a proposal to produce a technical document on ''The role of SSDLs in the quality assurance programme relating to the use of dose and dose rate meters for personal and environmental measurements'' received high priority, and at a subsequent meeting of the Board of Governors the proposal was approved. Prior to these proposals the SSDL Scientific Committee at its annual meeting in May 1986 also advised the IAEA to promote measures to ensure world wide reliability and traceability of dose measurements in the field of radiation protection. On 26-30 January 1987 an Advisory Group Meeting on ''The role of SSDLs in the dosimetry of unintentional radiation exposures'' was organized by the IAEA. This Advisory Group assisted the Agency in the formulation of a

  17. The ciprofloxacin target AUC : MIC ratio is not reached in hospitalized patients with the recommended dosing regimens.

    Science.gov (United States)

    Haeseker, Michiel; Stolk, Leo; Nieman, Fred; Hoebe, Christian; Neef, Cees; Bruggeman, Cathrien; Verbon, Annelies

    2013-01-01

    The aim of this study was to determine the ciprofloxacin serum concentrations in hospitalized patients and to determine which percentage reached the efficacy target of AUC : MIC > 125. Additionally, the influence of demographic anthropomorphic and clinical parameters on the pharmacokinetics and pharmacodynamics of ciprofloxacin were investigated. In serum of 80 hospitalized patients ciprofloxacin concentrations were measured with reverse phase high performance liquid chromatography with fluorescence detection. The ciprofloxacin dose was 400-1200 mg day(-1) i.v. in two or three doses depending on renal function and causative bacteria. Pharmacokinetic parameters were calculated with maximum a posteriori Bayesian estimation (MW\\PHARM 3.60). A two compartment open model was used. Mean (± SD) age was 66 (± 17) years, the mean clearance corrected for bodyweight was 0.24 l h(-1) kg(-1) and the mean AUC was 49 mg l(-1) h. Ciprofloxacin clearance and thus AUC were associated with both age and serum creatinine. Of all patients, 21% and 75% of the patients, did not reach the proposed ciprofloxacin AUC : MIC > 125 target with MICs of 0.25 and 0.5 mg l(-1), respectively. A computer simulated increase in the daily dose from 800 mg to 1200 mg, decreased these percentages to 1% and 37%, respectively. A substantial proportion of the hospitalized patients did not reach the target ciprofloxacin AUC : MIC and are suboptimally dosed with recommended doses. Taking into account the increasing resistance to ciprofloxacin worldwide, a ciprofloxacin dose of 1200 mg i.v. daily in patients with normal renal function is necessary to reach the targeted AUC : MIC > 125. © 2012 The Authors. British Journal of Clinical Pharmacology © 2012 The British Pharmacological Society.

  18. Implications for human and environmental health of low doses of ionising radiation

    International Nuclear Information System (INIS)

    Mothersill, Carmel; Seymour, Colin

    2014-01-01

    The last 20 years have seen a major paradigm shift in radiation biology. Several discoveries challenge the DNA centric view which holds that DNA damage is the critical effect of radiation irrespective of dose. This theory leads to the assumption that dose and effect are simply linked – the more energy deposition, the more DNA damage and the greater the biological effect. This is embodied in radiation protection (RP) regulations as the linear-non-threshold (LNT) model. However the science underlying the LNT model is being challenged particularly in relation to the environment because it is now clear that at low doses of concern in RP, cells, tissues and organisms respond to radiation by inducing responses which are not readily predictable by dose. These include adaptive responses, bystander effects, genomic instability and low dose hypersensitivity, and are commonly described as stress responses, while recognizing that “stress” can be good as well as bad. The phenomena contribute to observed radiation responses and appear to be influenced by genetic, epigenetic and environmental factors, meaning that dose and response are not simply related. The question is whether our discovery of these phenomena means that we need to re-evaluate RP approaches. The so-called “non-targeted” mechanisms mean that low dose radiobiology is very complex and supra linear or sub-linear (even hormetic) responses are possible but their occurrence is unpredictable for any given system level. Issues which may need consideration are synergistic or antagonistic effects of other pollutants. RP, at present, only looks at radiation dose but the new (NTE) radiobiology means that chemical or physical agents, which interfere with tissue responses to low doses of radiation, could critically modulate the predicted risk. Similarly, the “health” of the organism could determine the effect of a given low dose by enabling or disabling a critical response. These issues will be discussed

  19. Commercial milk distribution profiles and production locations. Hanford Environmental Dose Reconstruction Project

    Energy Technology Data Exchange (ETDEWEB)

    Deonigi, D.E.; Anderson, D.M.; Wilfert, G.L.

    1994-04-01

    The Hanford Environmental Dose Reconstruction (HEDR) Project was established to estimate radiation doses that people could have received from nuclear operations at the Hanford Site since 1944. For this period iodine-131 is the most important offsite contributor to radiation doses from Hanford operations. Consumption of milk from cows that ate vegetation contaminated by iodine-131 is the dominant radiation pathway for individuals who drank milk (Napier 1992). Information has been developed on commercial milk cow locations and commercial milk distribution during 1945 and 1951. The year 1945 was selected because during 1945 the largest amount of iodine-131 was released from Hanford facilities in a calendar year (Heeb 1993); therefore, 1945 was the year in which an individual was likely to have received the highest dose. The year 1951 was selected to provide data for comparing the changes that occurred in commercial milk flows (i.e., sources, processing locations, and market areas) between World War II and the post-war period. To estimate the doses people could have received from this milk flow, it is necessary to estimate the amount of milk people consumed, the source of the milk, the specific feeding regime used for milk cows, and the amount of iodine-131 contamination deposited on feed.

  20. FY 1993 task plans for the Hanford Environmental Dose Reconstruction Project

    International Nuclear Information System (INIS)

    Shipler, D.B.

    1991-10-01

    The purpose of the Hanford Environmental Dose Reconstruction (HEDR) Project is to estimate radiation doses from Hanford Site operations since 1944 to individuals and populations. The primary objective of work to be performed in FY 1993 is to complete the source term estimates and dose estimates for key radionuclides for the air and river pathways. At the end of FY 1993, the capability will be in place to estimate doses for individuals in the extended (32-county) study area, 1944--1991. Native American research will continue to provide input for tribal dose estimates. In FY 1993, the Technical Steering Panel (TSP) will decide whether demographic and river pathways data collection should be extended beyond FY 1993 levels. The FY 1993 work scopes and milestones in this document are based on the work plan discussed at the TSP Budget/Fiscal Subcommittee meeting on August 19--20, 1991. Table 1 shows the FY 1993 milestones; Table 2 shows estimated costs. The subsequent work scope descriptions are based on the milestones. This document and the FY 1992 task plans will form the basis for a contract with Battelle and the Centers for Disease Control (CDC). The 2-year dose reconstruction contract is expected to begin in February 1992. This contract will replace the current arrangement, whereby the US Department of Energy directly funds the Pacific Northwest Laboratory to conduct dose reconstruction work. In late FY 1992, the FY 1993 task plans will be more fully developed with detailed technical approaches, data quality objectives, and budgeted labor hours. The task plans will be updated again in July 1993 to reflect any scope, milestone, or cost changes directed during the year by the TSP. 2 tabs

  1. Environmental evaluation of the outdoor radiological risk from a sewage sludge irradiation plant using a consultation system

    International Nuclear Information System (INIS)

    Mangussi, M.J.; Caporale, M.C.

    2003-01-01

    The consultation system presented will be included in the environmental assessment for a sewage sludge irradiation plant working with 7000.000 Ci of cobalt 60. The system shows over suitable plans the effective dose rate at any point selected by the user or it shows the equal dose zones on a color scheme; in both situations the security recommended upper level of the effective dose is showed. The software, developed in the Borland Delphi 5 visual language, is comprehensible without high nuclear knowledge and perusing it will be easy for the environmental authorities as well as for common people. (author)

  2. An emergency decision-making on a regional environmental contamination

    International Nuclear Information System (INIS)

    Yasuda, Hiroshi

    1996-01-01

    When an environmental contamination occurs in a wide area, it is necessary to estimate the future influence by emergent environmental monitoring and rapidly take measures for it. This study aimed to support an emergency decision-making by constructing practical schemes with regards to the following three items in the dose limitation system recommended by ICRP; validity of intervention actions, optimization of protection and dose limitation. A framework of decision-making process was constructed to make clear the corresponding responsibility and the principle of intervention, to introduce stochastic techniques for estimating the environmental radiation shift and to reduce the social burden for the contamination. The results obtained by using this method were variable depending on the characteristics of subjects and regions applied. Therefore, it is needed to select an appropriate evaluation model and specific parameters suitable for the respective cases. (M.N.)

  3. Computational model design specification for Phase 1 of the Hanford Environmental Dose Reconstruction Project

    Energy Technology Data Exchange (ETDEWEB)

    Napier, B.A.

    1991-07-01

    The objective of the Hanford Environmental Dose Reconstruction (HEDR) Project is to estimate the radiation dose that individuals could have received as a result of emission from nuclear operations at Hanford since their inception in 1944. The purpose of this report is to outline the basic algorithm and necessary computer calculations to be used to calculate radiation doses specific and hypothetical individuals in the vicinity of Hanford. The system design requirements, those things that must be accomplished, are defined. The system design specifications, the techniques by which those requirements are met, are outlined. Included are the basic equations, logic diagrams, and preliminary definition of the nature of each input distribution. 4 refs., 10 figs., 9 tabs.

  4. Computational model design specification for Phase 1 of the Hanford Environmental Dose Reconstruction Project

    International Nuclear Information System (INIS)

    Napier, B.A.

    1991-07-01

    The objective of the Hanford Environmental Dose Reconstruction (HEDR) Project is to estimate the radiation dose that individuals could have received as a result of emission from nuclear operations at Hanford since their inception in 1944. The purpose of this report is to outline the basic algorithm and necessary computer calculations to be used to calculate radiation doses specific and hypothetical individuals in the vicinity of Hanford. The system design requirements, those things that must be accomplished, are defined. The system design specifications, the techniques by which those requirements are met, are outlined. Included are the basic equations, logic diagrams, and preliminary definition of the nature of each input distribution. 4 refs., 10 figs., 9 tabs

  5. Dose from radiological examinations

    International Nuclear Information System (INIS)

    Imamura, Keiko; Uji, Teruyuki; Sakuyama, Keiko; Fujikawa, Mitsuhiro; Fujii, Masamichi

    1976-01-01

    Relatively high gonad doses, several hundred to one thousand mR, have been observed in case of pelvis, hip-joint, coccyx, lower abdomen and lumber examination. Dose to the ovary is especially high in barium enema and I.V.P. examinations. About 12 per cent of the 4-ray examination are high-dose. The gonad dose is relatively high in examination of abdomen and lower extremities, in infants. The dose to the eyes is especially high, 1.0 to 2.5R per exposure, in temporal bone and nasal sinuses tomography. X-ray doses have been compared with dose limits recommended by ICRP and with the gonad dose from natural radiations. The gonad dose in lumbar examination, barium enema, I.V.P. etc. is as high as the maximum permissible dose per year recommended by ICRP. Several devices have been made for dose reduction in the daily examinations: (1) separating the radiation field from the gonad by one centimeter decreases the gonad dose about one-half. (2) using sensitive screens and films. In pelvimetry and in infant hip-joint examination, the most sensitive screen and film are used. In the I.V.P. examination of adult, use of MS screen in place of FS screen decreases the dose to one-third, in combination with careful setting of radiation field, (3) use of grid increases the dose about 50 percent and the lead rubber protection (0.1mm lead equivalent) decreases the gonad dose to one-thirtieth in the spinal column examination of infant, (4) A lead protector, 1mm thickness and 2.5cm in diameter, on the eyes decreases the dose to about one-eighth in the face and nead examinations. These simple and effective methods for dose reduction. Should be carried out in as many examinations as possible in addition to observing dose limits recommended by ICRP. (Evans, J.)

  6. Environmental and effluent monitoring at Lucas Heights Science and Technology Centre, 1997

    International Nuclear Information System (INIS)

    Hoffmann, E.L.; Loosz, T.; Farrar, Y

    1998-11-01

    Results are presented of environmental and effluent monitoring conducted in the vicinity of the Lucas Heights Science and Technology Centre (LHSTC) during 1997. All low-level liquid and gaseous effluent discharges complied with existing discharge authorizations and relevant environmental regulations. Potential effective doses to the general public from controlled airborne discharges from HIFAR were estimated utilising the PC-Cream atmospheric dispersion and dosimetry code. The potential effective dose to the public was estimated to be less than 0.010 mSv/year for all receptor locations on the 1.6 km buffer zone boundary around the HIFAR research reactor. This value represents 1% of the 1 mSv/year dose limit for long term exposure that is recommended by the National Health and Medical Research Council and 10% of the HIFAR dose constraint of 0.1 mSv/year

  7. Population pharmacokinetics of rifampicin, pyrazinamide and isoniazid in children with tuberculosis: in silico evaluation of currently recommended doses.

    Science.gov (United States)

    Zvada, Simbarashe P; Denti, Paolo; Donald, Peter R; Schaaf, H Simon; Thee, Stephanie; Seddon, James A; Seifart, Heiner I; Smith, Peter J; McIlleron, Helen M; Simonsson, Ulrika S H

    2014-05-01

    To describe the population pharmacokinetics of rifampicin, pyrazinamide and isoniazid in children and evaluate the adequacy of steady-state exposures. We used previously published data for 76 South African children with tuberculosis to describe the population pharmacokinetics of rifampicin, pyrazinamide and isoniazid. Monte Carlo simulations were used to predict steady-state exposures in children following doses in fixed-dose combination tablets in accordance with the revised guidelines. Reference exposures were derived from an ethnically similar adult population with tuberculosis taking currently recommended doses. The final models included allometric scaling of clearance and volume of distribution using body weight. Maturation was included for clearance of isoniazid and clearance and absorption transit time of rifampicin. For a 2-year-old child weighing 12.5 kg, the estimated typical oral clearances of rifampicin and pyrazinamide were 8.15 and 1.08 L/h, respectively. Isoniazid typical oral clearance (adjusted for bioavailability) was predicted to be 4.44, 11.6 and 14.6 L/h for slow, intermediate and fast acetylators, respectively. Higher oral clearance values in intermediate and fast acetylators also resulted from 23% lower bioavailability compared with slow acetylators. Simulations based on our models suggest that with the new WHO dosing guidelines and utilizing available paediatric fixed-dose combinations, children will receive adequate rifampicin exposures when compared with adults, but with a larger degree of variability. However, pyrazinamide and isoniazid exposures in many children will be lower than in adults. Further studies are needed to confirm these findings in children administered the revised dosages and to optimize pragmatic approaches to dosing.

  8. Draft Air Pathway Report: Phase 1 of the Hanford Environmental Dose Reconstruction Project

    Energy Technology Data Exchange (ETDEWEB)

    1990-07-20

    This report summarizes the air pathway portion of the first phase of the Hanford Environmental Dose Reconstruction (HEDR) Project, conducted by Battelle staff at the Pacific Northwest Laboratory under the direction of an independent Technical Steering Panel. The HEDR Project is estimating historical radiation doses that could have been received by populations near the Department of Energy's Hanford Site, in southeastern Washington State. Phase 1 of the air-pathway dose reconstruction sought to determine whether dose estimates could be calculated for populations in the 10 counties nearest the Hanford Site from atmospheric releases of iodine-131 from the site from 1944--1947. Phase 1 demonstrated the following: HEDR-calculated source-term estimates of iodine-131 releases to the atmosphere were within 20% of previously published estimates; calculated vegetation concentrations of iodine-131 agree well with previously published measurements; the highest of the Phase 1 preliminary dose estimates to the thyroid are consistent with independent, previously published estimates of doses to maximally exposed individuals; and relatively crude, previously published measurements of thyroid burdens for Hanford workers are in the range of average burdens that the HEDR model estimated for similar reference individuals'' for the period 1944--1947. 4 refs., 10 figs., 9 tabs.

  9. Environmental factors used for the estimation of radiation dose to thyroid gland

    International Nuclear Information System (INIS)

    Ohmomo, Yoichiro

    1976-01-01

    Environmental factors used for the estimation of radiation dose to thyroid gland were discussed in this paper, such as deposition velocity of radioactive iodine onto plant leaves, elimination factor from the leaves, transfer of this nuclide to milk and the consumption of those critical foods especially by inhabitants around nuclear sites in coastal area of Ibaraki Prefecture. Uptake of the stable iodine was estimated. (auth.)

  10. Announcement of a recommendation of the SSK (German Radiation Protection Commission)

    International Nuclear Information System (INIS)

    1986-01-01

    The SSK recommends the following: 1) The effective dose received through ingestion of milk or meat contaminated with Cs-134 and Cs-137 is negligibly small (0.05-0.15 mSv, or 5-15 mrem). In Southern Germany (as e.g. in the Tuebingen area, in Suebia, Lower and Upper Bavaria) the environmental exposure is higher, so that there, appropriate measures have to be taken with regard to animal feed and other processes in the food chain. 2) One should be very careful with mushrooms, especially cepes, collected in Southern Germany. 3) As to fresh water fish or seafish, normal amounts ingested will not lead to enhanced radiation exposure. 4) Despite the fact that game or venison from Southern Germany contains relatively high amounts of Cesium isotopes, the resulting effective dose received is negligibly small. Ingestion of 200 g of game with 1000 Bq Cs/kg will administer a dose of 0.003 mSv (0.3 mrem). (HP) [de

  11. 1990 recommendations of ICRP

    International Nuclear Information System (INIS)

    Clarke, R.H.

    1991-01-01

    The Main Commission of ICRP finalised its new recommendations during its November 1990 meeting. The recommendations will appear in the Annals of the ICRP in 1991 as Publication 60. This paper represents a personal summary of these recommendations. It covers the basic biological risk estimates and the conceptual framework of the system of radiological protection, the definition of radiation detriment and its use both in the definition of radiation quantities and in the establishment of the dose limits adopted by the Main Commissions. (author)

  12. Review of site recommendation process in Draft Environmental Assessments

    International Nuclear Information System (INIS)

    Joy, H.; Longo, T.; Burton, E.S.

    1985-01-01

    In December 1984, the US Department of Energy (DOE) published Draft Environmental Assessments (EAs) on nine potentially acceptable nuclear waste repository sites. Five sites in the states of Mississippi, Nevada, Texas, Utah, and Washington were proposed in the Draft EAs for nomination under the Nuclear Waste Policy Act as suitable for further detailed study (site characterization). The Nevada, Texas, and Washington sites were further proposed for recommendation to the President as preferred for site characterization. This paper reviews the process that DOE used in selecting the three sites proposed for site characterization. The process is consistent with DOE's implementation guidelines for selecting repository sites, and proceeds in three steps. First, the sites are ranked in order of preference for each of twenty technical guidelines based on information in the Draft EAs. The second step combines the individual guideline rankings into postclosure and preclosure guideline group rankings, and, finally, into an overall ranking. In the third step, the sensitivity of the choice of the three preferred sites is examined for a range of guideline weightings

  13. Status of ICRP recommendations at nuclear power plants

    International Nuclear Information System (INIS)

    Kaneko, Masahito

    1996-01-01

    Results of actual radiation exposure in nuclear power plants and related matters were presented for discussion of the principle of radiation protection involved in ICRP recommendations, which is prerequisite for safe operation of the plants and for treatment of radioactive waste. There were no personnel with actual exposure dose exceeding 50 mSv/y in 1995. Total exposure dose was 66.32 psn.Sv. and mean dose equivalent/personnel, 1.0 mSv. The amount of radioactive gasses and liquids released in the environment was far lower (<1/7,000) than that for the exposure index of 50 microSv/y in the public around the plant. The marked decrease in the amount of radioactive solid waste was noted in the plants. The laws and ICRP recommendations have been the basis for agreement between labor and management in the plant: e.g., the proposed voluntary dose was 30 mSv/y. This was also true for the recommendations in 1990. Finally, followings were proposed to ICRP: re-examination of linear theory without threshold, consideration for the balance between the radiation and other kind of hazardous materials and factors, carefulness in changing the recommendation concept, and exclusion of more severe limitations than those included in ICRP recommendations. (K.H.)

  14. Recommendations from gynaecological (GYN) GEC ESTRO working group (II): Concepts and terms in 3D image-based treatment planning in cervix cancer brachytherapy-3D dose volume parameters and aspects of 3D image-based anatomy, radiation physics, radiobiology

    International Nuclear Information System (INIS)

    Poetter, Richard; Haie-Meder, Christine; Limbergen, Erik van; Barillot, Isabelle; Brabandere, Marisol De; Dimopoulos, Johannes; Dumas, Isabelle; Erickson, Beth; Lang, Stefan; Nulens, An; Petrow, Peter; Rownd, Jason; Kirisits, Christian

    2006-01-01

    The second part of the GYN GEC ESTRO working group recommendations is focused on 3D dose-volume parameters for brachytherapy of cervical carcinoma. Methods and parameters have been developed and validated from dosimetric, imaging and clinical experience from different institutions (University of Vienna, IGR Paris, University of Leuven). Cumulative dose volume histograms (DVH) are recommended for evaluation of the complex dose heterogeneity. DVH parameters for GTV, HR CTV and IR CTV are the minimum dose delivered to 90 and 100% of the respective volume: D90, D100. The volume, which is enclosed by 150 or 200% of the prescribed dose (V150, V200), is recommended for overall assessment of high dose volumes. V100 is recommended for quality assessment only within a given treatment schedule. For Organs at Risk (OAR) the minimum dose in the most irradiated tissue volume is recommended for reporting: 0.1, 1, and 2 cm 3 ; optional 5 and 10 cm 3 . Underlying assumptions are: full dose of external beam therapy in the volume of interest, identical location during fractionated brachytherapy, contiguous volumes and contouring of organ walls for >2 cm 3 . Dose values are reported as absorbed dose and also taking into account different dose rates. The linear-quadratic radiobiological model-equivalent dose (EQD 2 )-is applied for brachytherapy and is also used for calculating dose from external beam therapy. This formalism allows systematic assessment within one patient, one centre and comparison between different centres with analysis of dose volume relations for GTV, CTV, and OAR. Recommendations for the transition period from traditional to 3D image-based cervix cancer brachytherapy are formulated. Supplementary data (available in the electronic version of this paper) deals with aspects of 3D imaging, radiation physics, radiation biology, dose at reference points and dimensions and volumes for the GTV and CTV (adding to [Haie-Meder C, Poetter R, Van Limbergen E et al

  15. National Recommended Water Quality Criteria

    Data.gov (United States)

    U.S. Environmental Protection Agency — The National Recommended Water Quality Criteria is a compilation of national recommended water quality criteria for the protection of aquatic life and human health...

  16. Standardized dose factors for dose calculations - 1982 SRP reactor safety analysis report tritium, iodine, and noble gases

    International Nuclear Information System (INIS)

    Pillinger, W.L.; Marter, W.L.

    1982-01-01

    Standardized dose constants are recommended for calculation of offsite doses in the 1982 SRP Reactor Safety Analysis Report (SAR). Dose constants are proposed for inhalation of tritium and radioiodines and for submersion in a semi-infinite cloud of radioiodines and noble gases. The proposed constants, based on ICRP2 methodology for internal dose and methodology recommended by the US Nuclear Regulatory Commission for external dose, are compatible with dose calculational methods used at the Savannah River Plant and Savannah River Laboratory for normal releases of radioactivity. 8 references

  17. An Internal Dose Assessment Associated with Personal Food Intake

    Energy Technology Data Exchange (ETDEWEB)

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

    2015-10-15

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

  18. The patient dose survey and dose reduction in diagnostic radiology

    International Nuclear Information System (INIS)

    Dang Thanh Luong; Duong Van Vinh; Ha Ngoc Thach

    2000-01-01

    This paper presented the results of the patient dose survey in some hospitals in Hanoi from 1995 to 1997. The main investigated types of the X-ray examination were: Chest PA, LAT; Skull PA/AP, LAT; Lumbar spine AP, LAT; and Pelvis AP. The fluctuation of the entrance surface doses (ESD) was too large, even in the same type of X-ray examination and X-ray facility. It was found that the ratio of maximum and minimum ESD were ranged from 1.5 to 18. The mean values of ESD for chest and skull were higher than CEC recommended values, while the mean values of lumbar spine and pelvis were smaller than that of CEC recommended values. The result of dose intercomparison was also reported. Some methods of dose reduction were applied for improving the patient dose in X-ray departments such as a high kV technique, high sensitive screen-film combination. (author)

  19. Recommendations of ICRP for radiation protection in 2005

    International Nuclear Information System (INIS)

    Holm, L. E.

    2004-01-01

    The present recommendations of the International Commission on Radiological Protection (ICRP) were published in 1991, and since then, the ICRP has provided additional recommendations. The system of protection has become increasingly co plex with time, and the Commission has decided to adopt a new set of recommendations in 2005- These should be seen as a consolidation of earlier recommendations. The new recommendations will recognize where the responsibility for justifying the introduction of a new practice lies, maintain the existing dose limits for individuals, develop the concept of dose constraints, require optimisation of protection from any source to ensure that exposures are as law as reasonably achievable, include of a policy for protection of non-human species, and clarify the dramatics quantities. The Commission intends to adopt the new recommendations in 2005, and this will be 15 years after the current recommendations were adopted. (Author) 13 refs

  20. Annual environmental monitoring report, 1974

    International Nuclear Information System (INIS)

    Stephens, L.D.; Cantelow, H.

    1975-04-01

    The Lawrence Berkeley Laboratory, a large multi-disciplinary research institute, is located in the hills above the University of California and the City of Berkeley. Nuclear Physics and Nuclear Chemistry research are the main contributors to the environmental radiation. In order to pursue this research effort, large particle accelerators have been built and are operated almost continuously. Other research may also involve the use of radioisotopes. These research activities result in a small but finite population dose to the general population which works or resides in the area surrounding the Laboratory. The annual maximum permissible dose equivalent (MPD) for members of the general population is recommended to be 500 mrem, however, Laboratory policy is to keep the population exposure as low as practicable at all times. In order to assure that this is done, several environmental monitoring stations are maintained which continuously telemeter radiation information to a central location. This information is presented here along with studies of the population distribution, in order to provide a total man-rem estimate. Using the data in this report the population dose due to laboratory operation ranges from 0.4 percent to 5.7 percent of the MPD. (U.S.)

  1. Basic concepts and assumptions behind the ICRP recommendations

    International Nuclear Information System (INIS)

    Lindell, B.

    1981-03-01

    The paper gives a review of the current radiation protection recommendations by the International Commission on Radiological Protection (ICRP). It discusses concepts like stochastic effects, radiation detriments, collective dose, dose equivalent and dose limits. (G.B.)

  2. Selection of dominant radionuclides for Phase 1 of the Hanford Environmental Dose Reconstruction Project

    Energy Technology Data Exchange (ETDEWEB)

    Napier, B.A.

    1991-07-01

    The objective of the Hanford Environmental Dose Reconstruction (HEDR) Project is to estimate the radiation dose that individuals could have received as a result of emissions from nuclear operations at Hanford since their inception in 1944. A vital step in the estimation of radiation doses is the determination of the source term,'' that is, the quantities of radionuclides that were released to the environment from the various Hanford operations. Hanford operations have at various times involved hundreds of different radionuclides, some in relatively large quantities. Those radionuclides present in the largest quantities, although significant from an operational handling point of view, may not necessarily have been those of greatest concern for offsite radiation dose. This report documents the selection of the dominant radionuclides (those that may have resulted in the largest portion of the received doses) in the source term for Phase 1 of the HEDR Project, that is, for atmospheric releases from 1944 through 1947 and for surface water releases from 1964 through 1966. 15 refs., 3 figs., 10 tabs.

  3. Environmental and effluent monitoring at Lucas Heights Science and Technology Centre, 1997

    Energy Technology Data Exchange (ETDEWEB)

    Hoffmann, E L; Loosz, T; Farrar, Y

    1998-11-01

    Results are presented of environmental and effluent monitoring conducted in the vicinity of the Lucas Heights Science and Technology Centre (LHSTC) during 1997. All low-level liquid and gaseous effluent discharges complied with existing discharge authorizations and relevant environmental regulations. Potential effective doses to the general public from controlled airborne discharges from HIFAR were estimated utilising the PC-Cream atmospheric dispersion and dosimetry code. The potential effective dose to the public was estimated to be less than 0.010 mSv/year for all receptor locations on the 1.6 km buffer zone boundary around the HIFAR research reactor. This value represents 1% of the 1 mSv/year dose limit for long term exposure that is recommended by the National Health and Medical Research Council and 10% of the HIFAR dose constraint of 0.1 mSv/year 24 tabs., 7 figs.; Glossary; Appendices

  4. Environmental policy. Ambient radioactivity levels and radiation doses in 1998

    International Nuclear Information System (INIS)

    1999-11-01

    The report contains information on the natural (background) radiation exposure (chapter II), the natural radiation exposure as influenced by anthropogenic effects (chapter III), the anthropogenic radiation exposure (chapter IV), and the radiation doses to the environment and the population emanating from the Chernobyl fallout (chapter V). The natural radiation exposure is specified referring to the contributions from cosmic and terrestrial background radiation and intake of natural radioactive substances. Changes of the natural environment resulting from anthropogenic effects (technology applications) inducing an increase in concentration of natural radioactive substances accordingly increase the anthropogenic radiation exposure. Indoor air radon concentration in buildings for instance is one typical example of anthropogenic increase of concentration of natural radioactivity, primarily caused by the mining industry or by various materials processing activities, which may cause an increase in the average radiation dose to the population. Measurements so far show that indoor air concentration of radon exceeds a level of 200 Bq/m 3 in less than 2% of the residential buildings; the EUropean Commission therefore recommends to use this concentration value as a maximum value for new residential buildings. Higher concentrations are primarily measured in areas with relevant geological conditions and abundance of radon, or eg. in mining areas. (orig./CB) [de

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

    International Nuclear Information System (INIS)

    Raskob, W.; Barry, P.

    1997-01-01

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

  6. Dose specification for radiation therapy: dose to water or dose to medium?

    International Nuclear Information System (INIS)

    Ma, C-M; Li Jinsheng

    2011-01-01

    The Monte Carlo method enables accurate dose calculation for radiation therapy treatment planning and has been implemented in some commercial treatment planning systems. Unlike conventional dose calculation algorithms that provide patient dose information in terms of dose to water with variable electron density, the Monte Carlo method calculates the energy deposition in different media and expresses dose to a medium. This paper discusses the differences in dose calculated using water with different electron densities and that calculated for different biological media and the clinical issues on dose specification including dose prescription and plan evaluation using dose to water and dose to medium. We will demonstrate that conventional photon dose calculation algorithms compute doses similar to those simulated by Monte Carlo using water with different electron densities, which are close (<4% differences) to doses to media but significantly different (up to 11%) from doses to water converted from doses to media following American Association of Physicists in Medicine (AAPM) Task Group 105 recommendations. Our results suggest that for consistency with previous radiation therapy experience Monte Carlo photon algorithms report dose to medium for radiotherapy dose prescription, treatment plan evaluation and treatment outcome analysis.

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

    International Nuclear Information System (INIS)

    1989-01-01

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

  8. The environmental impact of reprocessing

    International Nuclear Information System (INIS)

    Mummery, P.W.; Howells, H.; Scriven, A.

    1980-01-01

    The subject is discussed under the headings: introduction; basis of hazard assessment (dose limits - ICRP recommendations; biological radiation effects); comparison of standards and practice in the UK and USA in the limitation of exposure of the public as a consequence of discharges of radioactive effluent to the environment; nature of reprocessing operations (Thermal Oxide Fuel Reprocessing Plant (THORP); storage ponds; fuel shearing; leaching; clarification; solvent extraction; finishing); waste management (liquids, solids, gases); waste discharges; environmental impact of normal operations (identification of the critical groups; exposure of critical groups; risks and exposures, occupational and collective); environmental impact of accidents (risk - probability multiplied by consequence of the event; types of accident considered); conclusion. (U.K.)

  9. Environmental aspects and public exposure doses of airborne radioactive effluents from a PWR-power plant

    International Nuclear Information System (INIS)

    Song Miaofa; Zhang Jin; Fu Rongchu; Hu Yinxiu

    1989-04-01

    It is estimated that the environmental aspects and public exposure doses of airborne radioactive effluents from a imaginary 0.3 GW PWR-power plant which sited on the site of a large coalfired power plant estimated before. The major contributor to public exposure is found to be the release of 14 C and the critical pathway is food ingestion. A maximum annual individual body effective dose equivalent of 7.112 x 10 -6 Sv · (GW · a) -1 is found at the point of 0.5 km southeast of the source. The collective dose equivalent in the area around the plant within a radius of 100 km is to be 0.5974 man-Sv · a) -1 . Both maximum individual and collective effective dose equivalents of the PWR-power plant are much lower than those of the coal-fired one. If the ash emission ratio of the latter decreases from 24.6% to 1%, public exposure doses of the two plants would be nearly equal

  10. Integrated Task Plans for the Hanford Environmental Dose Reconstruction Project, FY 1992 through May 1994

    International Nuclear Information System (INIS)

    Shipler, D.B.

    1992-09-01

    The purpose of the Hanford Environmental Dose Reconstruction (HEDR) Project is to estimate radiation doses from Hanford Site operations since 1944 to populations and individuals. The primary objective of work to be performed through May 1994 is to (1) determine the project's appropriate scope (space, time, radionuclides, pathways and individuals/population groups), (2) determine the project's appropriate level of accuracy (level of uncertainty in dose estimates) for the project, (3) complete model and data development, and (4) estimate doses for the Hanford Thyroid Disease Study (HTDS), representative individuals, and special populations as described herein. The plan for FY 1992 through May 1994 has been prepared based on activities and budgets approved by the Technical Steering Panel (TSP) at its meetings on August 19--20, 1991, and April 23--25, 1992. The activities can be divided into four broad categories: (1) model and data evaluation activities, (2)additional dose estimates, (3) model and data development activities, and (4)technical and communication support

  11. The calculation of dose from external photon exposures using reference human phantoms and Monte Carlo methods. Pt. 7. Organ doses due to parallel and environmental exposure geometries

    Energy Technology Data Exchange (ETDEWEB)

    Zankl, M. [GSF - Forschungszentrum fuer Umwelt und Gesundheit Neuherberg GmbH, Oberschleissheim (Germany). Inst. fuer Strahlenschutz; Drexler, G. [GSF - Forschungszentrum fuer Umwelt und Gesundheit Neuherberg GmbH, Oberschleissheim (Germany). Inst. fuer Strahlenschutz; Petoussi-Henss, N. [GSF - Forschungszentrum fuer Umwelt und Gesundheit Neuherberg GmbH, Oberschleissheim (Germany). Inst. fuer Strahlenschutz; Saito, K. [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan)

    1997-03-01

    This report presents a tabulation of organ and tissue equivalent dose as well as effective dose conversion coefficients, normalised to air kerma free in air, for occupational exposures and environmental exposures of the public to external photon radiation. For occupational exposures, whole-body irradiation with idealised geometries, i.e. broad parallel beams and fully isotropic radiation incidence, is considered. The directions of incidence for the parallel beams are anterior-posterior, posterior-anterior, left lateral, right lateral and a full 360 rotation around the body`s longitudinal axis. The influence of beam divergence on the body doses is also considered as well as the dependence of effective dose on the angle of radiation incidence. Regarding exposure of the public to environmental sources, three source geometries are considered: exposure from a radioactive cloud, from ground contamination and from the natural radionuclides distributed homogeneously in the ground. The precise angular and energy distributions of the gamma rays incident on the human body were taken into account. The organ dose conversion coefficients given in this catalogue were calculated using a Monte Carlo code simulating the photon transport in mathematical models of an adult male and an adult female, respectively. Conversion coefficients are given for the equivalent dose of 23 organs and tissues as well as for effective dose and the equivalent dose of the so-called `remainder`. The organ equivalent dose conversion coefficients are given separately for the adult male and female models and - as arithmetic mean of the conversion coefficients of both - for an average adult. Fitted data of the coefficients are presented in tables; the primary raw data as resulting from the Monte Carlo calculation are shown in figures together with the fitted data. (orig.)

  12. The calculation of dose from external photon exposures using reference human phantoms and Monte Carlo methods. Pt. 7. Organ doses due to parallel and environmental exposure geometries

    International Nuclear Information System (INIS)

    Zankl, M.

    1997-03-01

    This report presents a tabulation of organ and tissue equivalent dose as well as effective dose conversion coefficients, normalised to air kerma free in air, for occupational exposures and environmental exposures of the public to external photon radiation. For occupational exposures, whole-body irradiation with idealised geometries, i.e. broad parallel beams and fully isotropic radiation incidence, is considered. The directions of incidence for the parallel beams are anterior-posterior, posterior-anterior, left lateral, right lateral and a full 360 rotation around the body's longitudinal axis. The influence of beam divergence on the body doses is also considered as well as the dependence of effective dose on the angle of radiation incidence. Regarding exposure of the public to environmental sources, three source geometries are considered: exposure from a radioactive cloud, from ground contamination and from the natural radionuclides distributed homogeneously in the ground. The precise angular and energy distributions of the gamma rays incident on the human body were taken into account. The organ dose conversion coefficients given in this catalogue were calculated using a Monte Carlo code simulating the photon transport in mathematical models of an adult male and an adult female, respectively. Conversion coefficients are given for the equivalent dose of 23 organs and tissues as well as for effective dose and the equivalent dose of the so-called 'remainder'. The organ equivalent dose conversion coefficients are given separately for the adult male and female models and - as arithmetic mean of the conversion coefficients of both - for an average adult. Fitted data of the coefficients are presented in tables; the primary raw data as resulting from the Monte Carlo calculation are shown in figures together with the fitted data. (orig.)

  13. Environmental monitoring for radioactivity in Scotland, 1983 to 1987

    International Nuclear Information System (INIS)

    1989-01-01

    This bulletin, which has been prepared by Her Majesty's Industrial Pollution Inspectorate (HMIPI) of the Scottish Development Department (SDD), contains a summary of the environmental monitoring for radioactivity carried out in Scotland as part of the statutory procedure for ensuring the safety of radioactive waste disposals from nuclear facilities. The results presented cover the period 1983 to 1987. The first section of the bulletin draws together the results of the monitoring and presents the principal conclusions; the second section summarises the procedures underlying the monitoring; and the remaining sections present detailed monitoring results. The principal conclusions of this bulletin are that: public radiation exposure in Scotland from environmental radioactivity arising from radioactive waste disposal has been well within the internationally recommended limits including the ICRP's recommended principal limit of 1 millisievert per year; the levels of radiation exposure have been consistent with the recommendation of the NRPB that procedures leading to exposure of the public should be controlled so that the life-time effective dose equivalent does not exceed 70 millisieverts; any doses received have been small and correspond to negligible levels of risk to individuals; and the effects of waste disposals have been limited in accordance with the national standards of radiological safety, which are designed to protect the population from the harmful effects of radiation. (author)

  14. Derivation of recommended limits for radionuclide contamination of foods by the FAO

    International Nuclear Information System (INIS)

    Wirth, E.; Mueller, M.K.

    1986-01-01

    As a consequence of the reactor accident at Chernobyl, USSR, various countries defined limits for radioactive contamination of foods at different levels. These limits ranged from a few Bq iodine 131 or cesium 134 + 137/kg (Malaysia and Canada) to more than 1000 Bq/kg (Great Britain and France). These variations in limits hindered the movement of foods in international trade. For this reason the FAO convened an Expert Consultation to derive 'action levels' below which neither intervention nor constraint would be justified in terms of international movement and trade in food and drink. These limits are to find application in cases of widespread environmental contamination after an accidental release of radionuclides. They are not to be applied in cases of local release, e.g. in the vicinity of nuclear facilities. The derivation of 'action levels' by the FAO was based on the recommendations issued by the International Commission of Radiological Protection (ICRP) in May 1985. According to this recommendation the committed dose equivalent for the whole body should not exceed 5 mSv in the first and 1 mSv in the consecutive years. For radionuclides that preferentially irradiate individual organs, e.g. I131 in the thyroid, the dose equivalent to a specified organ may be used to derive limiting values. For individual organs limiting doses of 50 mSv/a and 10 mSv/a respectively were chosen

  15. Derivation of recommended limits for radionuclide contamination of foods by the FAO

    Energy Technology Data Exchange (ETDEWEB)

    Wirth, E; Mueller, M K [Institute for Radiation Hygiene, Federal Health Office, Neuherberg (Germany)

    1986-07-01

    As a consequence of the reactor accident at Chernobyl, USSR, various countries defined limits for radioactive contamination of foods at different levels. These limits ranged from a few Bq iodine 131 or cesium 134 + 137/kg (Malaysia and Canada) to more than 1000 Bq/kg (Great Britain and France). These variations in limits hindered the movement of foods in international trade. For this reason the FAO convened an Expert Consultation to derive 'action levels' below which neither intervention nor constraint would be justified in terms of international movement and trade in food and drink. These limits are to find application in cases of widespread environmental contamination after an accidental release of radionuclides. They are not to be applied in cases of local release, e.g. in the vicinity of nuclear facilities. The derivation of 'action levels' by the FAO was based on the recommendations issued by the International Commission of Radiological Protection (ICRP) in May 1985. According to this recommendation the committed dose equivalent for the whole body should not exceed 5 mSv in the first and 1 mSv in the consecutive years. For radionuclides that preferentially irradiate individual organs, e.g. I131 in the thyroid, the dose equivalent to a specified organ may be used to derive limiting values. For individual organs limiting doses of 50 mSv/a and 10 mSv/a respectively were chosen.

  16. A system for environmental protection. Reference dose models for fauna and flora

    International Nuclear Information System (INIS)

    Pentreath, R.J.; Woodhead, D.S.

    2000-01-01

    Ideas have already been published on how the current problems relating to environmental protection could be explicitly addressed. One of the basic cornerstones of the proposed system is that of the use of reference dose models for fauna and flora, in a manner analogous to those used for the human species. The concept is that, for a number of both aquatic and terrestrial fauna and flora types, 'reference' dose models, and dose per unit (internal and external) exposure tables, could be compiled. These would then be used to draw broad conclusions on the likely effects for such organisms in relation to three broad environment end points of concern: life shortening; impairment of reproductive capacity; and scorable, cytogenetic damage. The level of complexity of the dose models needs to be commensurate with the morphological complexity of the modelled organism, its size, and the data bases which are either available or could be reasonably obtained. The most basic models considered are either solid ellipsoids or spheres, with fixed dimensions. Secondary models contain internal, but relatively simple geometric features representative of those key organs or tissues for which more precise estimates of dose are required. Their level of complexity is also a function of different internal and external sources of radiation, and expected differences in radiosensitivities. Tertiary models -of greater complexity- are only considered to be of value for higher vertebrates. The potential derivation and use of all three sets of models is briefly discussed. (author)

  17. Implication of new CEC recommendations for individual monitoring for external radiation doses to the skin and the extremities

    DEFF Research Database (Denmark)

    Christensen, P.; Julius, H.W.; Marshall, T.O.

    1991-01-01

    A drafting group consisting of the above authors has assisted the CEC in revising the CEC document Technical Recommendations for Monitoring the Exposure to Individuals to External Radiation, EUR 5287, published in 1975. The paper highlights sections of the revised version relating particularly...... to irradiation of the skin and the extremities and focusses on problems connected to exposure to weakly penetrating radiations. Concepts of individual monitoring for external radiation exposures to the skin of the whole body and to the extremities are discussed and guidance is given as regards dose quantities...

  18. Use of the pre-dose technique for environmental dosimetry. [Thermoluminescence from fired bricks or tiles

    Energy Technology Data Exchange (ETDEWEB)

    Bailiff, I K [Durham Univ. (UK). TL Lab.; Haskell, E H [Utah Univ., Salt Lake City (USA). Radiobiology Div.

    1984-01-01

    The pre-dose effect associated with the 110/sup 0/C TL peak of quartz is the basis of a dating technique developed at the Oxford Laboratory, and now in use to date pottery and brick at the Durham Laboratory. Recently its use for the measurement of fallout gamma dose has been initiated at the University of Utah. Using quartz extracted from fired brick, the technique has been shown to be sufficiently sensitive to measure doses in the region of 10 mGy. The complexities of the technique encountered during dating in its upper range (approx. 5 Gy) are equally apparent in its lower range (10 mGy). With a common interest in the pre-dose technique, the research that is being performed to apply the technique through its full range in environmental dosimetry is discussed.

  19. Uncertainty and power at low levels of incurred radiation dose

    International Nuclear Information System (INIS)

    Wilson, M; Jackson, D

    2005-01-01

    It is common practice when calculating dose to exposed populations to average the variables that go into the dose calculation (e.g. environmental concentrations, air kerma, consumption rates, occupancy rates). This approach is simple and can be useful where data are obtained over different periods (weekly, monthly, quarterly), where samples may be bulked for some analyses but not others and where gaps in the data are present. However, such an approach does not yield information on the degree of uncertainty around the average dose calculated. An alternative approach is to estimate the dose to each individual and to obtain an average from this data set, which can then also be used to derive a measure of uncertainty around the central dose estimate. In this study, we demonstrate the variability in dose estimates using a hypothetical data set and consider the implications for sample size to achieve fixed confidence or resolving power. We recommend calculating the dose to every individual sampled, in order both to obtain the average dose and to estimate its variability. We argue that it is best practice to obtain information as complete as possible from the available sample of individuals

  20. Development of autonomous gamma dose logger for environmental monitoring.

    Science.gov (United States)

    Jisha, N V; Krishnakumar, D N; Surya Prakash, G; Kumari, Anju; Baskaran, R; Venkatraman, B

    2012-03-01

    Continuous monitoring and archiving of background radiation levels in and around the nuclear installation is essential and the data would be of immense use during analysis of any untoward incidents. A portable Geiger Muller detector based autonomous gamma dose logger (AGDL) for environmental monitoring is indigenously designed and developed. The system operations are controlled by microcontroller (AT89S52) and the main features of the system are software data acquisition, real time LCD display of radiation level, data archiving at removable compact flash card. The complete system operates on 12 V battery backed up by solar panel and hence the system is totally portable and ideal for field use. The system has been calibrated with Co-60 source (8.1 MBq) at various source-detector distances. The system is field tested and performance evaluation is carried out. This paper covers the design considerations of the hardware, software architecture of the system along with details of the front-end operation of the autonomous gamma dose logger and the data file formats. The data gathered during field testing and inter comparison with GammaTRACER are also presented in the paper. AGDL has shown excellent correlation with energy fluence monitor tuned to identify (41)Ar, proving its utility for real-time plume tracking and source term estimation.

  1. Measurement of the environmental radiation dose due to the accident at the Fukushima Daiichi Nuclear Power Plant

    International Nuclear Information System (INIS)

    Yamamoto, Tomoaki; Muroi, Kenzo; Maruyama, Sumito; Koike, Takahisa; Matsuda, Marina; Katsumata, Kenichiro

    2013-01-01

    On March 11, 2011, an undersea megathrust earthquake caused a tsunami that inflicted serious damage to the Fukushima Daiichi Nuclear Power Plant (FDNPP). On March 12, 2011, we began measuring environmental radiation doses and identifying fission product radionuclides at the International University of Health and Welfare (IUHW). The purpose of this investigation is to estimate the external exposure dose of fission products from FDNPP. Measurements were performed between March 12 and August 31, 2011. A NaI(Tl) scintillation survey meter was used to measure the environmental radiation dose, and air dust samplers and a NaI(Tl) scintillation spectrum analyzer were used to identify radionuclides in the atmosphere and soil. For estimating external doses, three lifestyle groups were considered viz. students or office workers, business persons, and farmers or construction workers. Increasing doses were detected on March 15 around noon, and the doses peaked on March 16. Post-peak, the doses decreased exponentially and became stable after two months. Immediately after the accident, some fission product radionuclides were detected in the atmosphere and in the soil samples. Almost no radionuclides were detected in the atmosphere approximately one month after the first analysis; although the radiation was decaying, radionuclides were detected in the soil and were isolated. The external dose varied with the supposed lifestyle; assuming that the abundance ratio of Cs-134 to Cs-137 was 1:1, the annual external doses for the considered lifestyles were 1.069 mSv for students or office workers, 1.672 mSv for business persons, and 2.044 mSv for farmers or construction workers. These doses are sufficiently small so that most residents including children, living near IUHW, would not be affected. Further investigation of the internal exposure is necessary for a better estimate of the effective doses. External exposure to fission product radionuclides is within safe levels, and while

  2. A review of radiology staff doses and dose monitoring requirements

    International Nuclear Information System (INIS)

    Martin, C. J.

    2009-01-01

    Studies of radiation doses received during X-ray procedures by radiology, cardiology and other clinical staff have been reviewed. Data for effective dose (E), and doses to the eyes, thyroid, hands and legs have been analysed. These data have been supplemented with local measurements to determine the most exposed part of the hand for monitoring purposes. There are ranges of 60-100 in doses to individual tissues reported in the literature for similar procedures at different centres. While ranges in the doses per unit dose-area product (DAP) are between 10 and 25, large variations in dose result from differences in the sensitivity of the X-ray equipment, the type of procedure and the operator technique, but protection factors are important in maintaining dose levels as low as possible. The influence of shielding devices is significant for determining the dose to the eyes and thyroid, and the position of the operator, which depends on the procedure, is the most significant factor determining doses to the hands. A second body dosemeter worn at the level of the collar is recommended for operators with high workloads for use in assessment of effective dose and the dose to the eye. It is proposed that the third quartile values from the distributions of dose per unit DAP identified in the review might be employed in predicting the orders of magnitude of doses to the eye, thyroid and hands, based on interventional operator workloads. Such dose estimates could be employed in risk assessments when reviewing protection and monitoring requirements. A dosemeter worn on the little finger of the hand nearest to the X-ray tube is recommended for monitoring the hand. (authors)

  3. Adduction of acrylamide with biomacromolecules at environmental dose level measured by accelerator mass spectrometry (AMS)

    International Nuclear Information System (INIS)

    Xie, Q.Y.; Sun, H.F.; Liu, Y.F.; Ding, X.F.; Fu, D.P.; Liu, K.X.

    2005-01-01

    Acrylamide (AA) is a well-known neurotoxin, which also has developmental, reproductive as well as genetic toxicity. AA has been classified as a probable human carcinogen by IARC in 1994 since its carcinogenic effects in animals were reported after repetitive high level dosing. Over the last 10 years, there have been a large number of studies investigating the effects of AA on rodent reproductive performance. In 2002, the Swedish Food Administration reported the presence of AA in the heat-treated food products. which again elicited great concern on the toxicity of AA. However most of these studies were investigated at a dose level of mg/kg b.w and above, which is much higher than the actual human relevant dose. In this study we investigate the adduction of environmental level AA with biomacromolecules by the ultra-sensitive AMS technique. This may provide some information on the reproductive toxicity of AA under extremely low level exposure. A series doses of [2, 3- 14 C] AA (0, 0.1, 1, 10, 100, 250, 1000 μg/kg bw) were administrated with a single intraperitoneal injection (i.p.) to ICR adult male mice. The blood and spermatozoon were collected 24 h post dosing. Hemoglobin (Hb), serum albumin (SA), protamine, spermatozoon DNA, spermatozoon head and tail were isolated respectively, and then transformed into graphite following our previous procedure, The adduct levels were determined by a 0.6 MV compact AMS facility at the Institute of Heavy Ion Physics of Peking University. The results indicate that: (1) AA adduct number increases with the doses within 0.1-1000 μg/kg b.w. range in a log/log linear mode, except for DNA within 10-1000 μg/kg b.w. range. (2) Comparing protamine, Hb, and SA adducts with that of spermatozoon DNA (see Fig. 1), AA mainly adducts to proteins. For instance, at 1000 μg/kg b.w. dose level, spermatozoon DNA adducts only account for about 0.71%, 1.36% and 0.82% of protamine, Hb and SA adducts, respectively. (3) AA-protamine adducts, AA

  4. The new ICRP recommendations

    International Nuclear Information System (INIS)

    Schlesinger, T.

    1977-01-01

    The new ICRP recommendations are based on the concept of risk. The doses received by workers have to be justified and kept as low as practically achievable. The acceptable annual occupational risk is of the order of 10 -4 . This corresponds to an average annual dose equivalent of about 5 mSv(0.5 Rem). The annual dose equivalent limit for whole body irradiation will remain 50 mSv/year (5 Rem/year) provided that the average is about 1/10th of this value. The concept of the critical organ is abandoned and is replaced by the concept of equidetriment. (author)

  5. Summary and recommendations of a National Cancer Institute workshop on issues limiting the clinical use of Monte Carlo dose calculation algorithms for megavoltage external beam radiation therapy

    International Nuclear Information System (INIS)

    Fraass, Benedick A.; Smathers, James; Deye, James

    2003-01-01

    Due to the significant interest in Monte Carlo dose calculations for external beam megavoltage radiation therapy from both the research and commercial communities, a workshop was held in October 2001 to assess the status of this computational method with regard to use for clinical treatment planning. The Radiation Research Program of the National Cancer Institute, in conjunction with the Nuclear Data and Analysis Group at the Oak Ridge National Laboratory, gathered a group of experts in clinical radiation therapy treatment planning and Monte Carlo dose calculations, and examined issues involved in clinical implementation of Monte Carlo dose calculation methods in clinical radiotherapy. The workshop examined the current status of Monte Carlo algorithms, the rationale for using Monte Carlo, algorithmic concerns, clinical issues, and verification methodologies. Based on these discussions, the workshop developed recommendations for future NCI-funded research and development efforts. This paper briefly summarizes the issues presented at the workshop and the recommendations developed by the group

  6. Environmental and effluent monitoring at ANSTO sites, 1999

    Energy Technology Data Exchange (ETDEWEB)

    Hoffman, E L; Loosz, T; Mokhber-Shahin, L

    1999-07-01

    Results are presented of environmental and effluent monitoring conducted in 1999 at the two sites owned and operated by ANSTO, at the Lucas Heights Science and Technology Centre (LHSTC) and the National Medical Cyclotron (NMC). All low-level liquid and gaseous effluent discharges complied with existing discharge authorisations and relevant environmental regulations. Potential effective doses to the general public from LHSTC controlled airborne discharges were estimated for 1999 using the PC-Cream atmospheric dispersion and dosimetry code. The potential effective doses to the public in 1999 were estimated to be less than 0.010 mSv/year for all receptor locations on the LHSTC 1.6 km buffer zone boundary or beyond. This value represents 1% of the I milli sievert (mSv) per year dose limit for long term exposure that is recommended by the National Health and Medical Research Council and 3.3% of the LHSTC site dose constraint of 0.3 mSv/year. It is concluded that there is no impact on the health of the community, staff or the environment as a consequence of operations at the Lucas Heights Science and Technology Centre or the National Medical Cyclotron (authors)

  7. Environmental and effluent monitoring at ANSTO sites 1999

    Energy Technology Data Exchange (ETDEWEB)

    Hoffmann, E L; Loosz, T; Mokhber-Shahin, L [Australian Nuclear Science and Technology Organisation (ANSTO), Lucas Heights, NSW, Australia, (Australia)

    2000-07-01

    Results are presented of environmental and effluent monitoring conducted in 1999 at the two sites owned and operated by ANSTO, at the Lucas Heights Science and Technology Centre (LHSTC) and the National Medical Cyclotron (NMC). All low-level liquid and gaseous effluent discharges complied with existing discharge authorisations and relevant environmental regulations. Potential effective doses to the general public from LHSTC controlled airborne discharges were estimated for 1999 using the PC-Cream atmospheric dispersion and dosimetry code. The potential effective doses to the public in 1999 were estimated to be less than 0.010 mSv/year for all receptor locations on the LHSTC 1.6 km buffer zone boundary or beyond. This value represents 1% of the 1 millisievert (mSv) per year dose limit for long term exposure that is recommended by the National Health and Medical Research Council and 3.3% of the LHSTC site dose constraint of 0.3 mSv/year. It is concluded that there is no impact on the health of the community, staff or the environment as a consequence of operations at the Lucas Heights Science and Technology Centre or the National Medical Cyclotron.

  8. Environmental and effluent monitoring at ANSTO sites, 2000

    Energy Technology Data Exchange (ETDEWEB)

    Hoffmann, E L; Loosz, T; Mokhber-Shahin, L [Australian Nuclear Science and Technology Organisation, Menai, NSW (Australia)

    2001-07-01

    Results are presented of environmental surveillance and effluent monitoring conducted in the calendar year 2000 at the two sites owned and operated by ANSTO, at the Lucas Heights Science and Technology Centre (LHSTC) and the National Medical Cyclotron (NMC). All low-level liquid and gaseous effluent discharges complied with existing discharge authorisations and relevant environmental regulations. Potential effective doses to the general public from LHSTC controlled airborne discharges were estimated for 2000 using the PC-Cream atmospheric dispersion and dosimetry code. The potential effective doses to the public in 2000 were estimated to be less than 0.01 mSv/year for all receptor locations on the LHSTC 1.6 km buffer zone boundary or beyond. This value represents 1 % of the 1 milli sievert (mSv) per year dose limit for long term exposure that is recommended by the National Health and Medical Research Council and 3.3% of the LHSTC site dose constraint of 0.3 mSv/year. It is concluded that there is no impact on the health of the community, staff or the environment as a consequence of operations at the Lucas Heights Science and Technology Centre or the National Medical Cyclotron.

  9. Environmental and effluent monitoring at ANSTO sites, 2000

    International Nuclear Information System (INIS)

    Hoffmann, E.L.; Loosz, T.; Mokhber-Shahin, L.

    2001-01-01

    Results are presented of environmental surveillance and effluent monitoring conducted in the calendar year 2000 at the two sites owned and operated by ANSTO, at the Lucas Heights Science and Technology Centre (LHSTC) and the National Medical Cyclotron (NMC). All low-level liquid and gaseous effluent discharges complied with existing discharge authorisations and relevant environmental regulations. Potential effective doses to the general public from LHSTC controlled airborne discharges were estimated for 2000 using the PC-Cream atmospheric dispersion and dosimetry code. The potential effective doses to the public in 2000 were estimated to be less than 0.01 mSv/year for all receptor locations on the LHSTC 1.6 km buffer zone boundary or beyond. This value represents 1 % of the 1 milli sievert (mSv) per year dose limit for long term exposure that is recommended by the National Health and Medical Research Council and 3.3% of the LHSTC site dose constraint of 0.3 mSv/year. It is concluded that there is no impact on the health of the community, staff or the environment as a consequence of operations at the Lucas Heights Science and Technology Centre or the National Medical Cyclotron

  10. Environmental and effluent monitoring at ANSTO sites 1999

    International Nuclear Information System (INIS)

    Hoffmann, E. L.; Loosz, T.; Mokhber-Shahin, L.

    2000-01-01

    Results are presented of environmental and effluent monitoring conducted in 1999 at the two sites owned and operated by ANSTO, at the Lucas Heights Science and Technology Centre (LHSTC) and the National Medical Cyclotron (NMC). All low-level liquid and gaseous effluent discharges complied with existing discharge authorisations and relevant environmental regulations. Potential effective doses to the general public from LHSTC controlled airborne discharges were estimated for 1999 using the PC-Cream atmospheric dispersion and dosimetry code. The potential effective doses to the public in 1999 were estimated to be less than 0.010 mSv/year for all receptor locations on the LHSTC 1.6 km buffer zone boundary or beyond. This value represents 1% of the 1 millisievert (mSv) per year dose limit for long term exposure that is recommended by the National Health and Medical Research Council and 3.3% of the LHSTC site dose constraint of 0.3 mSv/year. It is concluded that there is no impact on the health of the community, staff or the environment as a consequence of operations at the Lucas Heights Science and Technology Centre or the National Medical Cyclotron

  11. Environmental and effluent monitoring at ANSTO sites, 1999

    International Nuclear Information System (INIS)

    Hoffman, E.L.; Loosz, T.; Mokhber-Shahin, L.

    1999-01-01

    Results are presented of environmental and effluent monitoring conducted in 1999 at the two sites owned and operated by ANSTO, at the Lucas Heights Science and Technology Centre (LHSTC) and the National Medical Cyclotron (NMC). All low-level liquid and gaseous effluent discharges complied with existing discharge authorisations and relevant environmental regulations. Potential effective doses to the general public from LHSTC controlled airborne discharges were estimated for 1999 using the PC-Cream atmospheric dispersion and dosimetry code. The potential effective doses to the public in 1999 were estimated to be less than 0.010 mSv/year for all receptor locations on the LHSTC 1.6 km buffer zone boundary or beyond. This value represents 1% of the I milli sievert (mSv) per year dose limit for long term exposure that is recommended by the National Health and Medical Research Council and 3.3% of the LHSTC site dose constraint of 0.3 mSv/year. It is concluded that there is no impact on the health of the community, staff or the environment as a consequence of operations at the Lucas Heights Science and Technology Centre or the National Medical Cyclotron (authors)

  12. 1986 annual site environmental report for Argonne National Laboratory

    International Nuclear Information System (INIS)

    Golchert, N.W.; Duffy, T.L.

    1987-03-01

    The results of the environmental monitoring program at Argonne National Laboratory (ANL) for 1986 are presented and discussed. To evaluate the effect of Argonne operations on the environment, measurements were made for a variety of radionuclides in air, surface water, ground water, soil, grass, bottom sediment, and milk; of the environmental penetrating radiation dose; and for a variety of chemical constituents in surface water, ground water, and Argonne effluent water. Sample collections and measurements were made on the site, at the site boundary, and off the Argonne site for comparison purposes. The results of the program are interpreted in terms of the sources and origin of the radioactive and chemical substances (natural, fallout, Argonne, and other) and are compared with applicable environmental quality standards. A US Department of Energy (DOE) dose calculation methodology based on recent International Commission on Radiological Protection (ICRP) recommendations is required and used in this report. The radiation dose to off-site population groups is estimated. The average concentrations and total amounts of radioactive and chemical pollutants released by Argonne to the environment were all below appropriate standards. 21 refs., 7 figs., 52 tabs

  13. Critical evaluation of the nonradiological environmental technical specifications. Program description, summary, and recommendations. Vol. 1

    International Nuclear Information System (INIS)

    Adams, S.M.; Cunningham, P.A.; Gray, D.D.; Kumar, K.D.; Witten, A.J.

    1976-01-01

    A comprehensive study of the data collected as part of the environmental Technical Specifications program for eight nuclear power plants was conducted for the Office of Nuclear Regulatory Research of the U.S. Nuclear Regulatory commission. This report includes a summary of the screening phase in which the adequacy of the hydrothermal and ecological monitoring data for each plant were evaluated, and the summary and recommendations resulting from a detailed examination of the three nuclear power plants selected in the initial screening

  14. Vancomycin Utilization Evaluation: Are We Dosing Appropriately?

    Directory of Open Access Journals (Sweden)

    Ladan Ayazkhoo

    2015-10-01

    Full Text Available Background: Inappropriate use of vancomycin not only increase health care costs but also contribute to the emergence of resistant organisms. Higher trough serum vancomycin concentrations (>10mg/L has been recommended for avoidance of development of resistance. We aim to compare the administered dose with recommended doses based on guideline-recommended weight-based dosing.Methods: In a cross sectional study, all patients who received vancomycin between July and October 2013, in infectious disease, internal medicine wards and emergency department of a teaching hospital in Tehran, Iran were entered to the study. Indication of vancomycin and necessary data for dose calculation including height and serum creatinine were recorded. Prescribed doses were compared with recommended doses in guidelines and calculated Glomerular filtration rate (GFR for each patient.Results: One hundred and four patients (45 females and 59 males recruited in the study. Our results indicated that, from all administered doses of vancomycin, 64.4% and 88.8% differs significantly (more than 20% based on American Pharmacist Association (AphA vancomycin monograph and guideline-recommended, weight-based vancomycin dosing (for adults, respectively.Conclusion: Underdosing of vancomycin is a major risk factor for developing resistance of gram positive organisms to this glycopeptide. Our results showed that more than half of patients receiving vancomycin are in the risk of low drug levels based on guidelines. So, having a comprehensive plan for the proper use of this drug especially designing effective internal guidelines can prevent emergence of resistance to vancomycin in future.

  15. Cervical cancer: intracavitary dose specification and prescription

    International Nuclear Information System (INIS)

    Potish, R.A.; Gerbi, B.J.

    1987-01-01

    Dose and volume specifications for reporting intracavitary therapy were analyzed according to criteria recommended by the International Commission on Radiation Units and Measurements (ICRU). Ninety Fletcher-Suit radium applications were studied to examine the validity of the assumptions of the ICRU and the merit of their routine reporting. It was demonstrated that the reporting recommendations were inconsistent with clinical prescription systems and added little to dose specification. The distinction between dose specification and dose prescription was stressed

  16. Recommendations for equipment requirements and specifications for digital and interventional radiology: Dosimetric aspects

    International Nuclear Information System (INIS)

    Suliman, I.I.; Zoetelief, J.

    2002-01-01

    The recognition of radiation induced injuries from fluoroscopically guided interventional procedures has resulted in the current demand for development of recommendations and standards to limit dose to both patients and staff. This paper outlines the recommendations drafted within the framework of European Project DIMOND III. The actual work involves survey and review of national and international documents as well as scientific publications in areas relevant to the digital and/or interventional radiology with an aim of developing recommendations for equipment requirements and specifications for digital and interventional radiology. A pilot study of experimental investigations in at least three hospitals will be conducted to test the requirements and the specifications, the result of which will be presented. The recommendations are expected to provide an effective means of dose reduction to both patients and staff while maintaining image quality adequate for the specific diagnosis or interventional procedure. Different components of x-ray systems that have direct impact on patient and staff doses have been considered. Where necessary a compromise between patient dose and image quality has been made. The dosimetric aspects of the recommendations propose detailed descriptions and limits to dosimetric information relevant to patient and staff doses. International recommendations on maximum patient entrance surface dose rate vary in the range from 25 to 65 mGy.min -1 for normal mode fluoroscopy. Maximum image intensifier or image receptor input dose rate around 0.1 Gy min -1 at a distance 30 cm from the image intensifier input surface has been generally recommended. Maximum fluoroscopic dose rate in air must not exceed 50 mGy.min -1 at a location depending on the configuration e.g. for undertable x-ray tube at 10 mm from the patient support on the patient side of the support. The use of pulsed fluoroscopy or low dose fluoroscopy is proposed as good options to minimize

  17. Current Trends in Radiation Protection Recommendations

    International Nuclear Information System (INIS)

    Gomaa, M.A.

    2008-01-01

    The third generation of the ICRP recommendations was adopted in April 2007. The recommendations rely on situations (planned, emergency and existing), individual (occupational, public and patient) and radiation protection system (justification, optimization and dose limits). In the present work attention is paid to discuss the new recommendations and role of IAEA in updating its Basic Safety Standards for protection against ionizing radiation and safety of radiation sources and its impact for the national regulations

  18. 2016 updated MASCC/ESMO consensus recommendations

    DEFF Research Database (Denmark)

    Einhorn, Lawrence H; Rapoport, Bernardo; Navari, Rudolph M

    2017-01-01

    PURPOSE: This review summarizes the recommendations for the prophylaxis of acute and delayed nausea and vomiting induced by multiple-day chemotherapy, high-dose chemotherapy, and breakthrough nausea and vomiting as agreed at the MASCC/ESMO Antiemetic Guidelines update meeting in Copenhagen in June...... receiving high-dose chemotherapy with stem cell transplant, a combination of a 5-HT3 receptor antagonist with dexamethasone and aprepitant (125 mg orally on day 1 and 80 mg orally on days 2 to 4) is recommended before chemotherapy. For patients undergoing multiple-day chemotherapy-induced nausea...... and vomiting, a 5-HT3 receptor antagonist, dexamethasone, and aprepitant, are recommended before chemotherapy for the prophylaxis of acute emesis and delayed emesis. For patients experiencing breakthrough nausea and vomiting, the available evidence suggests the use of 10 mg oral olanzapine, daily for 3 days...

  19. The recommendations of the International Commission on Radiological Protection

    International Nuclear Information System (INIS)

    Vennart, J.

    1983-01-01

    The most recent recommendations of the International Commission on Radiological Protection in its Publication 26 differ from all those made earlier by being based quantitatively on the risk of deleterious effects. Two types of effect are considered: stochastic and non-stochastic effects. The recommended dose limits are designed to avoid non-stochastic effects and reduce the risks of stochastic effects to acceptable values. The dose equivalent limits are only part of a much wider system that requires justification for the use of sources of ionizing radiation and consideration of costs and benefits to ensure that doses are kept as low as reasonably achievable. Annual Limits for Intakes (ALIs) of radionuclides by workers are recommended in ICRP Publication 30 and the dosimetric models and sources of data used to derive these values are described. ICRP are currently considering a statement about values of ALI for members of the public. The many factors by which these would differ from those recommended for workers are discussed. (author)

  20. ENVIRONMENTAL ASSESSMENT METHODOLOGY FOR THE NUCLEAR FUEL CYCLE

    Energy Technology Data Exchange (ETDEWEB)

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

    1977-07-01

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

  1. 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

  2. Population dose assessment: characteristics of PC CREAM

    International Nuclear Information System (INIS)

    Alonso, Maria T.; Curti, Adriana R.

    2000-01-01

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

  3. Dose-dependent transitions in mechanisms of toxicity

    International Nuclear Information System (INIS)

    Slikker, William; Andersen, Melvin E.; Bogdanffy, Matthew S.; Bus, James S.; Cohen, Steven D.; Conolly, Rory B.; David, Raymond M.; Doerrer, Nancy G.; Dorman, David C.; Gaylor, David W.; Hattis, Dale; Rogers, John M.; Woodrow Setzer, R.; Swenberg, James A.; Wallace, Kendall

    2004-01-01

    Scientists and decision makers from all sectors agree that risk assessments should be based on the best available science. Several years ago, the Health and Environmental Sciences Institute (HESI), a global branch of the International Life Sciences Institute (ILSI), identified the need for better scientific understanding of dose-dependent transitions in mechanisms of toxicity as one avenue by which the best and latest science can be integrated into the decision making process. In July 2001, the HESI Project Committee on Dose-Dependent Transitions in Mechanisms of Toxicity established a group of academic, government, and industry scientists to engage in active technical discourse on the issue of dose-dependent transitions in mechanisms of toxicity. Over the next 18 months, case studies were examined. These case studies included acetaminophen, butadiene, ethylene glycol, formaldehyde, manganese, methylene chloride, the peroxisome proliferator-activated receptor, progesterone/hydroxyflutamide, propylene oxide, vinyl acetate, vinyl chloride, vinylidene chloride, and zinc (Slikker, W., Jr., Andersen, M.E., Bogdanffy, M.S., Bus, J.S., Cohen, S.D., Conolly, R.B., David, R.M., Doerrer, N.G., Dorman, D.C., Gaylor, D.W., Hattis, D., Rogers, J.M., Setzer, R.W., Swenberg, J.A., Wallace, K., 2004. Dose-dependent transitions in mechanisms of toxicity: case studies. Toxicol. Appl. Pharmacol. 201(3), 226-294 (this issue)). The HESI Project Committee sponsored two technical workshops in 2003. The first of these workshops took place on February 12-13, 2003, and was co-sponsored by the Agency for Toxic Substances and Disease Registry, the American Chemistry Council, the National Institute of Environmental Health Sciences, the Society of Toxicology, and the U.S. Environmental Protection Agency. Additional support was provided by Health Canada. Invited experts from government, academia, and industry provided scientific perspectives and recommendations at the workshop. The purpose of

  4. Development of autonomous gamma dose logger for environmental monitoring

    Energy Technology Data Exchange (ETDEWEB)

    Jisha, N. V.; Krishnakumar, D. N.; Surya Prakash, G.; Kumari, Anju; Baskaran, R.; Venkatraman, B. [Radiological Safety Division, Indira Gandhi Centre for Atomic Research, Kalpakkam 603 102, Tamil Nadu (India)

    2012-03-15

    Continuous monitoring and archiving of background radiation levels in and around the nuclear installation is essential and the data would be of immense use during analysis of any untoward incidents. A portable Geiger Muller detector based autonomous gamma dose logger (AGDL) for environmental monitoring is indigenously designed and developed. The system operations are controlled by microcontroller (AT89S52) and the main features of the system are software data acquisition, real time LCD display of radiation level, data archiving at removable compact flash card. The complete system operates on 12 V battery backed up by solar panel and hence the system is totally portable and ideal for field use. The system has been calibrated with Co-60 source (8.1 MBq) at various source-detector distances. The system is field tested and performance evaluation is carried out. This paper covers the design considerations of the hardware, software architecture of the system along with details of the front-end operation of the autonomous gamma dose logger and the data file formats. The data gathered during field testing and inter comparison with GammaTRACER are also presented in the paper. AGDL has shown excellent correlation with energy fluence monitor tuned to identify {sup 41}Ar, proving its utility for real-time plume tracking and source term estimation.

  5. Spectrum-to-dose conversion operator value function of a Ge(Li) in-situ environmental gamma-ray spectrometer

    International Nuclear Information System (INIS)

    Terada, Hiromi; Sakai, Eiji; Katagiri, Masaki

    1976-05-01

    A spectrum-to-dose conversion operator value function was obtained for a 73cm 3 closed-end coaxial Ge(Li) in-situ environmental gamma-ray spectrometer; factors influencing the function are considered. (auth.)

  6. Environmental radioactivity in Canada, 1981

    International Nuclear Information System (INIS)

    McGregor, R.G.; Quinn, J.M.; Tracy, B.L.

    1983-01-01

    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. Special investigations were carried out during 1981 on bottled mineral waters and in conjunction with unusual occurences at nuclear reactor sites and a uranium refinery. Dose commitments have been estimated for the ongoing natural radioactivity, fallout and reactor studies. All measurements made during the year are below the limits recommended by the International Commission on Radiological Protection

  7. Preliminary results of measurement of natural environmental radiation levels and doses to population in China

    International Nuclear Information System (INIS)

    Wang Qiliang; He Miaoting; Shu Qi

    1985-01-01

    In this paper the preliminary results of measurement of natural environmental radiation levels in China with RSS-111 high pressure ionization chamber and estimated doses to population are reported. A total of 2,723 indoor locales throughout China were measured. The results showed that the average absorbed dose rates in air due to gamma radiation for indoors and outdoors were 11.0 x 10 -8 Gy.h -1 and 7.4 x 10 -8 Gy.h -1 , respectively, and those due to cosmic rays were 3.2 x 10 -8 Gy.h -1 and 3.7 x 10 -8 Gy.h -1 , respectively. The annual average effective dose equivalent to population was 919 μSv, including 630 μSv from natural gamma radiation and 289 μSv from cosmic rays

  8. Calculation of organ doses from environmental gamma rays using human phantoms and Monte Carlo methods. Pt. 1

    International Nuclear Information System (INIS)

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

    1990-01-01

    Organ doses from environmental γ-rays (U-238, Th-232, K-40) were calculated using Monte Carlo methods for three typical sources of a semi-infinite volume source in the air, an infinite plane source in the ground and a volume source in the ground. γ-ray fields in the natural environment were simulated rigourously without approximations or simplifications in the intermediate steps except for the disturbance of the radiation field by the human body which was neglected. Organ doses were calculated for four anthropomorphic phantoms representing a baby, a child, a female and a male adult. The dose of a fetus is given by the dose to the uterus of the adult female. Air kerma and dose conversion factors normalised to air kerma and to source intensity are given for monoenergetic sources and for the natural radionuclides. (orig./HP)

  9. Health Physics Society Comments to U.S. Environmental Protection Agency Regulatory Reform Task Force.

    Science.gov (United States)

    Ring, Joseph; Tupin, Edward; Elder, Deirdre; Hiatt, Jerry; Sheetz, Michael; Kirner, Nancy; Little, Craig

    2018-05-01

    The Health Physics Society (HPS) provided comment to the U.S. Environmental Protection Agency (EPA) on options to consider when developing an action plan for President Trump's Executive Order to evaluate regulations for repeal, replacement, or modification. The HPS recommended that the EPA reconsider their adherence to the linear no-threshold (LNT) model for radiation risk calculations and improve several documents by better addressing uncertainties in low-dose, low dose-rate (LDDR) radiation exposure environments. The authors point out that use of the LNT model near background levels cannot provide reliable risk projections, use of the LNT model and collective-dose calculations in some EPA documents is inconsistent with the recommendations of international organizations, and some EPA documents have not been exposed to the public comment rule-making process. To assist in establishing a better scientific basis for the risks of low dose rate and low dose radiation exposure, the EPA should continue to support the "Million Worker Study," led by the National Council on Radiation Protection and Measurement.

  10. New ICRP recommendations on occupational limits for radon daughters

    International Nuclear Information System (INIS)

    Jacobi, W.

    1981-01-01

    The ICRP has recommended in 1959 for the first time a maximum permissible concentration (MPC) for the occupational exposure to radon and its short-lived daughters. Since this time more realistic dosimetric models for radon daughters have been developed. Taking into account epidemiological and new dosimetric findings the ICRP has adopted in March this year new recommendations on occupational limits for inhalation of 222 Rn, 220 Rn and their short-lived daughters. This report will be published this year as ICRP Publication 32 (ICRP 1981). The recommended limits for radon daughters were derived from the basic dose and risk limits as they were proposed by ICRP in its new basic recommendations (ICRP Publ. 26, 1977). In the following this basic system of dose limitation is shortly outlined before the special recommendations for radon daughters are described

  11. Booster dose after 10 years is recommended following 17DD-YF primary vaccination.

    Science.gov (United States)

    Campi-Azevedo, Ana Carolina; Costa-Pereira, Christiane; Antonelli, Lis R; Fonseca, Cristina T; Teixeira-Carvalho, Andréa; Villela-Rezende, Gabriela; Santos, Raiany A; Batista, Maurício A; Campos, Fernanda M; Pacheco-Porto, Luiza; Melo Júnior, Otoni A; Hossell, Débora M S H; Coelho-dos-Reis, Jordana G; Peruhype-Magalhães, Vanessa; Costa-Silva, Matheus F; de Oliveira, Jaquelline G; Farias, Roberto H; Noronha, Tatiana G; Lemos, Jandira A; von Doellinger, Vanessa dos R; Simões, Marisol; de Souza, Mirian M; Malaquias, Luiz C; Persi, Harold R; Pereira, Jorge M; Martins, José A; Dornelas-Ribeiro, Marcos; Vinhas, Aline de A; Alves, Tatiane R; Maia, Maria de L; Freire, Marcos da S; Martins, Reinaldo de M; Homma, Akira; Romano, Alessandro P M; Domingues, Carla M; Tauil, Pedro L; Vasconcelos, Pedro F; Rios, Maria; Caldas, Iramaya R; Camacho, Luiz A; Martins-Filho, Olindo Assis

    2016-01-01

    A single vaccination of Yellow Fever vaccines is believed to confer life-long protection. In this study, results of vaccinees who received a single dose of 17DD-YF immunization followed over 10 y challenge this premise. YF-neutralizing antibodies, subsets of memory T and B cells as well as cytokine-producing lymphocytes were evaluated in groups of adults before (NVday0) and after (PVday30-45, PVyear1-4, PVyear5-9, PVyear10-11, PVyear12-13) 17DD-YF primary vaccination. YF-neutralizing antibodies decrease significantly from PVyear1-4 to PVyear12-13 as compared to PVday30-45, and the seropositivity rates (PRNT≥2.9Log10mIU/mL) become critical (lower than 90%) beyond PVyear5-9. YF-specific memory phenotypes (effector T-cells and classical B-cells) significantly increase at PVday30-45 as compared to naïve baseline. Moreover, these phenotypes tend to decrease at PVyear10-11 as compared to PVday30-45. Decreasing levels of TNF-α(+) and IFN-γ(+) produced by CD4(+) and CD8(+) T-cells along with increasing levels of IL-10(+)CD4(+)T-cells were characteristic of anti-YF response over time. Systems biology profiling represented by hierarchic networks revealed that while the naïve baseline is characterized by independent micro-nets, primary vaccinees displayed an imbricate network with essential role of central and effector CD8(+) memory T-cell responses. Any putative limitations of this cross-sectional study will certainly be answered by the ongoing longitudinal population-based investigation. Overall, our data support the current Brazilian national immunization policy guidelines that recommend one booster dose 10 y after primary 17DD-YF vaccination.

  12. Integrated task plans for the Hanford Environmental Dose Reconstruction Project, June 1992 through May 1994

    International Nuclear Information System (INIS)

    Shipler, D.B.

    1993-09-01

    The purpose of the Hanford Environmental Dose Reconstruction (HEDR) Project is to estimate radiation doses from Hanford Site operations since 1944 to representative individuals. The primary objective of work to be performed through May 1994 is to determine the project's appropriate scope: space, time, radionuclides, pathways and representative individuals; determine the project's appropriate level of accuracy/level of uncertainty in dose estimates; complete model and data development; and estimate doses for the Hanford Thyroid Disease Study and representative individuals. A major objective of the HEDR Project is to estimate doses to the thyroid of individuals who were exposed to iodine-131. A principal pathway for many of these individuals was milk from cows that ate vegetation contaminated by iodine-131 released into the air from Hanford facilities. The plan for June 1992 through May 1994 has been prepared based on activities and budgets approved by the Technical Steering Panel (TSP) at its meetings on January 7--9, 1993 and February 25--26, 1993. The activities can be divided into three broad categories: (1) computer code and data development activities, (2) calculation of doses, and (3) technical and communication support to the TSP and the TSP Native American Working Group (NAWG). The following activities will be conducted to accomplish project objectives through May 1994

  13. Natural terrestrial radiation exposure in Hong Kong. A survey on environmental gamma absorbed dose rate in air

    International Nuclear Information System (INIS)

    Wong, M.C.; Poon, H.T.; Chan, Y.K.; So, C.K.

    2000-01-01

    Hong Kong is a metropolitan city located on the southern coast of China with a population of some six million. About 90% of the population is concentrated in heavily built-up residential and commercial areas, which accounts for less than 50% of the total area in the territory. Hong Kong Observatory, 134A Nathan Road, Kowloon, Hong Kong, China. In order to understand the spatial variations in the environmental radiation levels in Hong Kong, the Hong Kong Observatory (HKO) in early 1999 conducted a study of the environmental gamma absorbed dose rate in air. The study combined data collected by the HKO radiation monitoring network (RMN) and data from a comprehensive territory-wide radiological survey conducted in January and February 1999. The RMN of ten stations each equipped with a Reuter-Stokes Model RSS-1013 HPIC has been in operation since 1987 to continuously monitor the environmental radiation levels over the territory as part of the emergency monitoring programme for response to nuclear accidents at a nearby nuclear power station. The terrestrial component of the environmental radiation field was estimated by subtracting from the measurements the cosmic contribution, which is determined to be about 39 nGy/h from measurements conducted over two large fresh water reservoirs. The RMN data with the long history was analysed to derive the seasonal variations in the environmental radiation levels. On average the environmental gamma absorbed dose rate in air in January and February is 1.03 times of the annual figure. This seasonal correction was applied to the results of the year 1999 survey. As the radiation field in the heavily built-up areas is enhanced by contribution from buildings, in the territory-wide survey measurements were made both in the open field and built-up areas. The territory of Hong Kong was divided into 42 grid boxes of 5 km x 5 km for open field and 61 grid boxes of 2.5 km x 2.5 km for built-up areas according to the population and land use. A

  14. [Radon risk in healthcare facilities: environmental monitoring and effective dose].

    Science.gov (United States)

    Cammarota, B; Cascone, Maria Teresa; De Paola, L; Schillirò, F; Del Prete, U

    2009-01-01

    Radon, the second cause of lung cancer after smoking (WHO- IARC), is a natural, radioactive gas, which originates from the soil and pollutes indoor air, especially in closed or underground spaces. The purpose of this study was to determine the concentration of radon gas, its effective dose, and the measurement of microclimatic degrees C; U.R. % and air velocity in non-academic intensive care units of public hospitals in the Naples area. The annual average concentrations of radon gas were detected with EIC type ionization electret chambers, type LLT with exposure over four 3-month periods. The concentrations varied for all health facilities between 186 and 1191 Bq/m3. Overall, the effective dose of exposure to radon gas of 3mSv/a recommended by Italian legislation was never exceeded. The concentration of radon gas showed a decreasing trend starting from the areas below ground level to those on higher floors; such concentrations were also influenced by natural and artificial ventilation of the rooms, building materials used for walls, and by the state of maintenance and improvements of the building (insulation of floors and walls). The data obtained confirmed the increased concentration of radionuclides in the yellow tuff of volcanic origin in the Campania Region and the resulting rate of release of radon gas, whereas the reinforced concrete structure (a hospital located on the hillside), which had the lowest values, proved to provide good insulation against penetration and accumulation of radon gas.

  15. Epidemiological methods for assessing dose-response and dose-effect relationships

    DEFF Research Database (Denmark)

    Kjellström, Tord; Grandjean, Philippe

    2007-01-01

    Selected Molecular Mechanisms of Metal Toxicity and Carcinogenicity General Considerations of Dose-Effect and Dose-Response Relationships Interactions in Metal Toxicology Epidemiological Methods for Assessing Dose-Response and Dose-Effect Relationships Essential Metals: Assessing Risks from Deficiency......Description Handbook of the Toxicology of Metals is the standard reference work for physicians, toxicologists and engineers in the field of environmental and occupational health. This new edition is a comprehensive review of the effects on biological systems from metallic elements...... access to a broad range of basic toxicological data and also gives a general introduction to the toxicology of metallic compounds. Audience Toxicologists, physicians, and engineers in the fields of environmental and occupational health as well as libraries in these disciplines. Will also be a useful...

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

    Science.gov (United States)

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

    2017-07-01

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

  17. Summary of literature review of risk communication: Hanford Environmental Dose Reconstruction Project

    International Nuclear Information System (INIS)

    Byram, S.J.

    1991-05-01

    The Hanford Environmental Dose Reconstruction (HEDR) Project will estimate radiation exposures people may have received from radioactive materials released during past operations at the Department of Energy's Hanford Site near Richland, Washington. The project is being conducted by Pacific Northwest Laboratory (PNL) under the direction of an independent Technical Steering Panel (TSP). The Centers for Disease Control (CDC) will use HEDR dose estimates in studies to investigate a potential link between thyroid disease and historical Hanford emissions. The HEDR Project was initiated to address public concerns about the possible health impacts from past releases of radioactive materials from Hanford. The TSP recognized early in the project that special mechanisms would be required to communicate effectively to the many different concerned audiences. To identify and develop these mechanisms, the TSP issued Directive 89-7 to PNL in May 1989. The TSP directed PNL to examine methods to communicate the causes and effects of uncertainties in the dose estimates. A literature review was conducted as the first activity in response to the TSP's directive. This report presents the results of the literature review. The objective of the literature review was to identify ''key principles'' that could be applied to develop communications strategies for the project. 26 refs., 6 figs

  18. Experimental evaluation of neutron dose in radiotherapy patients: Which dose?

    Energy Technology Data Exchange (ETDEWEB)

    Romero-Expósito, M., E-mail: mariateresa.romero@uab.cat; Domingo, C.; Ortega-Gelabert, O.; Gallego, S. [Grup de Recerca en Radiacions Ionizants (GRRI), Departament de Física, Universitat Autònoma de Barcelona, Bellaterra 08193 (Spain); Sánchez-Doblado, F. [Departamento de Fisiología Médica y Biofísica, Universidad de Sevilla, Sevilla 41009 (Spain); Servicio de Radiofísica, Hospital Universitario Virgen Macarena, Sevilla 41009 (Spain)

    2016-01-15

    Purpose: The evaluation of peripheral dose has become a relevant issue recently, in particular, the contribution of secondary neutrons. However, after the revision of the Recommendations of the International Commission on Radiological Protection, there has been a lack of experimental procedure for its evaluation. Specifically, the problem comes from the replacement of organ dose equivalent by the organ-equivalent dose, being the latter “immeasurable” by definition. Therefore, dose equivalent has to be still used although it needs the calculation of the radiation quality factor Q, which depends on the unrestricted linear energy transfer, for the specific neutron irradiation conditions. On the other hand, equivalent dose is computed through the radiation weighting factor w{sub R}, which can be easily calculated using the continuous function provided by the recommendations. The aim of the paper is to compare the dose equivalent evaluated following the definition, that is, using Q, with the values obtained by replacing the quality factor with w{sub R}. Methods: Dose equivalents were estimated in selected points inside a phantom. Two types of medical environments were chosen for the irradiations: a photon- and a proton-therapy facility. For the estimation of dose equivalent, a poly-allyl-diglicol-carbonate-based neutron dosimeter was used for neutron fluence measurements and, additionally, Monte Carlo simulations were performed to obtain the energy spectrum of the fluence in each point. Results: The main contribution to dose equivalent comes from neutrons with energy higher than 0.1 MeV, even when they represent the smallest contribution in fluence. For this range of energy, the radiation quality factor and the radiation weighting factor are approximately equal. Then, dose equivalents evaluated using both factors are compatible, with differences below 12%. Conclusions: Quality factor can be replaced by the radiation weighting factor in the evaluation of dose

  19. Analysis of Cumulative Dose to Implanted Pacemaker According to Various IMRT Delivery Methods: Optimal Dose Delivery Versus Dose Reduction Strategy

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jeong Woo; Hong, Se Mie [Dept. of Radiation Oncology, Konkuk University Medical Center, Seoul (Korea, Republic of)

    2011-11-15

    Cancer patients with implanted cardiac pacemaker occasionally require radiotherapy. Pacemaker may be damaged or malfunction during radiotherapy due to ionizing radiation or electromagnetic interference. Although radiotherapy should be planned to keep the dose to pacemaker as low as possible not to malfunction ideally, current radiation treatment planning (RTP) system does not accurately calculate deposited dose to adjacent field border or area beyond irradiated fields. In terms of beam delivery techniques using multiple intensity modulated fields, dosimetric effect of scattered radiation in high energy photon beams is required to be detailed analyzed based on measurement data. The aim of this study is to evaluate dose discrepancies of pacemaker in a RTP system as compared to measured doses. We also designed dose reduction strategy limited value of 2 Gy for radiation treatment patients with cardiac implanted pacemaker. Total accumulated dose of 145 cGy based on in-vivo dosimetry was satisfied with the recommendation criteria to prevent malfunction of pacemaker in SS technique. However, the 2 mm lead shielder enabled the scattered doses to reduce up to 60% and 40% in the patient and the phantom, respectively. The SS technique with the lead shielding could reduce the accumulated scattered doses less than 100 cGy. Calculated and measured doses were not greatly affected by the beam delivery techniques. In-vivo and measured doses on pacemaker position showed critical dose discrepancies reaching up to 4 times as compared to planned doses in RTP. The current SS technique could deliver lower scattered doses than recommendation criteria, but use of 2 mm lead shielder contributed to reduce scattered doses by 60%. The tertiary lead shielder can be useful to prevent malfunction or electrical damage of implanted pacemakers during radiotherapy. It is required to estimate more accurate scattered doses of the patient or medical device in RTP to design proper dose reduction strategy.

  20. Analysis of Cumulative Dose to Implanted Pacemaker According to Various IMRT Delivery Methods: Optimal Dose Delivery Versus Dose Reduction Strategy

    International Nuclear Information System (INIS)

    Lee, Jeong Woo; Hong, Se Mie

    2011-01-01

    Cancer patients with implanted cardiac pacemaker occasionally require radiotherapy. Pacemaker may be damaged or malfunction during radiotherapy due to ionizing radiation or electromagnetic interference. Although radiotherapy should be planned to keep the dose to pacemaker as low as possible not to malfunction ideally, current radiation treatment planning (RTP) system does not accurately calculate deposited dose to adjacent field border or area beyond irradiated fields. In terms of beam delivery techniques using multiple intensity modulated fields, dosimetric effect of scattered radiation in high energy photon beams is required to be detailed analyzed based on measurement data. The aim of this study is to evaluate dose discrepancies of pacemaker in a RTP system as compared to measured doses. We also designed dose reduction strategy limited value of 2 Gy for radiation treatment patients with cardiac implanted pacemaker. Total accumulated dose of 145 cGy based on in-vivo dosimetry was satisfied with the recommendation criteria to prevent malfunction of pacemaker in SS technique. However, the 2 mm lead shielder enabled the scattered doses to reduce up to 60% and 40% in the patient and the phantom, respectively. The SS technique with the lead shielding could reduce the accumulated scattered doses less than 100 cGy. Calculated and measured doses were not greatly affected by the beam delivery techniques. In-vivo and measured doses on pacemaker position showed critical dose discrepancies reaching up to 4 times as compared to planned doses in RTP. The current SS technique could deliver lower scattered doses than recommendation criteria, but use of 2 mm lead shielder contributed to reduce scattered doses by 60%. The tertiary lead shielder can be useful to prevent malfunction or electrical damage of implanted pacemakers during radiotherapy. It is required to estimate more accurate scattered doses of the patient or medical device in RTP to design proper dose reduction strategy.

  1. [Immunisation schedule of the Spanish Association of Paediatrics: 2018 recommendations].

    Science.gov (United States)

    Moreno-Pérez, David; Álvarez García, Francisco José; Álvarez Aldeán, Javier; Cilleruelo Ortega, María José; Garcés Sánchez, María; García Sánchez, Nuria; Hernández Merino, Ángel; Méndez Hernández, María; Merino Moína, Manuel; Montesdeoca Melián, Abián; Ruiz-Contreras, Jesús

    2018-01-01

    The Advisory Committee on Vaccines of the Spanish Association of Paediatrics annually publishes the immunisation schedule considered optimal for children resident in Spain, according to available evidence on current vaccines. Regarding funded immunisations, 2+1 strategy (2, 4, 11-12 months) with hexavalent (DTPa-IPV-Hib-HB) and 13-valent pneumococcal vaccines are recommended. Administration of the 6-year booster dose with DTPa is recommended, and a poliomyelitis dose for children who had received the 2+1 scheme, as well as Tdap vaccine for adolescents and pregnant women in every pregnancy between 27 and 32 weeks' gestation. The two-dose scheme should be used for MMR (12 months and 2-4 years) and varicella (15 months and 2-4 years). MMRV vaccine could be applied as the second dose if available. Coverage of human papillomavirus vaccination in girls aged 12 with a two dose scheme (0, 6 months) should be improved. Information and recommendation for male adolescents about potential beneficial effects of this immunisation should be provided as well. The new 9 genotypes vaccine is now available, expanding the coverage for both gender. Regarding non-funded immunisations, Committee on Vaccines of the Spanish Association of Paediatrics recommends meningococcal B vaccination, with a 3+1 schedule, and requests to be included in the National Immunisation Program. Tetravalent meningococcal vaccine (MenACWY) is recommended to adolescents (14-18 years) who are going to live in countries with systematic vaccination against ACWY serogroups, and people >6 weeks of age with risk factors or travellers to countries with very high incidence. Vaccination against rotavirus is recommended in all infants. Copyright © 2017 Asociación Española de Pediatría. Publicado por Elsevier España, S.L.U. All rights reserved.

  2. Dose mapping for documentation of radiation sterilization

    DEFF Research Database (Denmark)

    Miller, A.

    1999-01-01

    The radiation sterilization standards EN 552 and ISO 11137 require that dose mapping in real or simulated product be carried in connection with the process qualification. This paper reviews the recommendations given in the standards and discusses the difficulties and limitations of practical dose...... mapping. The paper further gives recommendations for effective dose mapping including traceable dosimetry, documented procedures for placement of dosimeters, and evaluation of measurement uncertainties. (C) 1999 Elsevier Science Ltd. All rights reserved....

  3. Argonne National Laboratory Site Environmental report for calendar year 2009.

    Energy Technology Data Exchange (ETDEWEB)

    Golchert, N. W.; Davis, T. M.; Moos, L. P.

    2010-08-04

    This report discusses the status and the accomplishments of the environmental protection program at Argonne National Laboratory for calendar year 2009. The status of Argonne environmental protection activities with respect to compliance with the various laws and regulations is discussed, along with the progress of environmental corrective actions and restoration projects. To evaluate the effects of Argonne operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the Argonne site were analyzed and compared with applicable guidelines and standards. A variety of radionuclides were measured in air, surface water, on-site groundwater, and bottom sediment samples. In addition, chemical constituents in surface water, groundwater, and Argonne effluent water were analyzed. External penetrating radiation doses were measured, and the potential for radiation exposure to off-site population groups was estimated. Results are interpreted in terms of the origin of the radioactive and chemical substances (i.e., natural, Argonne, and other) and are compared with applicable environmental quality standards. A U.S. Department of Energy (DOE) dose calculation methodology, based on International Commission on Radiological Protection recommendations and the U.S. Environmental Protection Agency's (EPA) CAP-88 Version 3 (Clean Air Act Assessment Package-1988) computer code, was used in preparing this report.

  4. Argonne National Laboratory Site Environmental Report for Calendar Year 2013

    Energy Technology Data Exchange (ETDEWEB)

    Davis, T. M. [Argonne National Lab. (ANL), Argonne, IL (United States); Gomez, J. L. [Argonne National Lab. (ANL), Argonne, IL (United States); Moos, L. P. [Argonne National Lab. (ANL), Argonne, IL (United States)

    2014-09-02

    This report discusses the status and the accomplishments of the environmental protection program at Argonne National Laboratory for calendar year 2013. The status of Argonne environmental protection activities with respect to compliance with the various laws and regulations is discussed, along with environmental management, sustainability efforts, environmental corrective actions, and habitat restoration. To evaluate the effects of Argonne operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the Argonne site were analyzed and compared with applicable guidelines and standards. A variety of radionuclides were measured in air, surface water, on-site groundwater, and bottom sediment samples. In addition, chemical constituents in surface water, groundwater, and Argonne effluent water were analyzed. External penetrating radiation doses were measured, and the potential for radiation exposure to off-site population groups was estimated. Results are interpreted in terms of the origin of the radioactive and chemical substances (i.e., natural, Argonne, and other) and are compared with applicable standards intended to protect human health and the environment. A U.S. Department of Energy (DOE) dose calculation methodology, based on International Commission on Radiological Protection (ICRP) recommendations and the U.S. Environmental Protection Agency’s (EPA) CAP-88 Version 3 computer code, was used in preparing this report.

  5. Argonne National Laboratory site environmental report for calendar year 2007.

    Energy Technology Data Exchange (ETDEWEB)

    Golchert, N. W.; Davis, T. M.; Moos, L. P.; ESH/QA Oversight

    2008-09-09

    This report discusses the status and the accomplishments of the environmental protection program at Argonne National Laboratory for calendar year 2007. The status of Argonne environmental protection activities with respect to compliance with the various laws and regulations is discussed, along with the progress of environmental corrective actions and restoration projects. To evaluate the effects of Argonne operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the Argonne site were analyzed and compared with applicable guidelines and standards. A variety of radionuclides were measured in air, surface water, on-site groundwater, and bottom sediment samples. In addition, chemical constituents in surface water, groundwater, and Argonne effluent water were analyzed. External penetrating radiation doses were measured, and the potential for radiation exposure to off-site population groups was estimated. Results are interpreted in terms of the origin of the radioactive and chemical substances (i.e., natural, fallout, Argonne, and other) and are compared with applicable environmental quality standards. A U.S. Department of Energy dose calculation methodology, based on International Commission on Radiological Protection recommendations and the U.S. Environmental Protection Agency's CAP-88 Version 3 (Clean Air Act Assessment Package-1988) computer code, was used in preparing this report.

  6. Argonne National Laboratory site environmental report for calendar year 2004.

    Energy Technology Data Exchange (ETDEWEB)

    Golchert, N. W.; Kolzow, R. G.

    2005-09-02

    This report discusses the accomplishments of the environmental protection program at Argonne National Laboratory (ANL) for calendar year 2004. The status of ANL environmental protection activities with respect to compliance with the various laws and regulations is discussed, along with the progress of environmental corrective actions and restoration projects. To evaluate the effects of ANL operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the ANL site were analyzed and compared with applicable guidelines and standards. A variety of radionuclides were measured in air, surface water, on-site groundwater, and bottom sediment samples. In addition, chemical constituents in surface water, groundwater, and ANL effluent water were analyzed. External penetrating radiation doses were measured, and the potential for radiation exposure to off-site population groups was estimated. Results are interpreted in terms of the origin of the radioactive and chemical substances (i.e., natural, fallout, ANL, and other) and are compared with applicable environmental quality standards. A U.S. Department of Energy dose calculation methodology, based on International Commission on Radiological Protection recommendations and the U.S. Environmental Protection Agency's CAP-88 (Clean Air Act Assessment Package-1988) computer code, was used in preparing this report.

  7. Argonne National Laboratory site environmental report for calendar year 2006.

    Energy Technology Data Exchange (ETDEWEB)

    Golchert, N. W.; ESH/QA Oversight

    2007-09-13

    This report discusses the status and the accomplishments of the environmental protection program at Argonne National Laboratory for calendar year 2006. The status of Argonne environmental protection activities with respect to compliance with the various laws and regulations is discussed, along with the progress of environmental corrective actions and restoration projects. To evaluate the effects of Argonne operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the Argonne site were analyzed and compared with applicable guidelines and standards. A variety of radionuclides were measured in air, surface water, on-site groundwater, and bottom sediment samples. In addition, chemical constituents in surface water, groundwater, and Argonne effluent water were analyzed. External penetrating radiation doses were measured, and the potential for radiation exposure to off-site population groups was estimated. Results are interpreted in terms of the origin of the radioactive and chemical substances (i.e., natural, fallout, Argonne, and other) and are compared with applicable environmental quality standards. A U.S. Department of Energy dose calculation methodology, based on International Commission on Radiological Protection recommendations and the U.S. Environmental Protection Agency's CAP-88 Version 3 (Clean Air Act Assessment Package-1988) computer code, was used in preparing this report.

  8. Environmental and effluent monitoring at Lucas Heights Science and Technology Centre, 1998

    Energy Technology Data Exchange (ETDEWEB)

    Hoffmann, E L; Loosz, T; Farrar, Y; Mokhber-Shahin, L

    1999-07-01

    Results are presented of environmental and effluent monitoring conducted in the vicinity of the Lucas Heights Science and Technology Centre (LHSTC) during 1998. All low-level liquid and gaseous effluent discharges complied with existing discharge authorizations and relevant environmental regulations. Potential effective doses to the general public from controlled airborne discharges from HIFAR were estimated utilising the PC-Cream atmospheric dispersion and dosimetry code. The potential effective dose to the public was estimated to be less than 0.010 mSv/year for all receptor locations on the 1.6 km buffer zone boundary around the HIFAR research reactor. This value represents 1% of the 1 mSv/year dose limit for long term exposure that is recommended by the National Health and Medical Research Council and 3.3% of the site dose constraint of 0.3 mSv/year approved by the Nuclear Safety Bureau. It is concluded that there is no impact on the health of the community, staff or the environment as a consequence of operations at the LHSTC.

  9. Environmental and effluent monitoring at Lucas Heights Science and Technology Centre, 1998

    International Nuclear Information System (INIS)

    Hoffmann, E.L.; Loosz, T.; Farrar, Y.; Mokhber-Shahin, L.

    1999-01-01

    Results are presented of environmental and effluent monitoring conducted in the vicinity of the Lucas Heights Science and Technology Centre (LHSTC) during 1998. All low-level liquid and gaseous effluent discharges complied with existing discharge authorizations and relevant environmental regulations. Potential effective doses to the general public from controlled airborne discharges from HIFAR were estimated utilising the PC-Cream atmospheric dispersion and dosimetry code. The potential effective dose to the public was estimated to be less than 0.010 mSv/year for all receptor locations on the 1.6 km buffer zone boundary around the HIFAR research reactor. This value represents 1% of the 1 mSv/year dose limit for long term exposure that is recommended by the National Health and Medical Research Council and 3.3% of the site dose constraint of 0.3 mSv/year approved by the Nuclear Safety Bureau. It is concluded that there is no impact on the health of the community, staff or the environment as a consequence of operations at the LHSTC

  10. Psychological functioning and adherence to the recommended dose of physical activity in later life: results from a national health survey.

    Science.gov (United States)

    Netz, Yael; Dunsky, Ayelet; Zach, Sima; Goldsmith, Rebecca; Shimony, Tal; Goldbourt, Uri; Zeev, Aviva

    2012-12-01

    Official health organizations have established the dose of physical activity needed for preserving both physical and psychological health in old age. The objective of this study was to explore whether adherence to the recommended criterion of physical activity accounted for better psychological functioning in older adults in Israel. A random sample of 1,663 (799 men) Israelis reported their physical activity routine, and based on official guidelines were divided into sufficiently active, insufficiently active, and inactive groups. The General Health Questionnaire (GHQ) was used for assessing mental health and the Mini-Mental State Examination (MMSE) for assessing cognitive functioning. Factor analysis performed on the GHQ yielded two factors - positive and negative. Logistic regressions for the GHQ factors and for the MMSE were conducted for explaining their variance, with demographic variables entered first, followed by health and then physical activity. The explained variance in the three steps was Cox and Snell R2 = 0.022, 0.023, 0.039 for the positive factor, 0.066, 0.093, 0.101 for the negative factor, and 0.204, 0.206, 0.209 for the MMSE. Adherence to the recommended dose of physical activity accounted for better psychological functioning beyond demographic and health variables; however, the additional explained variance was small. More specific guidelines of physical activity may elucidate a stronger relationship, but only randomized controlled trials can reveal cause-effect relationship between physical activity and psychological functioning. More studies are needed focusing on the positive factor of psychological functioning.

  11. ICRP Publication 103. The 2007 Recommendations of the International Commission on Radiological Protection

    International Nuclear Information System (INIS)

    Nenot, Jean-Claude; Brenot, Jean; Laurier, Dominique; Rannou, Alain; Thierry, Dominique

    2009-01-01

    These revised Recommendations for a System of Radiological Protection formally replace the Commission's previous, 1990, Recommendations; and update, consolidate, and develop the additional guidance on the control of exposure from radiation sources issued since 1990. Thus, the present Recommendations update the radiation and tissue weighting factors in the quantities equivalent and effective dose and update the radiation detriment, based on the latest available scientific information of the biology and physics of radiation exposure. They maintain the Commission's three fundamental principles of radiological protection, namely justification, optimisation, and the application of dose limits, clarifying how they apply to radiation sources delivering exposure and to individuals receiving exposure. The Recommendations evolve from the previous process-based protection approach using practices and interventions by moving to an approach based on the exposure situation. They recognise planned, emergency, and existing exposure situations, and apply the fundamental principles of justification and optimisation of protection to all of these situations. They maintain the Commission's current individual dose limits for effective dose and equivalent dose from all regulated sources in planned exposure situations. They reinforce the principle of optimisation of protection, which should be applicable in a similar way to all exposure situations, subject to the following restrictions on individual doses and risks; dose and risk constraints for planned exposure situations, and reference levels for emergency and existing exposure situations. The Recommendations also include an approach for developing a framework to demonstrate radiological protection of the environment

  12. Nordic Intervention Criteria for Nuclear or Radiological Emergencies. Recommendations

    International Nuclear Information System (INIS)

    2001-01-01

    Recommendations of the Nordic radiation protection authorities on application of international criteria in a nuclear or radiological emergency in the Nordic countries are presented. The recommendations are focused on the generic intervention levels for various actions to protect members of the public and workers undertaking an intervention. Prompt precautionary actions for the near zones around the Finnish and Swedish nuclear power plants are defined. These actions are; preventive sheltering, iodine prophylaxis and precautionary evacuation. No special intervention levels for these precautionary actions have been set, because implementation of these actions is always based on very limited information about an accident. These actions can be initiated on a mere indication of possible release of radioactivity. The indication might be an alarm or any other predefined signal. Intervention level for actions to protect members of the public are based on the concept of avertable dose. They are in line with the international recommendations. With regard to iodine prophylaxis, a national approach is recommended due to different national policies of advance distribution of iodine tablets. The longer term intervention actions, temporary relocation and permanent resettlement, will be based not only on radiation protection factors but also on wider judgement of the overall situation. For that reason, no generic intervention levels, in terms of radiation dose, are recommended. The intervention levels for various protective actions are in the following table.Table 1. Generic intervention levels for actions to protect members of the public.Protective action. Generic intervention level as an avertable dose. Sheltering: 10 mSv within two days (effective dose); Iodine prophylaxis: National recommendations; Evacuation: 50 mSv within one week (effective dose); Temporary relocation: No predetermined intervention level; Permanent resettlement: No predetermined intervention level. Workers

  13. Amendments to the U.S. Environmental Protection Agency's public health and environmental radiation protection standards for Yucca Mountain, Nevada (40 CFR PART 197) - 16156

    International Nuclear Information System (INIS)

    Clark, Raymond L.; Czyscinski, Kenneth; Rosnick, Reid J.; Schultheisz, Daniel

    2009-01-01

    In 2001, as directed by the Energy Policy Act of 1992, the United States Environmental Protection Agency (EPA) issued public health and environmental radiation protection standards for the proposed repository at Yucca Mountain, Nevada. Several parties sued the Agency on numerous aspects of the rule. A Federal Court upheld EPA on all counts except for the compliance period associated with the individual-protection standard, which the Agency had limited to 10,000 years for a number of technical and policy reasons. However, the National Academy of Sciences WAS) had recommended that the standard be set for the time of peak risk, within the limits imposed by the long-term stability of the geologic environment, which NAS estimated at 1 million years. EPA's standards required that the Department of Energy (DOE) project doses to the time of peak dose but did not apply a compliance standard to these longer term projections. The Court ruled that EPA's 10,000-year compliance period was inconsistent with the NAS recommendation. This aspect of the rule was vacated and remanded to the Agency for revision. In 2005, EPA proposed amendments to the standards. Following public hearings and a public review period, the final amendments were issued in September 2008. This paper discusses the new requirements. (authors)

  14. Environmental radioactivity in Canada - 1982

    International Nuclear Information System (INIS)

    Tracey, B.L.

    1984-01-01

    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. Special investigations were carried out during 1982 on metabolism of natural radionuclides and on the accumulation of radon in energy-efficient homes. The pre-operational phase of the monitoring program at the Point Lepreau Nuclear Generating Station was completed. Dose commitments have been estimated for the ongoing natural radioactivity, fallout and reactor studies. All measurements made during the year are below the limits recommended by the International Commission on Radiological Protection

  15. Recommended treatment for urinary tract infection in pregnancy.

    Science.gov (United States)

    Vercaigne, L M; Zhanel, G G

    1994-02-01

    To establish and recommend a therapeutic regimen for the treatment of urinary tract infection (UTI) in pregnancy based on the published studies. An English-language literature search employing MEDLINE, Index Medicus, and bibliographic reviews of the references obtained were searched (key terms: urinary tract infection, UTI, pregnancy, bacteriuria). All identified human studies dealing with bacteriuria or UTI in pregnancy were analyzed. Limited data are available regarding the appropriate antibiotic management of UTI in pregnancy. Single-dose cure rates with amoxicillin are approximately 80 percent. Trimethoprim/sulfamethoxazole provides cure rates of greater than 80 percent. Cephalosporins and nitrofurantoin produce variable results. We recommend separating pregnant subjects with UTI into two groups. Those with asymptomatic bacteriuria can be treated with a single dose of an antimicrobial to which the organism is susceptible. For those with symptomatic UTI, we recommend amoxicillin 500 mg tid for three days. Urine cultures should be repeated seven days following therapy to assess cure or failure. Well-designed studies need to be performed, comparing single-dose and three-day therapy for UTI in pregnancy.

  16. Environmental pathways and radiological dosimetry for biota

    International Nuclear Information System (INIS)

    Blaylock, B.G.

    1997-01-01

    Radionuclides entering the environment as a result man's activities may be transported, cycled, and/or concentrated in the biotic and abiotic compartments of the ecosystem. Organisms in an environment contaminated with radioactive waste may be irradiated externally by radionuclides in air, water, vegetation, soil or sediment and internally by radionuclides accumulated within their bodies by inhalation or by direct absorption through their skin. The purpose of this paper is to examine the pathways in which biota are exposed to radioactive releases to the environment and to review the methods used to calculate radiation doses to the biota. In general, the methodology for estimating radiation doses to biota in their natural environment is better developed for aquatic biota than for terrestrial biota. The different methodologies which have been used for calculating radiation doses to aquatic biota were reviewed. If the protection of non-human biota is an issue in addressing environmental assessments of nuclear facilities, then the methodology for estimating radiation doses to biota should be improved. It is recommended that dose calculations should be simplified and standardized by developing dose conversion factors for a number of generic aquatic and terrestrial organisms. (author)

  17. Background dose subtraction in personnel dosimetry

    International Nuclear Information System (INIS)

    Picazo, T.; Llorca, N.; Alabau, J.

    1997-01-01

    In this paper it is proposed to consider the mode of the frequency distribution of the low dose dosemeters from each clinic that uses X rays as the background environmental dose that should be subtracted from the personnel dosimetry to evaluate the doses due to practice. The problems and advantages of this indirect method to estimate the environmental background dose are discussed. The results for 60 towns are presented. (author)

  18. Insignificant levels of dose

    International Nuclear Information System (INIS)

    Webb, G.A.M.; McLean, A.S.

    1977-01-01

    The procedures recommended by the International Commission on Radiological Protection (ICRP) for making decisions concerning controllable sources of radiation exposure of the public include 'justification' and 'optimisation'. The tool recommended by the ICRP for reaching these decisions is collective dose or dose commitment supplemented by consideration of doses to individuals. In both these considerations the practical problem arises of whether very small doses to large numbers of people should contribute to the final decision-making process. It may be that at levels of dose which are small increments on natural background, the relationship between dose and effect is linear even though the slope may be close to zero. If so, collective dose is a meaningful concept and the calculation of total detriment for the purpose of justification could legitimately include all doses. In the calculation of collective doses for the purpose of optimisation, which involves decisions on how much money or resource should be allocated to dose reduction, it is necessary to appraise radiation detriment realistically. At low levels of dose to the individual such as those small by comparison with variations in natural background within the UK, the risk to the individual is such that his well-being will not be significantly changed by the presence or absence of the radiation dose. These small doses, which are well below the point at which an individual attaches significance, should not carry a societal significance. Societal acceptance of risk is analysed with a view to assessing a level of possible risk, and hence dose, below which resources should not in general be diverted to secure further reduction. A formulation for collective dose commitment is proposed incorporating a cut-off to exclude insignificant doses. The implications of this formulation in practical situations are discussed

  19. On the new recommendation of the International Commission on Radiological Protection. Publication 60

    International Nuclear Information System (INIS)

    Chukhin, S.G.

    1994-01-01

    The International Commission on Radioligical Protection (ICRP) published in 1990 new main recommendations (Publication 60), in which the recommendations of 1977 (Publication 26) were revised and noticeable changes were introduced. The main changes in ICRP recommendations important for practical personnel are discussed. These important changes include introduction of two protection systems, which are the protection system in practice and that during intervention, conception of potential irradiation, dose and risk limits, changes in dose limits and risk coefficients, determination of the effective dose and its numerical values by changing the weighting coefficients. The problems open to arguments are formulated

  20. Manipulating Sensory and Phytochemical Profiles of Greenhouse Tomatoes Using Environmentally Relevant Doses of Ultraviolet Radiation.

    Science.gov (United States)

    Dzakovich, Michael P; Ferruzzi, Mario G; Mitchell, Cary A

    2016-09-14

    Fruits harvested from off-season, greenhouse-grown tomato plants have a poor reputation compared to their in-season, garden-grown counterparts. Presently, there is a gap in knowledge with regard to the role of UV-B radiation (280-315 nm) in determining greenhouse tomato quality. Knowing that UV-B is a powerful elicitor of secondary metabolism and not transmitted through greenhouse glass and some greenhouse plastics, we tested the hypothesis that supplemental UV-B radiation in the greenhouse will impart quality attributes typically associated with garden-grown tomatoes. Environmentally relevant doses of supplemental UV-B radiation did not strongly affect antioxidant compounds of fruits, although the flavonol quercetin-3-O-rutinoside (rutin) significantly increased in response to UV-B. Physicochemical metrics of fruit quality attributes and consumer sensory panels were used to determine if any such differences altered consumer perception of tomato quality. Supplemental UV-A radiation (315-400 nm) pre-harvest treatments enhanced sensory perception of aroma, acidity, and overall approval, suggesting a compelling opportunity to environmentally enhance the flavor of greenhouse-grown tomatoes. The expression of the genes COP1 and HY5 were indicative of adaptation to UV radiation, which explains the lack of marked effects reported in these studies. To our knowledge, these studies represent the first reported use of environmentally relevant doses of UV radiation throughout the reproductive portion of the tomato plant life cycle to positively enhance the sensory and chemical properties of fruits.

  1. MILDOS - a computer program for calculating environmental radiation doses from uranium recovery operations. Research report

    International Nuclear Information System (INIS)

    Strenge, D.L.; Bander, T.J.

    1981-04-01

    MILDOS is a Fortran Computer Code which calculates the dose commitments received by individuals and the general population within an 80 kilometer radius of an operating uranium recovery facility. In addition air and ground concentrations are presented for individual locations, as well as for a generalized population grid. Extra-regional population doses resulting from transport of radon and export of agricultural produce are also displayed. The transport of radiological emissions from point and area sources is predicted by using a sector-averaged Gaussian plume dispersion model. Mechanisms such as radioactive decay, plume depletion by deposition, ingrowth of daughter products and resuspension of deposited radionuclides are included in the transport model. Alterations in operation throughout the facility's lifetime can be accounted for in the input stream. The pathways considered are: inhalation; external exposure from ground shine and cloud immersion; and ingestion of vegetables, meat and milk. Dose commitments are calculated primarily on the basis of the recommendations of the International Commission on Radiological Protection (ICRP). Predictive 40 CFR 190 and 10 CFR 20 compliances are also performed. This computer code is designed primarily for uranium milling facilities and should not be used for operations with different radionuclides or processes

  2. Comparison of Current Recommended Regimens of Atropinization in Organophosphate Poisoning

    OpenAIRE

    Connors, Nicholas J.; Harnett, Zachary H.; Hoffman, Robert S.

    2013-01-01

    Atropine is the mainstay of therapy in organophosphate (OP) toxicity, though research and consensus on dosing is lacking. In 2004, as reported by Eddleston et al. (J Toxicol Clin Toxicol 42(6):865-75, 2004), they noted variation in recommended regimens. We assessed revisions of original references, additional citations, and electronic sources to determine the current variability in atropine dosing recommendations. Updated editions of references from Eddleston et al.’s work, texts of Internal ...

  3. When is a dose not a dose?

    International Nuclear Information System (INIS)

    Green, Patrick

    1992-01-01

    There is confusion over radiation dose limits between the International Commission on Radiological Protection, the National Radiological Protection Board and the Ministry of Agriculture, Fisheries and Food (MAFF), reports a Friends of the Earth's radiation campaigner. MAFF is suggesting the inadequate ICRP public dose limit does not apply to public exposures which arise from environmental contamination from past radioactive discharges. (author)

  4. Radiation-induced cataracts: the Health Protection Agency's response to the ICRP statement on tissue reactions and recommendation on the dose limit for the eye lens.

    Science.gov (United States)

    Bouffler, Simon; Ainsbury, Elizabeth; Gilvin, Phil; Harrison, John

    2012-12-01

    This paper presents the response of the Health Protection Agency (HPA) to the 2011 statement from the International Commission on Radiological Protection (ICRP) on tissue reactions and recommendation of a reduced dose limit for the lens of the eye. The response takes the form of a brief review of the most recent epidemiological and mechanistic evidence. This is presented together with a discussion of dose limits in the context of the related risk and the current status of eye dosimetry, which is relevant for implementation of the limits. It is concluded that although further work is desirable to quantify better the risk at low doses and following protracted exposures, along with research into the mechanistic basis for radiation cataractogenesis to inform selection of risk projection models, the HPA endorses the conclusion reached by the ICRP in their 2011 statement that the equivalent dose limit for the lens of the eye should be reduced from 150 to 20 mSv per year, averaged over a five year period, with no year's dose exceeding 50 mSv.

  5. Argonne National Laboratory-East site environmental report for calendar year 1999

    International Nuclear Information System (INIS)

    Golchert, N. W.; Kolzow, R. G.

    2000-01-01

    This report discusses the results of the environmental protection program at Argonne National Laboratory-East (ANL-E) for 1999. To evaluate the effects of ANL-E operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the ANL-E site were analyzed and compared with applicable guidelines and standards. A variety of radionuclides were measured in air, surface water, on-site groundwater, and bottom sediment samples. In addition, chemical constituents in surface water, groundwater, and ANL-E effluent water were analyzed. External penetrating radiation doses were measured, and the potential for radiation exposure to off-site population groups was estimated. Results are interpreted in terms of the origin of the radioactive and chemical substances (i.e., natural, fallout, ANL-E, and other) and are compared with applicable environmental quality standards. A US Department of Energy dose calculation methodology, based on International Commission on Radiological Protection recommendations and the US Environmental Protection Agency's CAP-88 (Clean Air Act Assessment Package-1988) computer code, was used in preparing this report. The status of ANL-E environmental protection activities with respect to the various laws and regulations that govern waste handling and disposal is discussed, along with the progress of environmental corrective actions and restoration projects

  6. Argonne National Laboratory-East site environmental report for calendar year 1998

    International Nuclear Information System (INIS)

    Golchert, N.W.; Kolzow, R.G.

    1999-01-01

    This report discusses the results of the environmental protection program at Argonne National Laboratory-East (ANL-E) for 1998. To evaluate the effects of ANL-E operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the ANL-E site were analyzed and compared with applicable guidelines and standards. A variety of radionuclides were measured in air, surface water, on-site groundwater, and bottom sediment samples. In addition, chemical constituents in surface water, groundwater, and ANL-E effluent water were analyzed. External penetrating radiation doses were measured, and the potential for radiation exposure to off-site population groups was estimated. Results are interpreted in terms of the origin of the radioactive and chemical substances (i.e., natural, fallout, ANL-E, and other) and are compared with applicable environmental quality standards. A US Department of Energy dose calculation methodology, based on International Commission on Radiological Protection recommendations and the US Environmental Protection Agency's CAP-88 (Clean Air Act Assessment Package-1988) computer code, was used in preparing this report. The status of ANL-E environmental protection activities with respect to the various laws and regulations that govern waste handling and disposal is discussed, along with the progress of environmental corrective actions and restoration projects

  7. Comments on the recommendations of the International Commission on Radiological Protection

    Energy Technology Data Exchange (ETDEWEB)

    Pochin, E E; Rock Carling, Ernest; Court Brown, W M [Medical Research Council, Committee on Protection against Ionizing Radiations, London (United Kingdom); and others

    1960-12-01

    Full text: The Medical Research Council's Committee on Protection against Ionizing Radiations has considered the recommendations of the International Commission on Radiological Protection adopted September 9th, 1958 (Pergamon Press, 1959), and the explanatory statement and amendments to the 1958 recommendations made at the 1959 meeting of the Commission (Brit. J. Radiol., 1960, 33, 189). Subject to the following comments, the Committee advocates the acceptance of the Commission's recommendations. The text of these recommendations is not reproduced here and requires to be read in conjunction with these comments. References below to numbered paragraphs refer to the text of the Commission's recommendations. Occupational exposure - 1. The formula given in para. 47 relates the maximum permissible total occupational dose accumulated in the gonads or certain other organs to the age of a subject above the age of 18 by the relationship D= 5 (N - 8) where D is the tissue dose in rems and N is the age in years. The Committee notes that this formula would permit a maximum dose to the gonads of 60 rems by age 30 and is of the opinion that this dose is acceptable provided that the contribution from this source to the genetic dose for the whole population does not exceed I rem per head of population. 2. The Commission recommends (para. 51c) that, when a person begins to be occupationally exposed at an age of less than 18 years, the dose to various specified tissues shall not exceed 5 rems in any one year under age 18, and the dose accumulated to age 30 shall not exceed 60 rems. The Committee recommends that those persons between the ages of 6 and 18 years who are in occupational contact with radiation should not be allowed to receive, as a result of their occupation. an annual dose in excess of 1-5 rems. This should be sufficient to allow the training of such persons in the use of ionizing radiations in hospitals, industrial establishments, technical colleges and schools. However

  8. A work bibliography on native food consumption, demography and lifestyle. Hanford Environmental Dose Reconstruction Project

    Energy Technology Data Exchange (ETDEWEB)

    Murray, C.E.; Lee, W.J.

    1992-12-01

    The purpose of this report is to provide a bibliography for the Native American tribe participants in the Hanford Environmental Dose Reconstruction (HEDR) Project to use. The HEDR Project`s primary objective is to estimate the radiation dose that individuals could have received as a result of emissions since 1944 from the US Department of Energy`s Hanford Site near Richland, Washington. Eight Native American tribes are responsible for estimating daily and seasonal consumption of traditional foods, demography, and other lifestyle factors that could have affected the radiation dose received by tribal members. This report provides a bibliography of recorded accounts that tribal researchers may use to verify their estimates. The bibliographic citations include references to information on the specific tribes, Columbia River plateau ethnobotany, infant feeding practices and milk consumption, nutritional studies and radiation, tribal economic and demographic characteristics (1940--1970), research methods, primary sources from the National Archives, regional archives, libraries, and museums.

  9. Environmental components of OCS policy committee recommendations regarding national oil spill prevention and response program

    International Nuclear Information System (INIS)

    Groat, C.G.; Thorman, J.

    1991-01-01

    The Exxon Valdez oil spill of March 24, 1989 resulted in thousands of pages of analytical reports assessing the environmental, organizational, legal, procedural, social, economic, and political aspects of the event. Even though the accident was a transportation incident, it had a major impact on the public and political perception of offshore oil operations. This caused the OCS Policy Committee, which advises the Secretary of the Interior and the Minerals Management Service on Outer Continental Shelf resource development and environmental matters, to undertake a review of the reports for the purpose of developing recommendations to the secretary for improvements in OCS operations that would insure maximum efforts to prevent spills and optimal ability to deal with any that occur. The Committee felt strongly that 'a credible national spill prevention and response program from both OCS and non-OCS oil spills in the marine environment is needed to create the political climate for a viable OCS program.' The report of the Committee described eight essential elements of this program; four of these focused on the environmental aspects of oil spills, calling for (1) adequate characterization of the marine and coastal environment, including both information and analysis, accessible to decision makers, (2) the capacity to restore economic and environmental resources as quickly as possible if damage occurs, (3) a mechanism for research on oil spill impacts, and (4) a meaningful role for all interested and responsible parties, including the public, in as many of these activities as possible, from spill prevention and contingency planning to environmental oversight of ongoing operations and participation in clean-up and restoration activities

  10. Environmental and effluent monitoring at ANSTO sites, 2005-2006

    International Nuclear Information System (INIS)

    Hoffmann, Emmy L.; Loosz, Tom; Ferris, John M.; Harrison, Jennifer J.

    2006-01-01

    This report presents the results of ANSTO's environmental and effluent monitoring at the Lucas Heights Science and Technology Centre (LHSTC) and the National Medical Cyclotron (NMC) sites, from July 2005 to June 2006. Estimated effective doses to the critical group of members of the public potentially affected by routine airborne emissions from the LHSTC were less than 0.005 mSv/year. The maximum potential dose was 23% of the ANSTO ALARA objective of 0.02 mSv/year, much lower than the public dose limit of 1 mSv/year that is recommended by the Australian Radiation Protection and Nuclear Safety Agency (ARPANSA). The effective doses to the critical group of members of the public potentially exposed to routine liquid effluent releases from the LHSTC have been realistically estimated as a quarter (or less) of the estimated doses to the critical group for airborne releases. The median tritium concentrations detected in groundwater and surface waters at the LHSTC were typically less than 2% of those set out in the Australian Drinking Water Guidelines. The airborne emissions from the NMC were below the ARPANSA-approved notification levels. Results of environmental monitoring at both ANSTO sites confirm that the facilities continue to be operated well within regulatory limits. ANSTO's routine operations at the LHSTC and NMC make only a very small addition to the natural background radiation dose of -1.5 mSv/year experienced by members of the Australian public

  11. Heterogeneity of Rabies Vaccination Recommendations across Asia

    Directory of Open Access Journals (Sweden)

    Philippe Buchy

    2017-07-01

    Full Text Available Asian countries bear the greatest burden of the disease, with a majority (59% of rabies-related deaths occurring in Asia. In order to promote best practices, we summarized national human vaccination guidelines across this region, to highlight differences and similarities and to discuss the aspects that would benefit from updates. National management guidelines for rabies were retrieved from various sources to extract information on rabies pre- and post-exposure prophylaxis (PrEP, and PEP, booster vaccination, and route of administration. Rabies guidelines recommendations for wound management and PrEP across Asia are broadly aligned to the World Health Organization (WHO guidelines. For PEP, the 5-dose Essen, and the 4-dose Zagreb are the regimens of choice for intramuscular (IM, and the Thai Red Cross regimen for intradermal (ID, administration. Several national guidelines have yet to endorse ID vaccine administration. Most guidelines recommend rabies immunoglobulin in category III exposures. Booster recommendations are not included in all guidelines, with limited clarity on booster requirement across the spectrum of risk of rabies exposure. In conclusion, national recommendations across Asian countries differ and while some guidelines are closely aligned to the WHO recommendations, resource-saving ID administration and use of rational abbreviated schedules have yet to be endorsed.

  12. Offsite radiation doses from Hanford Operations for the years 1983 through 1987: A comparison of results calculated by two methods

    International Nuclear Information System (INIS)

    Soldat, J.K.

    1989-10-01

    This report compares the results of the calculation of potential radiation doses to the public by two different environmental dosimetric systems for the years 1983 through 1987. Both systems project the environmental movement of radionuclides released with effluents from Hanford operations; their concentrations in air, water, and foods; the intake of radionuclides by ingestion and inhalation; and, finally, the potential radiation doses from radionuclides deposited in the body and from external sources. The first system, in use for the past decade at Hanford, calculates radiation doses in terms of 50-year cumulative dose equivalents to body organs and to the whole body, based on the methodology defined in ICRP Publication 2. This system uses a suite of three computer codes: PABLM, DACRIN, and KRONIC. In the new system, 50-year committed doses are calculated in accordance with the recommendations of the ICRP Publications 26 and 30, which were adopted by the US Department of Energy (DOE) in 1985. This new system calculates dose equivalent (DE) to individual organs and effective dose equivalent (EDE). The EDE is a risk-weighted DE that is designed to be an indicator of the potential health effects arising from the radiation dose. 16 refs., 1 fig., 38 tabs

  13. Application of the ICRP recommendations to revised secondary radiation protection standards

    International Nuclear Information System (INIS)

    Kennedy, W.E. Jr.; Corley, J.P.

    1988-01-01

    In 1977, the International Commission on Radiological Protection (ICRP) issued Publication No. 26 containing its recommendations for major changes in the conceptual basis for radiation protection. The new recommendations consider total risk (to the whole body) instead of controlling (critical-organ) risk. Subsequent publications and explanatory statements most useful for providing clarification of the intent of the new recommendations have not resolved practical problems encountered in attempting to apply them to either occupational or public exposures. Some of the problems that still exist in applying these recommendations for estimating doses to members of the public include the following: allowance for age differences within an exposed population group, definition of 50-y dose versus lifetime (70-y) dose, definition of negligible risk levels for individual and collective doses, and derivation of appropriate concentration guidelines. The United States is in the process of adopting the revised recommendations of the ICRP. In addition to adopting versions of the primary radiation protection standards, both the U.S. Nuclear Regulatory Commission and the U.S. Department of Energy have developed draft secondary standards that are similar to the Derived Air Concentration values given by the ICRP. This paper presents a brief history of the development of these revised secondary standards, discusses their technical bases, provides a comparison of them, and discusses their limitations and potential misapplication

  14. International and national radiation protection standards and recommendations

    International Nuclear Information System (INIS)

    Swindon, T.N.

    1989-01-01

    The recommendations of the International Commission on Radiological Protection (ICRP) and their basis are discussed with particular emphasis on the extensive review of its earlier recommendations undertaken by the ICRP during the 1970s. The new recommendations issued in 1977 after this review are described. The dose limits for various organs and tissues before and after 1977 are compared. The optimization principle contained in the 1977 recommendations is assessed. The implementation of the 1977 recommendations, the subsequent changes to them and the ICRP's 1987 statement on cancer risk assessments are discussed. The National Radiological Protection Board's October 1987 radiation protection recommendations are outlined. 8 refs., 1 fig

  15. Literature and data review for the surface-water pathway: Columbia River and adjacent coastal areas. Hanford Environmental Dose Reconstruction Project

    Energy Technology Data Exchange (ETDEWEB)

    Walters, W.H.; Dirkes, R.L.; Napier, B.A.

    1992-11-01

    As part of the Hanford Environmental Dose Reconstruction (HEDR) Project, Battelle, Pacific Northwest Laboratories reviewed literature and data on radionuclide concentrations and distribution in the water, sediment, and biota of the Columbia River and adjacent coastal areas. Over 600 documents were reviewed including Hanford reports, reports by offsite agencies, journal articles, and graduate theses. Radionuclide concentration data were used in preliminary estimates of individual dose for the period 1964 through 1966. This report summarizes the literature and database reviews and the results of the preliminary dose estimates.

  16. Observations and recommendations for further research regarding environmentally assisted fatigue evaluation methods

    Energy Technology Data Exchange (ETDEWEB)

    Stevens, G.L.; Tregoning, R.L. [U.S. Nuclear Regulatory Commission (U.S. NRC), Rockville, MD (United States); Chopra, O.K. [Argonne National Laboratory, Argonne, IL (United States)

    2014-07-01

    The U.S. Nuclear Regulatory Commission (NRC) and Argonne National Laboratory (ANL) have completed research activities on environmentally assisted fatigue (EAF) methods. This work has led to a revision of NUREG/CR-6909 in its entirety, a draft of which is forthcoming for public review and comment. These activities addressed the following areas: - Air and water fatigue curves were re-developed using a much larger fatigue (ε-N) database. The additional data include an expansion in the ε-N data previously used by the NRC and ANL by as much as 50%. - The environmental fatigue multiplier (F{sub en}) expressions for carbon, low-alloy, stainless, and nickel-alloy steels were revised. - The revised F{sub en} expressions address comments from interested stakeholders related to: (a) the constants in previous F{sub en} expressions that results in F{sub en} values of approximately 2.0 even when the strain rate is very high or the temperature is very low, (b) the temperature dependence of the F{sub en} expression for carbon and low-alloy steels, and (c) the dependence of F{sub en} on water chemistry for austenitic stainless steels. - In addition, the appropriateness of a strain threshold and the possible effects of hold periods were evaluated. - The potential effects of dynamic strain aging (DSA) on cyclic deformation and environmental effects were discussed. - The revised F{sub en} expressions proposed were validated to the extent possible by comparing the results of five different experimental data sets obtained from fatigue tests that simulate actual plant conditions to estimates of fatigue usage adjusted for environmental effects using the updated F{sub en} expressions. In the course of performing the foregoing EAF research activities, the NRC and ANL observed several areas where further research could yield reduced conservatism in EAF evaluation. These include more refined, material-specific fatigue (S-N) curves, S-N curves for ferritic materials based on material tensile

  17. Building credibility in public studies: Lessons learned from the Hanford environmental Dose Reconstruction project may apply to all public studies

    International Nuclear Information System (INIS)

    Till, J.E.

    1995-01-01

    This article describes the process by which the author came to recognize the importance of openness to the public in environmental studies, during the Hanford Environmental Dose Reconstruction Project. Using the Dose reconstruction public involvement, the article goes on to describe a general guide to the construction of a new, positive framework for conducting future public studies. The steps include the following: putting the public in the study; building credibility into a public study (1 -search for proof in historical records; 2-define the domain and the exposed population; 3-characterize the material released; 4-identify key materials, pathways and receptors; 5-encouraging public participation; 6 -explaining the meaning of the results) and reconciling scientific and public issues

  18. Building credibility in public studies: Lessons learned from the Hanford environmental Dose Reconstruction project may apply to all public studies

    Energy Technology Data Exchange (ETDEWEB)

    Till, J.E. [Radiological Assessment Corp., Neeses, SC (United States)

    1995-09-01

    This article describes the process by which the author came to recognize the importance of openness to the public in environmental studies, during the Hanford Environmental Dose Reconstruction Project. Using the Dose reconstruction public involvement, the article goes on to describe a general guide to the construction of a new, positive framework for conducting future public studies. The steps include the following: putting the public in the study; building credibility into a public study (1 -search for proof in historical records; 2-define the domain and the exposed population; 3-characterize the material released; 4-identify key materials, pathways and receptors; 5-encouraging public participation; 6 -explaining the meaning of the results) and reconciling scientific and public issues.

  19. Recommendations for the determination of absorbed doses in curietherapy. CFMRI no. 1 report

    International Nuclear Information System (INIS)

    1983-01-01

    The aim of the Comite Francais ''mesure des Rayonnements ionisants'' (C.F.M.R.I.) is to prepare recommendations dealing with: numerical values of constant data or radiometrological parameters, methodology of measurement, etc... These recommendations are complementary to recommendations of international organizations such as International commission radiation units (ICRU) [fr

  20. Environmental dose in the Nuclear Medicine Department of the National Institute of Cancer

    International Nuclear Information System (INIS)

    Torres U, C. L.; Avila A, O. L.; Medina V, L. A.; Buenfil B, A. E.; Brandan S, M. E.; Trujillo Z, F. E.; Gamboa de Buen, I.

    2009-01-01

    The dosimeters TLD-100 and TLD-900 were used to know the levels of environmental dose in areas of the Nuclear Medicine Department of the National Institute of Cancer. The dosimeters calibration was carried out in the Metrology Department of the National Institute of Nuclear Research. The radioisotopes used in the studied areas are 131 I, 18 F, 67 Ga, 99m Tc, 111 In, 201 Tl and 137 Cs with gamma energies between 93 and 662 KeV. Dosimeters were placed during five months in the diagnostic, injection, waiting and PET rooms as well as hot room, waste room, enclosed corridors to patient rooms treated with 131 I and 137 Cs and witness dosimeters to know the bottom. The values found vary between 0.3 and 70 major times that those of bottom. The maximum doses were measured in the waste room and in the enclosed corridor to the patient rooms with cervical uterine cancer treated with 137 Cs. (Author)

  1. A new perspective on the ICRP's new draft recommendations

    International Nuclear Information System (INIS)

    Clarke, R.

    1990-01-01

    The final text of the new recommendations of the International Commission on Radiation Protection is due to be published in the first quarter of 1991. The recommendations consist of a main text supported by the three major appendices: quantities and units; biological effects of ionising radiation; and criteria for judging the significance of the effects of radiation. Aspects of the report considered here are: risk estimates; radiation detriment including fatal and non-fatal cancers and hereditary defects; the system of protection; dose and risks limits; the concept of a dose constraint; quantities and units. (author)

  2. Evaluation of the sterility of single-dose medications used in a multiple-dose fashion.

    Science.gov (United States)

    Martin, Elizabeth P; Mukherjee, Jean; Sharp, Claire R; Sinnott-Stutzman, Virginia B

    2017-11-01

    Bacterial proliferation was evaluated in single-dose medications used in a multi-dose fashion and when medications were intentionally inoculated with bacteria. Of 5 experimentally punctured medications, 1 of 75 vials (50% dextrose) became contaminated. When intentionally inoculated, hydroxyethyl starch and heparinized saline supported microbial growth. Based on these findings, it is recommended that hydroxyethyl starch and heparinized saline not be used in a multi-dose fashion.

  3. Update on pediatric resuscitation drugs: high dose, low dose, or no dose at all.

    Science.gov (United States)

    Sorrentino, Annalise

    2005-04-01

    Pediatric resuscitation has been a topic of discussion for years. It is difficult to keep abreast of changing recommendations, especially for busy pediatricians who do not regularly use these skills. This review will focus on the most recent guidelines for resuscitation drugs. Three specific questions will be discussed: standard dose versus high-dose epinephrine, amiodarone use, and the future of vasopressin in pediatric resuscitation. The issue of using high-dose epinephrine for cardiopulmonary resuscitation refractory to standard dose epinephrine has been a topic of debate for many years. Recently, a prospective, double-blinded study was performed to help settle the debate. These results will be reviewed and compared with previous studies. Amiodarone is a medication that was added to the pediatric resuscitation algorithms with the most recent recommendations from the American Heart Association in 2000. Its use and safety will also be discussed. Another topic that is resurfacing in resuscitation is the use of vasopressin. Its mechanism and comparisons to other agents will be highlighted, although its use in the pediatric patient has not been thoroughly studied. Pediatric resuscitation is a constantly evolving subject that is on the mind of anyone taking care of sick children. Clinicians are continually searching for the most effective methods to resuscitate children in terms of short- and long-term outcomes. It is important to be familiar with not only the agents being used but also the optimal way to use them.

  4. Drug dosing in chronic kidney disease.

    Science.gov (United States)

    Gabardi, Steven; Abramson, Stuart

    2005-05-01

    Patients with chronic kidney disease (CKD) are at high risk for adverse drug reactions and drug-drug interactions. Drug dosing in these patients often proves to be a difficult task. Renal dysfunction-induced changes in human pathophysiology regularly results may alter medication pharmacodynamics and handling. Several pharmacokinetic parameters are adversely affected by CKD, secondary to a reduced oral absorption and glomerular filtration; altered tubular secretion; and reabsorption and changes in intestinal, hepatic, and renal metabolism. In general, drug dosing can be accomplished by multiple methods; however, the most common recommendations are often to reduce the dose or expand the dosing interval, or use both methods simultaneously. Some medications need to be avoided all together in CKD either because of lack of efficacy or increased risk of toxicity. Nevertheless, specific recommendations are available for dosing of certain medications and are an important resource, because most are based on clinical or pharmacokinetic trials.

  5. Area and environmental gamma dose monitoring at PINSTECH

    International Nuclear Information System (INIS)

    Javed, M.; Awan, M.A.; Ahmad, S.; Afsar, M.; Orfi, S.D.

    1986-11-01

    Radiation dose monitoring of various radioactive laboratories including PARR building, radioactive waste disposal area and the environment upto initial peripheral limits of PINSTECH has been carried out by TLD's installed at different locations. Average dose rates in terms of percentage of dose limits have been compiled. The results for the year 1985 have been discussed in this report. (author)

  6. Argonne National Laboratory-East site environmental report for calendar year 1992

    International Nuclear Information System (INIS)

    Golchert, N.W.; Kolzow, R.G.

    1993-05-01

    This report discusses the results of the Environmental Protection Program at Argonne National Laboratory-East (ANL) for 1992. To evaluate the effects of ANL operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the ANL site were analyzed and compared to applicable guidelines and standards. A variety of radionuclides was measured in air, surface water, groundwater, soil, grass, and bottom sediment samples. In addition, chemical constituents in surface water, groundwater, and ANL effluent water were analyzed. External penetrating radiation doses were measured and the potential for radiation exposure to off-site population groups was estimated. The results of the surveillance program are interpreted in terms of the origin of the radioactive and chemical substances (natural, fallout, ANL, and other) and are compared with applicable environmental quality standards. A US Department of Energy (DOE) dose calculation methodology, based on International Commission on Radiological Protection (ICRP) recommendations and the CAP-88 version of the EPA-AIRDOSE/RADRISK computer code, is used in this report. The status of ANL environmental protection activities with respect to the various laws and regulations which govern waste handling and disposal is discussed

  7. Argonne National Laboratory-East site environmental report for calendar year 1992

    Energy Technology Data Exchange (ETDEWEB)

    Golchert, N.W.; Kolzow, R.G.

    1993-05-01

    This report discusses the results of the Environmental Protection Program at Argonne National Laboratory-East (ANL) for 1992. To evaluate the effects of ANL operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the ANL site were analyzed and compared to applicable guidelines and standards. A variety of radionuclides was measured in air, surface water, groundwater, soil, grass, and bottom sediment samples. In addition, chemical constituents in surface water, groundwater, and ANL effluent water were analyzed. External penetrating radiation doses were measured and the potential for radiation exposure to off-site population groups was estimated. The results of the surveillance program are interpreted in terms of the origin of the radioactive and chemical substances (natural, fallout, ANL, and other) and are compared with applicable environmental quality standards. A US Department of Energy (DOE) dose calculation methodology, based on International Commission on Radiological Protection (ICRP) recommendations and the CAP-88 version of the EPA-AIRDOSE/RADRISK computer code, is used in this report. The status of ANL environmental protection activities with respect to the various laws and regulations which govern waste handling and disposal is discussed.

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

    International Nuclear Information System (INIS)

    Beamish, David

    2014-01-01

    technologically enhanced, localised contributions to dose rate values are also apparent in the data sets. Two detailed examples are provided that reveal the detectability of site-scale environmental impacts due to former industrial activities and the high dose values (>500 nGy h −1 ) that are associated with former, small-scale Uranium mining operations. - Highlights: • UK airborne estimates of dose rates have been obtained across 40,000 km 2 . • Spatial mapping densities range from 10 to 50 m. • Wide scale (geological) and localized (technological) effects are quantified. • Theory and data indicate soil attenuation effects are pervasive. • Comparison of ground geochemical and airborne dose estimates

  9. FY 1991 project plan for the Hanford Environmental Dose Reconstruction Project, Phase 2

    International Nuclear Information System (INIS)

    1991-02-01

    Phase 1 of the Hanford Environmental Dose Reconstruction Project was designed to develop and demonstrate a method for estimating radiation doses people may have received from Hanford Site operations since 1944. The method researchers developed relied on a variety of measured and reconstructed data as input to a modular computer model that generates dose estimates and their uncertainties. As part of Phase 1, researchers used the reconstructed data and computer model to calculate preliminary dose estimates for populations in a limited geographical area and time period. Phase 2, now under way, is designed to evaluate the Phase 1 data and model and improve them to calculate more accurate and precise dose estimates. Phase 2 will also be used to obtain preliminary estimates of two categories of doses: for Native American tribes and for individuals included in the pilot phase of the Hanford Thyroid Disease Study (HTDS). TSP Directive 90-1 required HEDR staff to develop Phase 2 task plans for TSP approval. Draft task plans for Phase 2 were submitted to the TSP at the October 11--12, 1990 public meeting, and, after discussions of each activity and associated budget needs, the TSP directed HEDR staff to proceed with a slate of specific project activities for FY 1991 of Phase 2. This project plan contains detailed information about those activities. Phase 2 is expected to last 15--18 months. In mid-FY 1991, project activities and budget will be reevaluated to determine whether technical needs or priorities have changed. Separate from, but related to, this project plan, will be an integrated plan for the remainder of the project. HEDR staff will work with the TSP to map out a strategy that clearly describes ''end products'' for the project and the work necessary to complete them. This level of planning will provide a framework within which project decisions in Phases 2, 3, and 4 can be made

  10. Argonne National Laboratory-East site environmental report for calendar year 1989

    International Nuclear Information System (INIS)

    Golchert, N.W.; Duffy, T.L.

    1990-04-01

    This report discusses the results of the environmental monitoring program at Argonne National Laboratory (ANL) for 1989. To evaluate the effects of ANL operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the ANL site were analyzed and compared. A variety of radionuclides were measured in air, surface water, groundwater, soil, grass, bottom sediment, and milk samples. In addition, chemical constituents in surface water, groundwater, and ANL effluent water were analyzed. External penetrating radiation doses were measured and the potential for radiation exposure to off-site population groups was estimated. The results of the monitoring program are interpreted in terms of the origin of the radioactive and chemical substances (natural, fallout, ANL, and other) and are compared with applicable environmental quality standards. A US Department of Energy (DOE) dose calculation methodology, based on International Commission on Radiological Protection (ICRP) recommendations, is used in this report. This report also discusses progress being made on corrective actions and restoration projects from past activities. 27 refs., 7 figs., 75 tabs

  11. Dose evaluation and protection of cosmic radiation

    International Nuclear Information System (INIS)

    Iwai, Satoshi; Takagi, Toshiharu

    2004-01-01

    This paper explained the effects of cosmic radiation on aircraft crews and astronauts, as well as related regulations. International Commission on Radiological Protection (ICRP) recommends the practice of radiation exposure management for the handling/storage of radon and materials containing natural radioactive substances, as well as for boarding jet aircraft and space flight. Common aircraft crew members are not subject to radiation exposure management in the USA and Japan. In the EU, the limit value is 6 mSv per year, and for the crew group exceeding this value, it is recommended to keep records containing appropriate medical examination results. Pregnant female crewmembers are required to keep an abdominal surface dose within 1 mSv. For astronauts, ICRP is in the stage of thinking about exposure management. In the USA, National Council on Radiation Protection and Measurement has set dose limits for 30 days, 1 year, and lifetime, and recommends lifetime effective dose limits against carcinogenic risk for each gender and age group. This is the setting of the dose limits so that the risk of carcinogenesis, to which space radiation exposure is considered to contribute, will reach 3%. For cosmic radiation environments at spacecraft inside and aircraft altitude, radiation doses can be calculated for astronauts and crew members, using the calculation methods for effective dose and dose equivalent for tissue. (A.O.)

  12. Some important issues in developing basic radiation protection recommendations: dosimetric aspects

    Energy Technology Data Exchange (ETDEWEB)

    Thomas, R.H.

    1984-03-01

    Some aspects of the difficulties encountered in the dose equivalent system used in radiation protection are explored and recent work to improve these deficiencies described. The philosophical advantages of a departure from the dose equivalent-based system and its replacement by a risk-based system are briefly discussed. The definition of dose equivalent and the debate concerning its physical dimensions and units are described. Dose equivalent is related to other physiological quantities in physics and the treatment of these quantities in the International System of Units compared. Practical problems in the determination of dose equivalent are illustrated using neutrons as an example. The proliferation of operational quantities for the evaluation of neutron dose equivalent and the concomitant potential for confusion when determinations of neutron dose equivalent are intercompared is described. The evaluation of fluence to dose equivalent conversion coefficients and methods of interpolation between recommended values are described. Particular emphasis is given to the accuracy and precision of dose equivalent estimation. Recent work of a Task Group of the ICRP to improve recommended conversion coefficients and the work of an ICRU committee to improve the definition of operational dose equivalent quantities is summarized. 125 references, 11 figures, 4 tables.

  13. Some important issues in developing basic radiation protection recommendations: dosimetric aspects

    International Nuclear Information System (INIS)

    Thomas, R.H.

    1984-03-01

    Some aspects of the difficulties encountered in the dose equivalent system used in radiation protection are explored and recent work to improve these deficiencies described. The philosophical advantages of a departure from the dose equivalent-based system and its replacement by a risk-based system are briefly discussed. The definition of dose equivalent and the debate concerning its physical dimensions and units are described. Dose equivalent is related to other physiological quantities in physics and the treatment of these quantities in the International System of Units compared. Practical problems in the determination of dose equivalent are illustrated using neutrons as an example. The proliferation of operational quantities for the evaluation of neutron dose equivalent and the concomitant potential for confusion when determinations of neutron dose equivalent are intercompared is described. The evaluation of fluence to dose equivalent conversion coefficients and methods of interpolation between recommended values are described. Particular emphasis is given to the accuracy and precision of dose equivalent estimation. Recent work of a Task Group of the ICRP to improve recommended conversion coefficients and the work of an ICRU committee to improve the definition of operational dose equivalent quantities is summarized. 125 references, 11 figures, 4 tables

  14. How to use mechanistic effect models in environmental risk assessment of pesticides: Case studies and recommendations from the SETAC workshop MODELINK.

    Science.gov (United States)

    Hommen, Udo; Forbes, Valery; Grimm, Volker; Preuss, Thomas G; Thorbek, Pernille; Ducrot, Virginie

    2016-01-01

    Mechanistic effect models (MEMs) are useful tools for ecological risk assessment of chemicals to complement experimentation. However, currently no recommendations exist for how to use them in risk assessments. Therefore, the Society of Environmental Toxicology and Chemistry (SETAC) MODELINK workshop aimed at providing guidance for when and how to apply MEMs in regulatory risk assessments. The workshop focused on risk assessment of plant protection products under Regulation (EC) No 1107/2009 using MEMs at the organism and population levels. Realistic applications of MEMs were demonstrated in 6 case studies covering assessments for plants, invertebrates, and vertebrates in aquatic and terrestrial habitats. From the case studies and their evaluation, 12 recommendations on the future use of MEMs were formulated, addressing the issues of how to translate specific protection goals into workable questions, how to select species and scenarios to be modeled, and where and how to fit MEMs into current and future risk assessment schemes. The most important recommendations are that protection goals should be made more quantitative; the species to be modeled must be vulnerable not only regarding toxic effects but also regarding their life history and dispersal traits; the models should be as realistic as possible for a specific risk assessment question, and the level of conservatism required for a specific risk assessment should be reached by designing appropriately conservative environmental and exposure scenarios; scenarios should include different regions of the European Union (EU) and different crops; in the long run, generic MEMs covering relevant species based on representative scenarios should be developed, which will require EU-level joint initiatives of all stakeholders involved. The main conclusion from the MODELINK workshop is that the considerable effort required for making MEMs an integral part of environmental risk assessment of pesticides is worthwhile, because

  15. Argonne National Laboratory-East site environmental report for calendar year 1996

    International Nuclear Information System (INIS)

    Golchert, N.W.; Kolzow, R.G.

    1997-09-01

    This report discusses the results of the environmental protection program at Argonne National Laboratory-East (ANL-E) for 1996. To evaluate the effects of ANL-E operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the ANL-E site were analyzed and compared to applicable guidelines and standards. A variety of radionuclides were measured in air, surface water, on-site groundwater, soil, grass, and bottom sediment samples. In addition, chemical constituents in surface water, groundwater, and ANL-E effluent water were analyzed. External penetrating radiation doses were measured, and the potential for radiation exposure to off-site population groups was estimated. The results of the surveillance program are interpreted in terms of the origin of the radioactive and chemical substances (natural, fallout, ANL-E, and other) and are compared with applicable environmental quality standards. A US Department of Energy dose calculation methodology, based on International Commission on Radiological Protection recommendations and the CAP-88 version of the EPA-AIRDOSE/RADRISK computer code, is used in this report. The status of ANL-E environmental protection activities with respect to the various laws and regulations that govern waste handling and disposal is discussed. This report also discusses progress being made on environmental corrective actions and restoration projects

  16. Argonne National Laboratory-East site environmental report for calendar year 1993

    International Nuclear Information System (INIS)

    Golchert, N.W.; Kolzow, R.G.

    1994-05-01

    This report discusses the results of the environmental protection program at Argonne National Laboratory-East (ANL) for 1993. To evaluate the effects of ANL operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the ANL site were analyzed and compared to applicable guidelines and standards. A variety of radionuclides was measured in air, surface water, groundwater, soil, grass, and bottom sediment samples. In addition, chemical constituents in surface water, groundwater, and ANL effluent water were analyzed. External penetrating radiation doses were measured and the potential for radiation exposure to off-site population groups was estimated. The results of the surveillance program are interpreted in terms of the origin of the radioactive and chemical substances (natural, fallout, ANL, and other) and are compared with applicable environmental quality standards. A US Department of Energy (DOE) dose calculation methodology, based on International Commission on Radiological Protection (ICRP) recommendations and the CAP-88 version of the EPA-AIRDOSE/RADRISK computer code, is used in this report. The status of ANL environmental protection activities with respect to the various laws and regulations which govern waste handling and disposal is discussed. This report also discusses progress being made on environmental corrective actions and restoration projects from past activities

  17. Argonne National Laboratory-East site environmental report for calendar year 1994

    International Nuclear Information System (INIS)

    Golchert, N.W.; Kolzow, R.G.

    1995-05-01

    This report discusses the results of the environmental protection program at Argonne National Laboratory-East (ANL) for 1994. To evaluate the effects of ANL operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the ANL site were analyzed and compared to applicable guidelines and standards. A variety of radionuclides was measured in air, surface water, groundwater, soil, grass, and bottom sediment samples. In addition, chemical constituents in surface water, groundwater, and ANL effluent water were analyzed. External penetrating radiation doses were measured and the potential for radiation exposure to off-site population groups was estimated. The results of the surveillance program are interpreted in terms of the origin of the radioactive and chemical substances (natural, fallout, ANL, and other) and are compared with applicable environmental quality standards. A US Department of Energy (DOE) dose calculation methodology, based on International Commission on Radiological Protection (ICRP) recommendations and the CAP-88 version of the EPA-AIRDOSE/RADRISK COMPUTER CODE, is used in this report. The status of ANL environmental protection activities with respect to the various laws and regulations which govern waste handling and disposal is discussed. This report also discusses progress being made on environmental corrective actions and restoration projects

  18. Argonne National Laboratory-East site environmental report for calendar year 1994

    Energy Technology Data Exchange (ETDEWEB)

    Golchert, N.W.; Kolzow, R.G.

    1995-05-01

    This report discusses the results of the environmental protection program at Argonne National Laboratory-East (ANL) for 1994. To evaluate the effects of ANL operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the ANL site were analyzed and compared to applicable guidelines and standards. A variety of radionuclides was measured in air, surface water, groundwater, soil, grass, and bottom sediment samples. In addition, chemical constituents in surface water, groundwater, and ANL effluent water were analyzed. External penetrating radiation doses were measured and the potential for radiation exposure to off-site population groups was estimated. The results of the surveillance program are interpreted in terms of the origin of the radioactive and chemical substances (natural, fallout, ANL, and other) and are compared with applicable environmental quality standards. A US Department of Energy (DOE) dose calculation methodology, based on International Commission on Radiological Protection (ICRP) recommendations and the CAP-88 version of the EPA-AIRDOSE/RADRISK COMPUTER CODE, is used in this report. The status of ANL environmental protection activities with respect to the various laws and regulations which govern waste handling and disposal is discussed. This report also discusses progress being made on environmental corrective actions and restoration projects.

  19. Argonne National Laboratory--East site environmental report for calendar year 1990

    International Nuclear Information System (INIS)

    Golchert, N.W.; Duffy, T.L.; Moos, L.P.

    1991-07-01

    This report discusses the results of the environmental protection program at Argonne National Laboratory-East (ANL) for 1990. To evaluate the effects of ANL operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the ANL site were analyzed and compared to applicable guidelines and standards. A variety of radionuclides was measured in air, surface water, groundwater, soil, grass, bottom sediment, and milk samples. In addition, chemical constituents in surface water, groundwater, and ANL effluent water were analyzed. External penetrating radiation doses were measured and the potential for radiation exposure to off-site population groups was estimated. The results of the surveillance program are interpreted in terms of the origin of the radioactive and chemical substances (natural, fallout, ANL, and other) and are compared with applicable environmental quality standards. A US Department of Energy (DOE) dose calculation methodology, based on International Commission on Radiological Protection (ICRP) recommendations, is used in this report. The status of ANL environmental protection activities with respect to the various laws and regulations which govern waste handling and disposal is discussed. This report also discusses progress being made on environmental corrective actions and restoration projects from past activities

  20. Argonne National Laboratory-East site environmental report for calendar year 1991

    International Nuclear Information System (INIS)

    Golchert, N.W.; Duffy, T.L.; Moos, L.P.

    1992-05-01

    This report discusses the results of the environmental protection program at Argonne National Laboratory-East (ANL) for 1991. To evaluate the effects of ANL operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the ANL site were analyzed and compared to applicable guidelines and standards. A variety of radionuclides was measured in air, surface water, groundwater, soil, grass, and bottom sediment samples. Chemical constituents in surface water, groundwater, and ANL effluent water were analyzed. External penetrating radiation doses were measured and the potential for radiation exposure to off-site population groups was estimated. Results are interpreted in terms of the origin of the radioactive and chemical substances (natural, fallout, ANL, and other) and are compared with applicable environmental quality standards. A US Department of Energy (DOE) dose calculation methodology, based on International Commission on Radiological Protection (ICRP) recommendations and the CAP-88 version of the EPA-AIRDOSE/RADRISK computer code, is used in this report. The status of ANL environmental protection activities with respect to the various laws and regulations which govern waste handling and disposal is discussed. This report also discusses progress being made on environmental corrective actions and restoration projects from past activities

  1. Argonne National Laboratory-East site environmental report for calendar year 1996

    Energy Technology Data Exchange (ETDEWEB)

    Golchert, N.W.; Kolzow, R.G.

    1997-09-01

    This report discusses the results of the environmental protection program at Argonne National Laboratory-East (ANL-E) for 1996. To evaluate the effects of ANL-E operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the ANL-E site were analyzed and compared to applicable guidelines and standards. A variety of radionuclides were measured in air, surface water, on-site groundwater, soil, grass, and bottom sediment samples. In addition, chemical constituents in surface water, groundwater, and ANL-E effluent water were analyzed. External penetrating radiation doses were measured, and the potential for radiation exposure to off-site population groups was estimated. The results of the surveillance program are interpreted in terms of the origin of the radioactive and chemical substances (natural, fallout, ANL-E, and other) and are compared with applicable environmental quality standards. A US Department of Energy dose calculation methodology, based on International Commission on Radiological Protection recommendations and the CAP-88 version of the EPA-AIRDOSE/RADRISK computer code, is used in this report. The status of ANL-E environmental protection activities with respect to the various laws and regulations that govern waste handling and disposal is discussed. This report also discusses progress being made on environmental corrective actions and restoration projects.

  2. Digital dosimetry and personal and environmental monitoring assembly

    International Nuclear Information System (INIS)

    Cerovac, Z.; Radalj, Z.; Prlic, I.; Cerovac, H.

    1996-01-01

    Film+TLD and film or TLD Dosimetry have a certain delay in dose reporting, since the reports on occupational doses are usually available to the users within 40 days after the actual exposure. This is particularly important when the dose is received within the short-time interval or when the radiation source has some technical failures. For this reason, the additional monitoring is recommendable. The common Dosimetry service in Croatia is well established and the data available shows that over 80% of occupationally exposed persons are working in medical facilities, mainly with x-ray sources. Dosimetry services in the country are providing three types of dosemeters, film dosemeter badge, film+TLD dosemeter badge or plane TLD badge. We have decided to introduce the palette of digital pocket dosemeters to be used at different workplaces occupationally exposed to ionizing radiation. After the first experience with the ALARA 1G digital dosemeter it came out that this type of ionizing radiation measuring device is suitable for the various non-occupational purposes. After some technical improvement and with some telecommunication electronics this device is usable as a point environmental measuring station. This means that the probe of the record any change in normal environmental radiation field, send the data to the central station and to raise alarm if necessary. That is why we have made a prototype for environmental monitoring able to be connected to any kind of telecommunication net. (author)

  3. The impact of ambient dose rate measuring network and precipitation radar system for detection of environmental radioactivity released by accident

    International Nuclear Information System (INIS)

    Bleher, M; Stoehlker, U.

    2003-01-01

    For the surveillance of environmental radioactivity, the German measuring network of BfS consists of more than 2000 stations where the ambient gamma dose rate is continuously measured. This network is a helpful tool to detect and localise enhanced environmental contamination from artificial radionuclides. The threshold for early warning is so low, that already an additional dose rate contribution of 0,07 μGy/h is detectable. However, this threshold is frequently exceeded due to precipitation events caused by washout of natural activity in air. Therefore, the precipitation radar system of the German Weather Service provides valuable information on the problem, whether the increase of the ambient dose rate is due to natural or man-made events. In case of an accidental release, the data of this radar system show small area precipitation events and potential local hot spots not detected by the measuring network. For the phase of cloud passage, the ambient dose rate measuring network provides a reliable database for the evaluation of the current situation and its further development. It is possible to compare measured data for dose rate with derived intervention levels for countermeasures like ''sheltering''. Thus, critical regions can be identified and it is possible to verify implemented countermeasures. During and after this phase of cloud passage the measured data of the monitoring network help to adapt the results of the national decision support systems PARK and RODOS. Therefore, it is necessary to derive the actual additional contribution to the ambient dose rate. Map representations of measured dose rate are rapidly available and helpful to optimise measurement strategies of mobile systems and collection strategies for samples of agricultural products. (orig.)

  4. Ecofriendly nanotechnologies and nanomaterials for environmental applications: Key issue and consensus recommendations for sustainable and ecosafe nanoremediation.

    Science.gov (United States)

    Corsi, I; Winther-Nielsen, M; Sethi, R; Punta, C; Della Torre, C; Libralato, G; Lofrano, G; Sabatini, L; Aiello, M; Fiordi, L; Cinuzzi, F; Caneschi, A; Pellegrini, D; Buttino, I

    2018-06-15

    The use of engineered nanomaterials (ENMs) for environmental remediation, known as nanoremediation, represents a challenging and innovative solution, ensuring a quick and efficient removal of pollutants from contaminated sites. Although the growing interest in nanotechnological solutions for pollution remediation, with significant economic investment worldwide, environmental and human risk assessment associated with the use of ENMs is still a matter of debate and nanoremediation is seen yet as an emerging technology. Innovative nanotechnologies applied to water and soil remediation suffer for a proper environmental impact scenario which is limiting the development of specific regulatory measures and the exploitation at European level. The present paper summarizes the findings from the workshop: "Ecofriendly Nanotechnology: state of the art, future perspectives and ecotoxicological evaluation of nanoremediation applied to contaminated sediments and soils" convened during the Biannual ECOtoxicology Meeting 2016 (BECOME) held in Livorno (Italy). Several topics have been discussed and, starting from current state of the art of nanoremediation, which represents a breakthrough in pollution control, the following recommendations have been proposed: (i) ecosafety has to be a priority feature of ENMs intended for nanoremediation; ii) predictive safety assessment of ENMs for environmental remediation is mandatory; (iii) greener, sustainable and innovative nano-structured materials should be further supported; (iii) those ENMs that meet the highest standards of environmental safety will support industrial competitiveness, innovation and sustainability. The workshop aims to favour environmental safety and industrial competitiveness by providing tools and modus operandi for the valorization of public and private investments. Copyright © 2018 Elsevier Inc. All rights reserved.

  5. Nordic Guidance Levels for Patient Doses in Diagnostic Radiology

    International Nuclear Information System (INIS)

    Saxebol, G.; Olerud, H.M.; Hjardemaal, O.; Leitz, W.; Servomaa, A.; Walderhaug, T.

    1998-01-01

    Within the framework of Nordic authoritative cooperation in radiation protection and nuclear safety, recommendations have been prepared dealing with dose constraints in diagnostic radiology. A working group with participants from all the Nordic countries has met and discussed possible implementations of the ICRP dose constraint for medical radiology. Dose constraints, expressed as guidance levels, were specified for six different radiological examinations, i.e. chest, pelvis, lumbar spine, urography, barium meal and enema in units of kerma-area product and entrance surface dose. The recommendations are described in report No 5 in the series 'Report on Nordic Radiation Protection Cooperation'. Examples of dose distributions and factors affecting the patient dose are described in the report. (author)

  6. Assessment of mean glandular dose to patients from digital mammography systems

    International Nuclear Information System (INIS)

    Pwamang, Caroline K.

    2016-07-01

    Mean glandular dose assessment of patients undergoing digital mammography examination has been done. A total of 297 patient data was used for the study. Basic Quality Control tests were done to ascertain the performance of the equipment used. The results of Quality Control tests indicated that the three Mammography units used for this study were functioning within the internationally acceptable performance criteria. Patients with a breast thickness of 30 mm within the two age groups of 40-49 yrs and 50-64 yrs received doses slightly higher than the acceptable dose levels. A patient in the category 40-49 yrs with breast thickness of 30 mm received 1.83 mGy as calculated Mean Glandular Dose, 2.10 mGy was the recorded dose and 1.58 mGy was recorded under the age group 50-64 yrs. These values have deviated by -22%, -40%, and -5.33% respectively from 1.5 mGy which is the recommended dose for a breast thickness of 30 mm. Also patients with breast thickness of 70 mm under the age group 40–49 yrs had a recorded dose of 6.58 mGy, which deviated by -1.21% from the recommended value of 6.5 mGy for that breast thickness. Aside these values, all the other values were within the recommended dose values. The percentage deviation between the recommended values and the calculated values was within ±25% which was a working limit that was set for this work. Doses delivered by the Full-field Digital mammography equipment were higher than doses delivered by the Computered Radiography equipment. The calculated Mean Glandular Doses for the three facilities were within recommended dose values. (author)

  7. Dose conversion factors

    International Nuclear Information System (INIS)

    Kocher, D.C.; Eckerman, K.F.

    1992-01-01

    The following is discussed in this report: concepts and quantities used in calculating radiation dose from internal and external exposure. Tabulations of dose conversion factor for internal and external exposure to radionuclides. Dose conversion factors give dose per unit intake (internal) or dose per unit concentration in environment (external). Intakes of radionuclides for internal exposure and concentrations of radionuclides in environment for external exposure are assumed to be known. Intakes and concentrations are obtained, e.g., from analyses of environmental transport and exposure pathways. differences between dosimetry methods for radionuclides and hazardous chemicals are highlighted

  8. Deuterons at energies of 10 MeV to 1 TeV: Conversion coefficients for fluence-to-absorbed dose, equivalent dose, effective dose and gray equivalent, calculated using Monte Carlo radiation transport code MCNPX 2.7.C

    International Nuclear Information System (INIS)

    Copeland, K.; Parker, D. E.; Friedberg, W.

    2011-01-01

    Conversion coefficients were calculated for fluence-to-absorbed dose, fluence-to-equivalent dose, fluence-to-effective dose and fluence-to-gray equivalent for isotropic exposure of an adult female and an adult male to deuterons ( 2 H + ) in the energy range 10 MeV -1 TeV (0.01-1000 GeV). Coefficients were calculated using the Monte Carlo transport code MCNPX 2.7.C and BodyBuilder TM 1.3 anthropomorphic phantoms. Phantoms were modified to allow calculation of the effective dose to a Reference Person using tissues and tissue weighting factors from 1990 and 2007 recommendations of the International Commission on Radiological Protection (ICRP) and gray equivalent to selected tissues as recommended by the National Council on Radiation Protection and Measurements. Coefficients for the equivalent and effective dose incorporated a radiation weighting factor of 2. At 15 of 19 energies for which coefficients for the effective dose were calculated, coefficients based on ICRP 1990 and 2007 recommendations differed by < 3 %. The greatest difference, 47 %, occurred at 30 MeV. (authors)

  9. Dose limits to the eye lens

    International Nuclear Information System (INIS)

    Sion, N.

    2016-01-01

    Protecting the human body from the effects of ionizing radiation is essential to forestall stochastic effects and require placing limits on the effective dose. Dose limits on specific organs are also necessary to reduce the deterministic effects and tissue reactions. The standard for radiation protection was ISO 15382 (2002) which mainly dealt with beta radiation for nuclear power plant workers. Clearly an update is required to allow for new technology and the proliferative use of radiation in medical practices. There is a need for more explicit radiation monitoring to operators and staff. ICRP118 (International Commission on Radiological Protection), Ref. 1, evolved their recommendations to include eye lens doses as a follow on to their publication 103 and to focus on radiation exposures. It provides updated estimates of 'practical' threshold doses for tissue injury at the level of 1% incidence. This paper discusses the current status and the recommendation for a drastic reduction of the dose limit to the eye lens. (author)

  10. Dose limits to the eye lens

    Energy Technology Data Exchange (ETDEWEB)

    Sion, N.

    2016-09-15

    Protecting the human body from the effects of ionizing radiation is essential to forestall stochastic effects and require placing limits on the effective dose. Dose limits on specific organs are also necessary to reduce the deterministic effects and tissue reactions. The standard for radiation protection was ISO 15382 (2002) which mainly dealt with beta radiation for nuclear power plant workers. Clearly an update is required to allow for new technology and the proliferative use of radiation in medical practices. There is a need for more explicit radiation monitoring to operators and staff. ICRP118 (International Commission on Radiological Protection), Ref. 1, evolved their recommendations to include eye lens doses as a follow on to their publication 103 and to focus on radiation exposures. It provides updated estimates of 'practical' threshold doses for tissue injury at the level of 1% incidence. This paper discusses the current status and the recommendation for a drastic reduction of the dose limit to the eye lens. (author)

  11. 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

  12. 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.

  13. Issues in the reconstruction of environmental doses on the basis of thermoluminescence measurements in the Techa riverside

    Science.gov (United States)

    Bougrov, N. G.; Goksu, H. Y.; Haskell, E.; Degteva, M. O.; Meckbach, R.; Jacob, P.; Neta, P. I. (Principal Investigator)

    1998-01-01

    The potential of thermoluminescence measurements of bricks from the contaminated area of the Techa river valley, Southern Urals, Russia, for reconstructing external exposures of affected population groups has been studied. Thermoluminescence dating of background samples was used to evaluate the age of old buildings available on the river banks. The anthropogenic gamma dose accrued in exposed samples is determined by subtracting the natural radiation background dose for the corresponding age from the accumulated dose measured by thermoluminescence. For a site in the upper Techa river region, where the levels of external exposures were extremely high, the depth-dose distribution in bricks and the dependence of accidental dose on the height of the sampling position were determined. For the same site, Monte Carlo simulations of radiation transport were performed for different source configurations corresponding to the situation before and after the construction of a reservoir on the river and evacuation of the population in 1956. A comparison of the results provides an understanding of the features of the measured depth-dose distributions and height dependencies in terms of the source configurations and shows that bricks from the higher sampling positions are likely to have accrued a larger fraction of anthropogenic dose from the time before the construction of the reservoir. The applicability of the thermoluminescent dosimetry method to environmental dose reconstruction in the middle Techa region, where the external exposure was relatively low, was also investigated.

  14. ICRP new recommendations. Committee 2's efforts

    International Nuclear Information System (INIS)

    Eckerman, K.F.

    2007-01-01

    The International Commission on Radiological Protection (ICRP) may release new primary radiation protection recommendation in 2007. Committee 2 has underway reviews of the dosimetric and biokinetic models and associated data used in calculating dose coefficients for intakes of radionuclides and exposures to external radiation fields. This paper outlines the work plans of Committee 2 during the current term, 2005-2009, in anticipation of the new primary recommendations. The two task groups of Committee 2 responsible for the computations of dose coefficients, INDOS and DOCAL, are reviewing the models and data used in the computations. INDOS is reviewing the lung model and the biokinetic models that describe the behavior of the radionuclides in the body. DOCAL is reviewing its computational formulations with the objective of harmonizing the formulation with those of nuclear medicine, and developing new computational phantoms representing the adult male and female reference individuals of ICRP Publication 89. In addition, DOCAL will issue a publication on nuclear decay data to replace ICRP Publication 38. While the current efforts are focused on updating the dose coefficients for occupational intakes of radionuclides plans are being formulated to address dose coefficients for external radiation fields which include consideration of high energy fields associated with accelerators and space travel and the updating of dose coefficients for members of the public. (author)

  15. Cattle and the oil and gas industry in Alberta: A literature review with recommendations for environmental management

    International Nuclear Information System (INIS)

    1996-01-01

    The purpose of this report is to bring together a review of published information on the potential effects of upstream oil and gas industry operations on the cattle industry in Alberta, some indication of the probability of occurrence of these effects, and recommendations on how they might be avoided or mitigated. Based on reviews of scientific papers and industry good-practice manuals, the report describes: The sources and quantities of environmental contaminants generated by Alberta's oil and gas industry, including normal operations, accidental releases, and the effects of aging infrastructure; the chemical composition of the products, materials, and wastes associated with the industry; the fate and transport of the contaminants through air, water, and soil; cattle operations in Alberta; the toxicology of oil and gas industry contaminants in cattle; and selected Alberta case studies of accidental releases and planned experiments. Conclusions and recommendations deal with critical information gaps and strategies for the sustainable management of cattle and oil/gas operations in the province

  16. Doses from radiation exposure

    International Nuclear Information System (INIS)

    Menzel, H-G.; Harrison, J.D.

    2012-01-01

    Practical implementation of the International Commission on Radiological Protection’s (ICRP) system of protection requires the availability of appropriate methods and data. The work of Committee 2 is concerned with the development of reference data and methods for the assessment of internal and external radiation exposure of workers and members of the public. This involves the development of reference biokinetic and dosimetric models, reference anatomical models of the human body, and reference anatomical and physiological data. Following ICRP’s 2007 Recommendations, Committee 2 has focused on the provision of new reference dose coefficients for external and internal exposure. As well as specifying changes to the radiation and tissue weighting factors used in the calculation of protection quantities, the 2007 Recommendations introduced the use of reference anatomical phantoms based on medical imaging data, requiring explicit sex averaging of male and female organ-equivalent doses in the calculation of effective dose. In preparation for the calculation of new dose coefficients, Committee 2 and its task groups have provided updated nuclear decay data (ICRP Publication 107) and adult reference computational phantoms (ICRP Publication 110). New dose coefficients for external exposures of workers are complete (ICRP Publication 116), and work is in progress on a series of reports on internal dose coefficients to workers from inhaled and ingested radionuclides. Reference phantoms for children will also be provided and used in the calculation of dose coefficients for public exposures. Committee 2 also has task groups on exposures to radiation in space and on the use of effective dose.

  17. Environmental and effluent monitoring at ANSTO sites, 2004-2005

    International Nuclear Information System (INIS)

    Hoffmann, Emmy L.; Loosz, Tom; Ferris, John M.; Harrison, Jennifer J.

    2005-01-01

    This report presents the results of ANSTO's environmental and effluent monitoring at the Lucas Heights Science and Technology Centre (LHSTC) and the National Medical Cyclotron (NMC) sites, from July 2004 to June 2005. Effective doses to the critical group of members of the public potentially affected by routine airborne emissions from the LHSTC were less than 0.005 mSv/year. This estimated maximum potential dose is less than 24% of the ANSTO ALARA objective of 0.02 mSv/year, and much lower than the public dose limit of 1 mSv/year that is recommended by the Australian Radiation Protection and Nuclear Safety Agency (ARPANSA). The effective doses to the critical group of members of the public potentially exposed to routine liquid effluent releases from the LHSTC have been realistically estimated as a quarter (or less) of the estimated doses to the critical group for airborne releases. The levels of tritium detected in groundwater and stormwater at the LHSTC were less than those set out in the Australian Drinking Water Guidelines. The airborne and liquid effluent emissions from the NMC were below both the ARPANSA-approved notification levels and Sydney Water limits for acceptance of trade wastewater to sewer. Results of environmental monitoring at both ANSTO sites confirm that the facilities continue to be operated well within regulatory limits. ANSTO's routine operations at the LHSTC and NMC make only a very small addition to the natural background radiation dose of ∼1.5 mSv/year experienced by members of the Australian public

  18. Pan-oral dose assessment: a comparative report of methodologies

    International Nuclear Information System (INIS)

    Shafford, J.; Pryor, M.; Hollaway, P.; Peet, D.; Oduko, J.

    2015-01-01

    National guidance from the Institute of Physics and Engineering in Medicine (IPEM Report 91) currently recommends that the patient dose for a pan-oral X-ray unit is measured as dose area product (DAP) replacing dose width product described in earlier guidance. An investigation identifying different methods available to carry out this measurement has been undertaken and errors in the methodologies analysed. It has been shown that there may be up to a 30 % variation in DAP measurement between methods. This paper recommends that where possible a DAP meter is used to measure the dose-area product from a pan-oral X-ray unit to give a direct DAP measurement. However, by using a solid-state dose measurement and film/ruler to calculate DAP the authors have established a conversion factor of 1.4. It is strongly recommended that wherever a DAP value is quoted the methodology used to obtain that value is also reported. (authors)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2001-01-01

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

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

    International Nuclear Information System (INIS)

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

    2001-01-01

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

  1. Practical experience of monitoring patient dose

    Energy Technology Data Exchange (ETDEWEB)

    McDonnell, C.; Shrimpton, P. (National Radiological Protection Board, Chilton (United Kingdom)); O' Mahoney, M. (National Radiological Protection Board, Leeds (United Kingdom)); Foster, J. (Nuffield Hospitals, Surbiton (United Kingdom))

    1994-05-01

    NRPB recommends the use of reference dose levels for diagnostic medical exposures as an aid to patient dose reduction, but is this approach effective This article describes the broadly encouraging experiences of one large group of hospitals in carrying out measurements of entrance surface dose on patients undergoing some common types of x-ray examination. (author).

  2. Environmental and safety problems of waste management in nuclear engineering

    International Nuclear Information System (INIS)

    Schwibach, J.; Jacobi, W.

    1976-01-01

    The environmental and safety problems which waste management in nuclear technology poses are discussed under the aspects of the disposal of radioactive waste by nuclear facilities and the safety of radioactive waste disposal. The release and global distribution of long-lived radionuclides such as tritium, Kr-85, C-14, I-129, and Pu-239 as well as the radiation exposure of the world population resulting thereof are investigated, the authors starting from a specific production rate of the nuclides released from nuclear facilities. Definitions of the terms 'dose commitment' and 'collective dose commitment' are given. Furthermore, local radiation exposure in reprocessing plants is investigated and compared with regional and global radiation exposure. A recommendation is made to take measures which would reduce the nuclides tritium, Kr-85, and C-14 in order to achieve considerably smaller collective doses. (HR/LN) [de

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

    Science.gov (United States)

    Aprea, Maria Cristina

    2012-04-25

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

  4. Recommendations to the NRC for review criteria for alternative methods of low-level radioactive waste disposal: Environmental monitoring and surveillance programs

    International Nuclear Information System (INIS)

    Denham, D.H.; Stenner, R.D.; Eddy, P.A.; Jaquish, R.E.; Ramsdell, J.V. Jr.

    1988-07-01

    Licensing of a facility for low-level radioactive waste disposal requires the review of the environmental monitoring and surveillance programs. A set of review criteria is recommended for the US Nuclear Regulatory Commission (NRC) staff to use in each monitoring phase---preoperational, operational, and post operational---for evaluating radiological and selected nonradiological parameters in proposed environmental monitoring and surveillance programs at low-level waste disposal facilities. Applicable regulations, industry standards, and technical guidance on low-level radioactive waste are noted throughout the document. In the preoperational phase, the applicant must demonstrate that the environmental monitoring program identifies radiation levels and radionuclide concentrations at the site and also provides adequate basic data on the disposal site. Data recording and statistical analyses for this phase are addressed

  5. Estimation of the transit dose component in high dose rate brachytherapy

    International Nuclear Information System (INIS)

    Garcia Romero, A.; Millan Cebrian, E.; Lozano Flores, F.J.; Lope Lope, R.; Canellas Anoz, M.

    2001-01-01

    Current high dose rate brachytherapy (HDR) treatment planning systems usually calculate dose only from source stopping positions (stationary component), but fails to account for the administered dose when the source is moving (dynamic component or transit dose). Numerical values of this transit dose depends upon the source velocity, implant geometry, source activity and prescribed dose. In some HDR treatments using particular geometry the transit dose cannot be ignored because it increases the dose at the prescriptions points and also could increase potential late tissue complications as predicted by the linear quadratic model. International protocols recommend to verify this parameter. The aim of this paper has been to establish a procedure for the transit dose calculation for the Gammamed 12i equipment at the RT Department in the Clinical University Hospital (Zaragoza-Spain). A numeric algorithm was implemented based on a dynamic point approximation for the moving HDR source and the calculated results for the entrance-exit transit dose was compared with TLD measurements made in some discrete points. (author) [es

  6. Evolution of authorised limits for environmental releases from nuclear facilities in India

    International Nuclear Information System (INIS)

    Subramanian, Chitra; Narayanan, K.K.; Sharma, R.M.

    2002-01-01

    Full text: The controlled environmental releases of radioactive effluents from any nuclear facility is primarily based on the effective dose limits for the general public, recommended by the international commission on radiation protection (ICRP). To meet the dose limit criteria for members of the public, regulatory-limits are set for the discharges of radioactive effluents from nuclear facilities, which are known as the authorised limits (ALs). The paper presents the evolution of ALs in India applicable to nuclear power plant sites, starting from Tarapur Atomic Power Station (TAPS) commissioned in 1969, when the dose limit used to be 5 mSv/yr for the public, to the present generation pressurised heavy water reactors, when the population dose limit has been revised downward to 1 mSv/yr. The paper also presents the changes in the philosophy of dose apportionment for multifacility sites like Tarapur, Rawatbhata and Kalpakkam over the years. The operating experience with respect to environmental discharges from operating nuclear power plants (NPPs) in the country was reviewed vis-a-vis the applicable discharge limits, which shows that the actual releases constitute only a small percentage of the discharge limits. A strong case for lowering the dose apportionment for NPPs is suggested on the basis of latest data on site meteorology, dosimetry of radionuclides and environmental dose assessment methodology and operating experience. It is established in the paper that there is scope for reduction in the dose apportionment of NPPs for most of the radionuclides, without major changes in the existing discharge limits. The lowering of dose apportionment will be critically important at multifacility sites like Tarapur, Rawatbhata and Kalpakkam where many new facilities are being planned. At present the dose reserve available at these sites is only 0.14 mSv/yr, 0.06 mSv/yr and 0.16 mSv/yr, respectively at Tarapur, Rawatbhata and Kalpakkam. With the programme of siting

  7. Detection of sub micro Gray dose levels using OSL phosphor LiMgPO_4:Tb,B

    International Nuclear Information System (INIS)

    Rawat, N.S.; Dhabekar, Bhushan; Muthe, K.P.; Koul, D.K.; Datta, D.

    2017-01-01

    Highlights: • LiMgPO4:Tb,B has been studied and shown to possesses minimum measurable dose (MMD) in sub micro Gray region. • MMD as low as 0.49 µGy in readout time of less than 1 s at stimulation intensity of 32 mW/cm"2 has been achieved. • The OSL measurements for low doses has strengthened and validated this claim. • OSL spectrum shows several emission peaks and the prominent peak around 380 nm. - Abstract: Detection of sub micro Gray doses finds application in personnel and environmental monitoring, and nuclear forensics. Recently developed LiMgPO_4:Tb,B (LMP) is highly sensitive Optically Stimulated Luminescence (OSL) phosphor with excellent dosimetric properties. The OSL emission spectrum of LMP consists of several peaks attributed to characteristic Tb"3"+ emission. The OSL emission peak at 380 nm is favorable for bi-alkali PMT used in RISO reader system. It is demonstrated that significant improvement in dose detection threshold can be realized for LMP by optimization of continuous wave (CW–) OSL parameters like stimulation intensity and readout time. The minimum measurable dose (MMD) as low as 0.49 µGy in readout time of less than 1 s at stimulation intensity of 32 mW/cm"2 has been achieved using this phosphor. The recommendations for choice of parameters for personnel and environmental monitoring are also discussed.

  8. Controllable dose

    International Nuclear Information System (INIS)

    Alvarez R, J.T.; Anaya M, R.A.

    2004-01-01

    With the purpose of eliminating the controversy about the lineal hypothesis without threshold which found the systems of dose limitation of the recommendations of ICRP 26 and 60, at the end of last decade R. Clarke president of the ICRP proposed the concept of Controllable Dose: as the dose or dose sum that an individual receives from a particular source which can be reasonably controllable by means of any means; said concept proposes a change in the philosophy of the radiological protection of its concern by social approaches to an individual focus. In this work a panorama of the foundations is presented, convenient and inconveniences that this proposal has loosened in the international community of the radiological protection, with the purpose of to familiarize to our Mexican community in radiological protection with these new concepts. (Author)

  9. Comparison of therapy augmentation and deviation rates from the recommended once-daily dosing regimen between LDX and commonly prescribed long-acting stimulants for the treatment of ADHD in youth and adults.

    Science.gov (United States)

    Setyawan, Juliana; Hodgkins, Paul; Guérin, Annie; Gauthier, Geneviève; Cloutier, Martin; Wu, Eric; Erder, M Haim

    2013-10-01

    To compare therapy augmentation and deviation rates from the recommended once-daily dosing regimen in Attention Deficit Hyperactivity Disorder (ADHD) patients initiated on lisdexamfetamine (LDX) vs other once-daily Food and Drug Administration (FDA) approved stimulants. ADHD patients initiated on a long-acting ADHD stimulant medication (index medication) in/after 2007 were selected from a large U.S. administrative claims database. Patients were required to be persistent for ≥90 days and continuously enrolled in their healthcare plan for ≥12 months following treatment initiation date. Based on age and previous treatment status, patients were classified into treatment-naïve children and adolescents (6-17 years old), previously treated children and adolescents, treatment-naïve adults (≥18 years old), and previously treated adults. Furthermore, patients were classified into four mutually exclusive treatment groups, based on index medication: lisdexamfetamine (LDX), osmotic release methylphenidate hydrochloride long-acting (OROS MPH), other methylphenidate/dexmethylphenidate long-acting (MPH LA), and amphetamine/dextroamphetamine long-acting (AMPH LA). The average daily consumption was measured as the quantity of index medication supplied in the 12-month study period divided by the total number of days of supply. Therapy augmentation was defined as the use of another ADHD medication concomitantly with the index medication for ≥28 consecutive days. Therapy augmentation and deviation rates from the recommended once-daily dosing regimen were compared between treatment groups using multivariate logistic regression models. Compared to the other treatment groups, LDX patients were less likely to augment with another ADHD medication (range odds ratios [OR]; 1.28-3.30) and to deviate from the recommended once-daily dosing regimen (range OR; 1.73-4.55), except for previously treated adult patients, where therapy augmentation differences were not statistically

  10. The determination of effective doses from the intake of tritiated water

    International Nuclear Information System (INIS)

    1987-08-01

    To comply with the regulatory requirements relating to the dose from exposures to tritiated water (HTO), Atomic Energy Control Board (AECB) licensees currently measure tritium concentration in urine to determine whole body dose. This approach has been based on the consideration that the time-integrated tritium concentration (which is proportional to accumulated dose) in any organ from urine concentrations are always conservative. The International Commission on Radiological Protection (ICRP) recommends that the average soft tissue dose be used to determine effective dose equivalents for HTO exposures. The ICRP also recommends that only the retention in body water be considered when committed doses from HTO exposures are calculated; this recommendation is based on the consideration that the errors introduced by neglecting the long-lived tritium component (those tritium atoms retained in organic molecules of the body cells) are small (only of the order of 10% of the committed dose equivalent to the whole body). The AECB position is presented in the following regulatory policy statement

  11. Supplements in pregnancy: the latest recommendations

    Science.gov (United States)

    Martínez García, Rosa María

    2016-07-12

    Pregnancy is a challenge from the nutritional point of view, because nutrient requirements are increased and alter its intake can affect maternal and fetal health. Micronutrient defi ciency states are related to preeclampsia, intrauterine growth restriction, abortion and congenital anomalies. Currently, the diet of many expectant mothers is insufficient in micronutrients, in this cases supplementation is necessary. It is recommended supplementation with folic acid in doses of 400 mcg / day and 5 mg/day in risk pregnant, and should begin at least one month before conception and during the first 12 weeks gestation, and extend it throughout pregnancy in mothers with nutritional risk. It is important to keep watch the proper dose of folic acid to prevent possible adverse effects of unmetabolized accumulation in plasma. A high percentage of pregnant women presented iron deficiency anemia, being recommended intermittent use of iron supplements (with lower gastrointestinal alteration and oxidative stress); not recommended for mothers without anemia (hemoglobin> 13.5 g / L). Since calcium absorption is increased up to 40% in gestation, its supplementation is not recommended for mothers with adequate intakes (3 dairy / day), and its use must be reserved to women with inadequate intakes and / or high risk of preeclampsia. Regarding the iodine, there are confl icting positions by different working groups established potassium iodide supplementation in women who do not reach their recommended intake (3 servings of milk and dairy products + 2 g of iodized salt), with their diets. Given that vitamin A and D can be toxic to mother and fetus, it is not recommended its supplementation except in cases of deficiency. Although the use of multiple micronutrients supplements may favorably impact the outcome of pregnancy, more scientific evidence is needed to establish the replacement of iron and folic acid with a multiple micronutrient supplement.

  12. How does the choice of ILCD’s recommended methods change the assessment of environmental impacts in LCA of products?

    DEFF Research Database (Denmark)

    Owsianiak, Mikolaj; Laurent, Alexis; Bjørn, Anders

    2014-01-01

    on human health and impacts from land use on natural environment; between 1 and 3 orders of magnitude for metal depletion and for toxicity-related impact categories; and within 1 order of magnitude for the remaining impact categories.These differences are caused by the differences in underlying...... environmental impacts and there is large difference in demand for output from that process between the compared options. Nevertheless, the choice of ILCD' matters the most for assessment of impacts from ionizing radiation, land use, resource depletion (minerals), and all toxicity-related impact categories......The European Commission has launched a recommended set of characterization methods for application inlife cycle impact assessment (LCIA). However, it is not known yet whether the choice of the recommended practice, referred to as the ILCD, over existing LCIA methodologies matter for interpretation...

  13. Patient dose measurement and dose reduction in East Anglia (UK)

    International Nuclear Information System (INIS)

    Wade, J.P.; Goldstone, K.E.; Dendy, P.P.

    1995-01-01

    At the end of 1990 a programme of patient dose measurements was introduced as part of the quality assurance service already provided for X ray departments throughout the East Anglian Health Region (UK). Thermoluminescence dosemeters (TLDs) were used to measure over 1200 skin entrance surface doses for four common radiographic views in 33 hospitals in both the NHS and private sector. The four views were chosen to cover a wide range of equipment and techniques. The data collected have enabled Regional reference doses to be set which, for all views considered, fall below the National Radiological Protection Board (NRPB) Reference levels. In departments which exceeded reference levels, techniques were reviewed, improvements suggested and doses re-measured, in accordance with the recommended procedure for patient dose audit. A significant finding was that, given appropriate controls, X ray departments in the private sector could achieve the same acceptably low doses as NHS departments. (Author)

  14. Applicability of federal and state environmental requirements to selected DOE field installations and recommendations for development of generic compliance guidance. Final report

    International Nuclear Information System (INIS)

    1982-01-01

    This final report identifies and describes federal and state environmental requirements applicable to selected Department of Energy (DOE) nuclear field installations, establishes priorities for the requirements, determines the need for development of additional compliance guidance, and recommends development of compliance guidance for specific priority requirements. Compliance guidance developed as part of the study is summarized. The applicability of environmental requirements to 12 DOE field installations was reviewed. Five installations were examined under Task 4. They are: Nevada Test Site; Lawrence Berkeley Laboratory; Paducah Gaseous Diffusion Plant; Oak Ridge Y-12 Plant; and Los Alamos Scientific Laboratory. Seven other installations were reviewed under Task 2 and included: Idaho National Engineering Laboratory; Hanford; Savannah River Plant; Oak Ridge Gaseous Diffusion Plant; Pantex Plant; Rocky Flats Plant; and Lawrence Livermore Laboratory. This report combines results of the two tasks. The objective of the study was to identify the set of environmental requirements which are applicable to DOE field installations, track changes in the requirements, and prepare compliance guidance for important requirements and important regulatory developments as necessary. A cumulative calendar update for July 1982 represents the current status of applicable requirements. Environmental profiles of each facility, along with ambient monitoring results, are presented. Applicable federal requirements are identified. The specific applicability of federal and state requirements is detailed for each installation. Compliance guidance available from various agencies is described. Each requirement described is ranked by priority, and recommendations are made for development of additional guidance

  15. A design of ambient dose equivalent dosimeter and its dosimetric performance

    International Nuclear Information System (INIS)

    Zhao Shian; Ou Xiangming; Li Kaibao

    1997-01-01

    Objective: To design an ambient dose equivalent dosimeter with digital display for radiation protection, which is based on the definition of the new operational radiation quantity for environmental monitoring-ambient dose equivalent recommended by the International Commission on Radiation Units and Measurements (ICRU) Report 39. Methods: Considering the energy response of the instrument, the inner wall of ionizing chamber is coated with gum graphite added with a bit of metal powder. Results: Using this chamber, measurement of H * (10) for photon radiation with unknown spectrum distribution is possible in the energy range from 47 keV to 230 keV with an uncertainty of better than 5%. The configuration, technology and dosimetric performance of the chamber and automatic functions of the reader are presented. Conclusion: The ambient dose equivalent dosimeter can be used as not only a working reference dosimeter, but also a field dosimeter for radiation protection because the readings are expressed directly in ambient dose equivalent and averaged automatically in the period of measurement. Also, its power is supplied by battery for the portable purpose and the readings are displayed on the screen with light-background for dim field

  16. Public doses estimation based on effluents data and direct measurements of Tritium in environmental samples at Cernavoda

    International Nuclear Information System (INIS)

    Bobric, E.; Popescu, I.; Simionov, V.

    2002-01-01

    The release of any potential radioactive pollutant to the environment during routine operation of a Nuclear Power Plant should be the subject of appropriate controls and assessments. The layout of the Candu reactor and the design of its systems ensure that the radioactive waste quantities are minimized, but small amounts of radioisotopes are continuously discharged at very low concentrations through gaseous and liquid effluents. Radioprotection of the public is based on the principles recommended by ICRP, the protection being mainly achieved by control of the sources of exposure. Source monitoring provide a means of assessing the radiation exposure of population groups, critical groups and individual members of the public. The assessed doses are used to demonstrate the compliance with authorized dose limits - 1 mSv / year in our case - but can also be used for optimization purposes

  17. Basic concepts and assumptions behind the new ICRP recommendations

    International Nuclear Information System (INIS)

    Lindell, B.

    1979-01-01

    A review is given of some of the basic concepts and assumptions behind the current recommendations by the International Commission on Radiological Protection in ICRP Publications 26 and 28, which form the basis for the revision of the Basic Safety Standards jointly undertaken by IAEA, ILO, NEA and WHO. Special attention is given to the assumption of a linear, non-threshold dose-response relationship for stochastic radiation effects such as cancer and hereditary harm. The three basic principles of protection are discussed: justification of practice, optimization of protection and individual risk limitation. In the new ICRP recommendations particular emphasis is given to the principle of keeping all radiation doses as low as is reasonably achievable. A consequence of this is that the ICRP dose limits are now given as boundary conditions for the justification and optimization procedures rather than as values that should be used for purposes of planning and design. The fractional increase in total risk at various ages after continuous exposure near the dose limits is given as an illustration. The need for taking other sources, present and future, into account when applying the dose limits leads to the use of the commitment concept. This is briefly discussed as well as the new quantity, the effective dose equivalent, introduced by ICRP. (author)

  18. Comparative study of eye dose and chest dose received during radiopharmaceutical production processes

    International Nuclear Information System (INIS)

    Chindarkar, A.S.; Chavan, S.V.; Sawant, D.K.; Sahoo, L.; Gopalakrishnan, R.K.; Sneha, C.; Sachdev, S.S.; Dey, A.C.

    2018-01-01

    Radiopharmaceutical laboratory, BRIT, Vashi produces different radiopharmaceuticals of 131 I, 153 Sm, 99 Mo/ 99m Tc and 177 Lu. Principle gamma energies of these isotopes vary from 103 to 740 KeV and their maximum beta energies vary from 384 to 1214 KeV. In the light of the revised eye lens dose limit recommended in IAEA Basic Safety Standard Interim Edition No. GSR Part 3 (IAEA-2011), the study of radiation dose for eye lens was carried out using CaSO 4 : Dy based Thermo luminescence dosimeter (TLD). This TLD was worn at center of the forehead to measure eye lens dose. This TLD dose was then compared with chest TLD dose to deduce any correlation between these TLD doses. These TLD doses were assessed on quarterly basis. Eight quarter data of these TLD doses were compared

  19. Environmental survey at Lucas Heights Research Laboratories, 1992

    International Nuclear Information System (INIS)

    Hoffman, E.L.; Loosz, T.

    1994-07-01

    This report summarises the results from the environmental survey during 1992 and assesses the effects of radioactive discharges on both local population and the environment. None of the samples taken from possible human food chains in the vicinity of the Lucas Heights Research Laboratories contained radioactivity which could be attributed to the operation of the site. The data presented din this report clearly shows that the environmental impact of operations at LHRL has been very low. The effective dose to residents living in the immediate neighbourhood of the reactor are very difficult to measure directly but calculated dose estimates are far lower than those due to natural background radiation and medical exposures. Discharges of airborne radioactive gases were within authorised limits when averaged over the year. The dose to the most sensitive members of the public from iodine-131 releases, was -2 mSv/year and the calculated dose from released noble gases to the most exposed individuals was less than 0.01 mSv/year. These figures represent less than one per cent of the limits recommended by the National Health and Medical Research Council of Australia. The monthly average liquid effluent discharge to the Water Board Sewer during 1992 was less than 30 per cent of the permitted level for all periods except May which rose to 62 per cent. For tritium, the concentration was less than 2 per cent of the specified limit. 23 refs., 19 tabs., 5 tabs

  20. ICRP recommendations in the present and in the short term

    International Nuclear Information System (INIS)

    Valentin, Jack

    2003-01-01

    The recommendations of ICRP are either re-stated or revised at intervals of about 15 years, most recently in 1990. The protection philosophy in Publication 60 comprises justification of the practice or intervention considered; optimisation of protection; dose and risk limits and constraints to restrict the options in optimisation. For medical exposures, dose and risk limits and formal constraints are irrelevant, but Diagnostic Reference Levels serve a similar purpose. Building on this foundation, ICRP plans to issue its next recommendations around 2005. The 2005 Recommendations are likely to emphasise protection of the individual more than protection of society; to aim at protection of non-human species as well as man; to summarise and simplify advice given in various reports after Publication 60, and to be formatted as concise recommendations underpinned by separate publications with more detail. The draft will be circulated and comments will be discussed in 2004 with a view approval of the recommendations in 2005 and publication in 2005 or 2006. Thus, integration into legislation may be possible sometime between 2006 and 2010. (author)

  1. Dose mapping in category I irradiators

    International Nuclear Information System (INIS)

    Mondal, Sandip; Shinde, S.H.; Mhatre, S.G.V.

    2012-01-01

    Category I irradiators such as Gamma Chambers and Blood Irradiators are compact self shielded, dry source storage gamma irradiators offering irradiation volume of few hundred cubic centimeters. In the present work, dose distribution profiles along the central vertical plane of the irradiation volume of Gamma Chamber 900 and Blood Irradiator 2000 were measured using Fricke, FBX, and alanine dosimeters. Measured dose distribution profiles in Gamma Chamber 900 differed from the typical generic dose distribution pattern whereas that in Blood Irradiator 2000 was in agreement with the typical pattern. All reagents used were of analytical reagent grade and were used without further purification. Preparation and dose estimations of Fricke and FBX were carried out as recommended. Alanine pellets were directly placed in precleaned polystyrene container having dimensions 6.5 mm o.d., 32 mm height and 3 mm wall thickness. For these dosimeters, dose measurements were made using e-scan Bruker BioSpin alanine dedicated ESR spectrometer. Specially designed perspex jigs were used during irradiation in Gamma Chamber 900 and Blood Irradiator 2000. These jigs provided the reproducible geometry during irradiation, Absorbance measurements were made using a spectrophotometer calibrated as per the recommended procedure. In Gamma Chamber 900, there is a dose distribution variation of about 34% from top to the center, 18% from center to the bottom, and 15% from center to the periphery. Such a dose distribution profile is largely deviating from the typical profile wherein 15% variation is observed from center to the periphery on all sides. Further investigation showed that there was a nonalignment in the source and sample chamber. However, in Blood Irradiator 2000, there is a dose distribution variation of about 20% from top to the center, 15% from center to the bottom, and 12% from center to the periphery. This pattern is very much similar to the typical profile. Hence it is recommended

  2. [Current dietary exposure to mercury during pregnancy and childhood, and public health recommendations].

    Science.gov (United States)

    Llop, Sabrina; Ibarlucea, Jesús; Sunyer, Jordi; Ballester, Ferran

    2013-01-01

    Exposure to high levels of mercury during vulnerable periods (such as pregnancy and childhood) may have serious consequences for cognitive development, as observed after acute poisoning episodes in Japan and Irak. The main source of mercury exposure in the general population is consumption of certain types of fish. There is growing concern about the possible neurotoxic effects of mercury, especially in younger children in populations where fish intake is moderate to high. The scientific evidence to date is inconclusive. In Spain, the Childhood and Environment (Infancia y Medio Ambiente [INMA]) project has provided information on levels of prenatal exposure to mercury among 1800 newborns from Valencia, Sabadell, Asturias and Guipúzcoa. In general, levels were high, being above the World Health Organization's recommended dose in 24% of children and above the recommended levels of the U.S. Environmental Protection Agency in 64%. However, the results did not indicate a significant association between prenatal mercury exposure and delayed cognitive development during the second year of life. Various agencies have developed recommendations on fish consumption for pregnant women and children, due to the presence of mercury. These recommendations should be strengthened, since there is general consensus among all regional and national public administrations that fish is an essential source of nutrients for development in the early stages of life. Copyright © 2012 SESPAS. Published by Elsevier Espana. All rights reserved.

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

    Science.gov (United States)

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

    2016-06-14

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

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

    International Nuclear Information System (INIS)

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

    2016-01-01

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

  5. Collective dose as a performance measure for occupational radiation protection programs: Issues and recommendations

    International Nuclear Information System (INIS)

    Strom, D.J.; Harty, R.; Hickey, E.E.; Martin, J.B.; Peffers, M.S.; Kathren, R.L.

    1998-07-01

    Collective dose is one of the performance measures used at many US Department of Energy (DOE) contractor facilities to quantitatively assess the objectives of the radiation protection program. It can also be used as a management tool to improve the program for keeping worker doses as low as reasonably achievable (ALARA). Collective dose is used here to mean the sum of all total effective dose equivalent values for all workers in a specified group over a specified time. It is often used as a surrogate estimate of radiological risk. In principle, improvements in radiation protection programs and procedures will result in reduction of collective dose, all other things being equal. Within the DOE, most frequently, a single collective dose number, which may or may not be adjusted for workload and other factors, is used as a performance measure for a contractor. The purpose of this report is to evaluate the use of collective dose as a performance measure for ALARA programs at DOE sites

  6. Health physics society position on draft environmental protection agency recommendations for federal radiation protection guidance for occupational exposure

    International Nuclear Information System (INIS)

    Anon.

    1984-01-01

    Specific recommendations of the Health Physics Society are presented. There should not be any occupational exposure to ionizing radiation without the expectation of an overall benefit from the activity causing the exposure. Such activities should be permitted only when exposure to workers is controlled under a comprehensive radiation protection program that includes several elements: adequate, practical standards; adequately trained and qualified staff; adequately designed, operated and maintained facilities and equipment; appropriate monitoring programs, dose assessment programs and occupational exposure records; appropriate methods and procedures for controlling exposures in conformance with both the applicable limits and the ALARA philosophy; and appropriate quality assurance and audit programs

  7. Tritons at energies of 10 MeV to 1 TeV: Conversion coefficients for fluence-to-absorbed dose, equivalent dose, effective dose, and gray equivalent, calculated using Monte Carlo radiation transport code MCNPX 2.7.C

    International Nuclear Information System (INIS)

    Copeland, K.; Parker, D. E.; Friedberg, W.

    2010-01-01

    Conversion coefficients were calculated for fluence-to-absorbed dose, fluence-to-equivalent dose, fluence-to-effective dose and fluence-to-gray equivalent for isotropic exposure of an adult female and an adult male to tritons ( 3 H + ) in the energy range of 10 MeV to 1 TeV (0.01-1000 GeV). Coefficients were calculated using Monte Carlo transport code MCNPX 2.7.C and BodyBuilder TM 1.3 anthropomorphic phantoms. Phantoms were modified to allow calculation of effective dose to a Reference Person using tissues and tissue weighting factors from 1990 and 2007 recommendations of the International Commission on Radiological Protection (ICRP) and calculation of gray equivalent to selected tissues as recommended by the National Council on Radiation Protection and Measurements. At 15 of the 19 energies for which coefficients for effective dose were calculated, coefficients based on ICRP 2007 and 1990 recommendations differed by less than 3%. The greatest difference, 43%, occurred at 30 MeV. Published by Oxford Univ. Press on behalf of the US Government 2010. (authors)

  8. Helions at energies of 10 MeV to 1 TeV: Conversion coefficients for fluence-to-absorbed dose, equivalent dose, effective dose and gray equivalent, calculated using Monte Carlo radiation transport code MCNPX 2.7.C

    International Nuclear Information System (INIS)

    Copeland, K.; Parker, D. E.; Friedberg, W.

    2010-01-01

    Conversion coefficients were calculated for fluence-to-absorbed dose, fluence-to-equivalent dose, fluence-to-effective dose and fluence-to-gray equivalent, for isotropic exposure of an adult male and an adult female to helions ( 3 He 2+ ) in the energy range of 10 MeV to 1 TeV (0.01-1000 GeV). Calculations were performed using Monte Carlo transport code MCNPX 2.7.C and BodyBuilder TM 1.3 anthropomorphic phantoms modified to allow calculation of effective dose using tissues and tissue weighting factors from either the 1990 or 2007 recommendations of the International Commission on Radiological Protection (ICRP), and gray equivalent to selected tissues as recommended by the National Council on Radiation Protection and Measurements. At 15 of the 19 energies for which coefficients for effective dose were calculated, coefficients based on ICRP 2007 and 1990 recommendations differed by less than 2%. The greatest difference, 62%, occurred at 100 MeV. Published by Oxford Univ. Press on behalf of the U.S. Government 2010. (authors)

  9. Permission for the disposal of substances. Recommendation of the Radiation Protection Commission

    International Nuclear Information System (INIS)

    Baldauf, D.

    2007-01-01

    Since the Nineteen Eighties the German Radiation Protection Commission (SSK) has issued a number of recommendations for the release of weakly radioactive substances from the requirement of official approval for use. These have been summarised in a general guide [SSK 98]. The recommendations are based on the de minimis concept of the IAEA [IAEA 88] which allows an upper total dose limit for the general population of several 10 μSv per year from all substances exempt from official approval. As a means of modelling the disposal of exempt substances the general guide uses a model based on a study by Poschner and Schaller [POS 95]. The exemption values given in the general guide also take account of age groups and the dose coefficients given in the basic radiation protection standards of the EU [EU 96]. In the meantime the framework conditions have changed, due in part to new waste management regulations and in part to improvements in disposal technology. The changes in waste management law have resulted in particular from the Ordinance on the Environmentally Friendly Landfilling of Household Wastes (AbfAblV) of 20 February 2001, BGBl 2001, 305 and from the Ordinance on Landfills and Long-Term Storage Facilities (DepV) of 24 July 2002, BGBl 2002, 2807, in which the regulations of the Technical Code on Household Waste (TASi) [TASi 93] have been detailed and made binding. This has led to certain requirements being placed on existing as well as new landfills and storage facilities and related work processes, which in turn has impacted on dose calculation formulas (in particular soil sealing, covering, pretreatment of wastes). The consequences of the new requirements were investigated in a research project conducted by the Federal Radiation Protection Office (BfS) [THI 04]. For these reasons the Radiation Protection Commission has been commissioned by the Federal Ministry for Environment, Nature Conservation and Reactor Safety (BMU) to work out a recommendation for

  10. Do recommended doses of glyphosate-based herbicides affect soil invertebrates? Field and laboratory screening tests to risk assessment.

    Science.gov (United States)

    Niemeyer, Júlia Carina; de Santo, Fernanda Benedet; Guerra, Naiara; Ricardo Filho, Altair Maçaneiro; Pech, Tatiani Maria

    2018-05-01

    Despite glyphosate-based herbicides are widely used in agriculture, forestry and gardens, little is known about its effects on non-target organisms. The present work evaluated the ecotoxicity of four formulated products (Roundup ® Original, Trop ® , Zapp ® Qi 620 and Crucial ® ) on soil invertebrates. Screening ecotoxicity tests were carried out with soil and oat straw collected in a field experiment, besides laboratory-spiked soils. Screening tests included avoidance behaviour of earthworms (Eisenia andrei), collembolans (Folsomia candida) and isopods (Porcellio dilatatus) in single and multispecies tests; reproduction of collembolans (F. candida), and bait lamina in field. Non-avoidance behaviour was observed in standard tests (earthworms) in soil, neither in multispecies tests (earthworm + isopods) using oat straw, while for collembolans it occurred for the product Zapp ® Qi 620 even at the recommended dose. Reproduction of F. candida was not impaired even at high doses in laboratory-spiked soils. Feeding activity on bait lamina test was impaired in treatment corresponding to the red label product, Crucial ® . Results showed the relevance of bait lamina test on screening the impact of herbicides in the field. The findings highlight the importance of considering different formulations for the same active ingredient in risk assessment of pesticides. Copyright © 2018 Elsevier Ltd. All rights reserved.

  11. The new ICRP general recommendations

    International Nuclear Information System (INIS)

    Mason, Ch.; Kosako, T.; Kuniyoshi, H.; Kiryu, Y.; Choi, H.S.; Burns, P.A.; Pan, Z.Q.; Xia, Y.

    2007-01-01

    Regulatory views from Japan, South Korea, Australia, China and Indonesia were explained based on their regional context. Some issues, for example 'optimisation', 'dose constrains', 'natural radioactivity', were addressed from the viewpoint of how each country's current regulation system would adopt these new recommendations. It was noted that there would be a need for some flexibility in applying these new recommendations since different countries have different regulatory criteria and benchmarks as well different decision-making processes. It was also noted that definitions and terminologies should be given serious consideration with regard to non-English speaking countries to assure that the new ICRP recommendations are clearly understood, not misinterpreted, easily translated and finally applied in the field of radiation protection. In addition, some recent radiation protection activities, as well as views on utilisation of nuclear power in several countries were presented. (authors)

  12. Offsite doses from SRP radioactive releases - 1985

    International Nuclear Information System (INIS)

    Marter, W.L.

    1986-01-01

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

  13. Consultative exercise on dose assessments.

    Science.gov (United States)

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

    2001-06-01

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

  14. Leakage and accidental releases from Sillamaee waste depository and environmental risk assessment

    International Nuclear Information System (INIS)

    Bergstroem, U.; Nordlinder, S.; Aggeryd, I.

    1994-01-01

    An environmental risk assessment has been performed for the Sillamaee depository. The object of the study is to illustrate the consequences to man if the hazardous substances contained in the depository reach the sea. Two cases were studied: 1) the environmental impact at present conditions with a relatively low continuous leakage of the elements from the dam, and 2) the impact from a sudden dam collapse. The radiological dose impact on the population in the Baltic Sea area has been calculated for the observed leaking rate. The highest individual dose is less than 1μSv while for the dam collapse the dose will be in the order of 2 μSv and the dominant exposure pathway is via consumption of fish. The collective dose is about 1 manSv (emanating from fish caught in all parts of the Baltic Sea for both cases). Furthermore, the consequences of release of some metals (copper, zinc, niobium and molybdenum) were studied in the case of a dam break. In the Bay of Narva, outside the nearest coast, the additional contribution to the natural concentration in water will be neglectable for zinc and niobium. However, for copper and molybdenum the concentration will rise considerably during the first year. The additional load from the depository will still after 50 years be in the same order as published concentrations in the sea. The intake by man of those metals via fish caught in the Bay of Narva will be well below the limits of intake for zinc and molybdenum, (no recommendation of limits for niobium was found), while the calculated intake of copper from the depository will be in the same order as internationally recommended limits of intake. 34 refs

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

    Science.gov (United States)

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

    2009-01-01

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

  16. 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

  17. Age-dependent conversion coefficients for organ doses and effective doses for external neutron irradiation

    International Nuclear Information System (INIS)

    Nishizaki, Chihiro; Endo, Akira; Takahashi, Fumiaki

    2006-06-01

    To utilize dose assessment of the public for external neutron irradiation, conversion coefficients of absorbed doses of organs and effective doses were calculated using the numerical simulation technique for six different ages (adult, 15, 10, 5 and 1 years and newborn), which represent the member of the public. Calculations were performed using six age-specific anthropomorphic phantoms and a Monte Carlo radiation transport code for two irradiation geometries, anterior-posterior and rotational geometries, for 20 incident energies from thermal to 20 MeV. Effective doses defined by the 1990 Recommendation of ICRP were calculated from the absorbed doses in 21 organs. The calculated results were tabulated in the form of absorbed doses and effective doses per unit neutron fluence. The calculated conversion coefficients are used for dose assessment of the public around nuclear facilities and accelerator facilities. (author)

  18. Estimation of the fetal dose by dose measurement during an irradiation of a parotid tumor; Estimation de la dose foetale par mesure de dose lors d'une irradiation d'une tumeur de la parotide

    Energy Technology Data Exchange (ETDEWEB)

    Marchesi, V.; Graff-Cailleaud, P.; Peiffert, D. [Centre Alexis-Vautrin, 54 - Vandoeuvre-les-Nancy (France); Noel, A. [Institut National Polytechnique de Lorraine, CRAN CNRS UMR-7039, 54 - Vandoeuvre-les-Nancy (France)

    2006-11-15

    The irradiation of a five months pregnant patient has been made for a right parotid attack. In conformation with the legislative texts relative to radiation protection ( publication 84 of the ICRP) an estimation of the dose received for the fetus has been led by dose measurement on phantom. With the dose limit ( 100 mGy) recommended in the publication 84 of the ICRP neither modification of the treatment nor abortion was necessary. (N.C.)

  19. Compact and maintenance-free radio probes for environmental surveillance of the gamma dose rate

    International Nuclear Information System (INIS)

    Genrich, V.

    1998-01-01

    The author reports on his experience with the operation of radio data networks for the continuous observation of the gamma dose rate in nuclear installations. Practically at every location (within) the installation the hermetically sealed probes can record the measurement values. Moreover, the probes have proved successful in environmental surveillance where they typically work in the form of measurement rings in 10 to 30 km distance. All measurement data are organized in the form of a data base. They can be disposed of in the form of an SQL-server in the computer network (LAN) of the power plant or the institution in charge of environmental surveillance. In comparison to conventional, e.g. cable-bound measurement networks with the new radio transmission technology there are numerous advantages: - minimal cost for projection - minimal cost for installation due to simple fixing - quasi-mobile use with highest possible flexibility - maintenance-free operation and high degree of operating reliability. (orig.) [de

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

    International Nuclear Information System (INIS)

    2014-07-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2014-07-15

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

  2. Environmental and Effluent Monitoring at ANSTO Sites, 2002-2003

    Energy Technology Data Exchange (ETDEWEB)

    Hoffmann, E L; Ferris,; Markich, S J

    2004-10-01

    This report presents the results of environmental and effluent monitoring at the Lucas Heights Science and Technology Centre (LHSTC) and the National Medical Cyclotron (NMC) from January 2002 to June 2003. Potential effective dose rates to the general public from airborne discharges from the LHSTC site were less than 0.01 mSv/year, well below the 1 mSv/year dose rate limit for long term exposure that is recommended by the Australian National Occupational Health and Safety Commission. The effective dose rates to hypothetical individuals potentially exposed to radiation in routine liquid effluent discharges from the LHSTC were recently calculated to be less than 0.001 mSv/year. This is much less than dose rates estimated for members of public potentially exposed to airborne emissions. The levels of tritium detected in roundwater and stormwater at the LHSTC were less than the Australian drinking water guidelines. The airborne and liquid effluent emissions from the NMC were below the ARPANSA-approved notification levels and NSW EPA limits, respectively. ANSTO's routine operations at the LHSTC and the NMC make only a very small addition to the natural background radiation dose experienced by members of the Australian public. (authors)

  3. Estimation of environmental transfer of plutonium and the dose to man

    International Nuclear Information System (INIS)

    1981-09-01

    The need to examine the behaviour of individual radionuclides in the environment is stressed. Sometimes unique pathways of exposure exist and more specialized methods of dose estimation could be considered. The toxicity of the alpha emitting plutonium isotopes is of concern and their long half-lives lead to persistence in the environment and long-term potential for exposing man. Some formulas are therefore presented for making preliminary estimates of environmental transfer and dose for the radioisotopes of the element plutonium. Exposure of man to plutonium in the environment may occur by inhalation or ingestion - the inhalation and ingestion intake rates for which specific pathways have been considered are listed. The primary pathway to man is the inhalation intake; the most important ingestion intake is the consumption of plant foods due to the greater concentration achieved and the higher consumption rates of these foods. Also discussed is plutonium in the nuclear fuel cycle, the release of plutonium from current nuclear installations, the occurrence of plutonium from weapons fallout, airborne releases of plutonium (concentration in the air, deposition rate, resuspension, transfer to plants - foliar and root uptake - transfer to milk, etc.), liquid release (concentration in water, transfer to drinking water, to fish, to plants by irrigation, to milk, to meat). The importance of the release situation and local environment conditions including land and water utilization, population factors and habits for any further investigation is pointed out

  4. CARCINOGENIC EFFECTS OF LOW DOSES OF IONIZING RADIATION

    Science.gov (United States)

    Carcinogenic Effects of Low Doses of Ionizing RadiationR Julian Preston, Environmental Carcinogenesis Division, NHEERL, U.S. Environmental Protection Agency, Research Triangle Park, NC 27711The form of the dose-response curve for radiation-induced cancers, particu...

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

    International Nuclear Information System (INIS)

    Blanchard, A.D.H.

    1997-01-01

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

  6. What we expect of ICRP new recommendations

    International Nuclear Information System (INIS)

    Yoshikawa, S.

    2004-01-01

    We believe that it is essential for Japan to continue to maintain and promote nuclear power generation. To promote nuclear power generation, we believe it is important that the effect of low-level radiation on humans and the exposure dose limits have to be widely and properly understood by the general public and radiation workers. From such a point of view, we express our agreement with ICRP latest attempt that is aimed at preparing a simple and easy-to understanding radiological protection system. We would like to express some of our opinions about ICRP new recommendations. - The relation between PAL and the conventional dose limit should be shown clearly. - Optimisation on low-enough level (natural background level) should be omitted. - The process of optimisation must take the state of affairs in each country into consideration. - The dose limits (100 mSv/5 yrs and 50 mSv/yr) for workers should not be changed. (Single-year dose limit of 20 mSv/yr has no flexibility and has serious impact on nuclear power operators.). - Full discussion is necessary to establish the radiological protection criteria for environment. We appreciate ICRP's releases and calls for opinions regarding the new recommendations. We hope ICRP continues to disclose the status of discussion in a timely manner, and invite opinions. (author)

  7. Environmental survey at Lucas Heights Research Laboratories, 1989

    International Nuclear Information System (INIS)

    Hoffman, E.L.; Arthur, J.

    1990-09-01

    Results are presented of an environmental survey conducted in the neighbourhood of the Lucas Heights Research Laboratories during 1989. No radioactivity which could have originated from these laboratories was found in samples collected from possible human food chains. All low-level liquid and gaseous waste discharges were within authorised limits. The maximum possible annual dose to the general public from airborne waste during this period is estimated to be less than 0.01 millisieverts, which is one per cent of the limit for long-term exposure that is recommended by the National Health and Medical Research Council. 9 refs., 17 tabs., 2 figs

  8. Environmental survey at Lucas Heights Research Laboratories, 1990

    International Nuclear Information System (INIS)

    Hoffmann, E.L.

    1991-10-01

    Results are presented of an environmental survey conducted in the neighbourhood of the Lucas Heights Research Laboratories during 1990. No radioactivity which could have originated from these laboratories was found in samples collected from possible human food chains. All low-level liquid and gaseous waste discharges were within authorised limits. The maximum possible annual dose to the general public from airborne waste during this period is estimated to be less than 0.01 millisieverts, which is one per cent of the limit for long-term exposure that is recommended by the National Health and Medical Research Council. 11 refs., 16 tabs., 2 figs

  9. Environmental survey at Lucas Heights Research Laboratories, 1987

    International Nuclear Information System (INIS)

    Giles, M.S.; Foy, J.J.; Hoffmann, E.L.

    1989-12-01

    Results are presented of an environmental survey conducted in the neighbourhood of the Lucas Heights Research Laboratories during 1987. No radioactivity which could have originated from these laboratories was found in samples collected from possible human food chains. All low-level liquid and gaseous waste discharges were within authorized limits. The maximum possible annual dose to the general public from airborne waste during this period is estimated to be less than 0.01 millisieverts, which is one per cent of the limit for long-term exposure that is recommended by the National Health and Medical Research Council. 9 refs., 18 tabs., 2 figs

  10. Environmental survey at Lucas Heights Research Laboratories, 1984

    International Nuclear Information System (INIS)

    Giles, M.S.; Dudaitis, A.

    1986-12-01

    Results are presented of the environmental survey conducted in the neighbourhood of the Lucas Heights Research Laboratories during 1984. These results are satisfactory. No radioactivity which could have originated from these laboratories was found in samples collected from possible human food chains. All low-level liquid and gaseous waste discharges were within authorised limits. The maximum possible annual dose to the general public from airborne waste discharges during this period is estimated to be less than 0.01 millisieverts, which is one per cent of the limit for long-term exposure that is recommended by the National Health and Medical Research Council

  11. DOZIM - evaluation dose code for nuclear accident

    International Nuclear Information System (INIS)

    Oprea, I.; Musat, D.; Ionita, I.

    2008-01-01

    During a nuclear accident an environmentally significant fission products release can happen. In that case it is not possible to determine precisely the air fission products concentration and, consequently, the estimated doses will be affected by certain errors. The stringent requirement to cope with a nuclear accident, even minor, imposes creation of a computation method for emergency dosimetric evaluations needed to compare the measurement data to certain reference levels, previously established. These comparisons will allow a qualified option regarding the necessary actions to diminish the accident effects. DOZIM code estimates the soil contamination and the irradiation doses produced either by radioactive plume or by soil contamination. Irradiations either on whole body or on certain organs, as well as internal contamination doses produced by isotope inhalation during radioactive plume crossing are taken into account. The calculus does not consider neither the internal contamination produced by contaminated food consumption, or that produced by radioactive deposits resuspension. The code is recommended for dose computation on the wind direction, at distances from 10 2 to 2 x 10 4 m. The DOZIM code was utilized for three different cases: - In air TRIGA-SSR fuel bundle destruction with different input data for fission products fractions released into the environment; - Chernobyl-like accident doses estimation; - Intervention areas determination for a hypothetical severe accident at Cernavoda Nuclear Power Plant. For the first case input data and results (for a 60 m emission height without iodine retention on active coal filters) are presented. To summarize, the DOZIM code conception allows the dose estimation for any nuclear accident. Fission products inventory, released fractions, emission conditions, atmospherical and geographical parameters are the input data. Dosimetric factors are included in the program. The program is in FORTRAN IV language and was run on

  12. Identifying environmental, social, and psychological correlates of meeting the recommended physical activity levels for colon cancer prevention among Japanese adults.

    Science.gov (United States)

    Ishii, Kaori; Shibata, Ai; Oka, Koichiro

    2013-11-01

    Although physical activity reduces the risk of diseases such as cancer, diabetes and cardiovascular disease, a large proportion of the population is not sufficiently physically active. Therefore, the present study examined the environmental, social, and psychological correlates for meeting the 2 recommended physical activity criteria: ≥420 min per week of at least moderate-intensity activity (MPA criterion) and ≥210 min per week of vigorous activity (VPA criterion) for colon cancer prevention among Japanese adults. Cross-sectional study. The sample included 2000 Japanese adults aged 20-79 years. An Internet-based survey was used to assess seven sociodemographic variables (e.g., education level, employment status), environmental variables (home fitness equipment, access to facilities, neighborhood safety, aesthetic sensibilities, and frequency of observing others exercising, residential area), social variables (social support), psychological variables (self-efficacy, perceived positive (pros) and negative (cons) aspects of exercise), and physical activity. The adjusted odds of meeting each physical activity criterion by these variables were calculated. Overall, 22.3% of the study population met the criterion of MPA, and 7.3% met the criterion of VPA. Having high self-efficacy, fewer perceived cons, possessing home fitness equipment, reporting enjoyable scenery, and living in a rural area were significantly associated with meeting the recommended criteria. Participants who met the 2 activity recommendations differed by self-efficacy, cons, possession of home fitness equipment, reporting of enjoyable scenery, and residential area. These findings imply that strategies to promote more intense physical activities specifically in terms of these variables may be necessary for colon cancer prevention. Crown Copyright © 2013. Published by Elsevier Ltd. All rights reserved.

  13. Final generic environmental impact statement on decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    1988-08-01

    This final generic environmental impact statement was prepared as part of the requirement for considering changes in regulations on decommissioning of commercial nuclear facilities. Consideration is given to the decommissioning of pressurized water reactors, boiling water reactors, research and test reactors, fuel reprocessing plants (FRPs) (currently, use of FRPs in the commercial sector is not being considered), small mixed oxide fuel fabrication plants, uranium hexafluoride conversion plants, uranium fuel fabrication plants, independent spent fuel storage installations, and non-fuel-cycle facilities for handling byproduct, source and special nuclear materials. Decommissioning has many positive environmental impacts such as the return of possibly valuable land to the public domain and the elimination of potential problems associated with increased numbers of radioactively contaminated facilities with a minimal use of resources. Major adverse impacts are shown to be routine occupational radiation doses and the commitment of nominally small amounts of land to radioactive waste disposal. Other impacts, including public radiation doses, are minor. Mitigation of potential health, safety, and environmental impacts requires more specific and detailed regulatory guidance than is currently available. Recommendations are made as to regulatory decommissioning particulars including such aspects as decommissioning alternatives, appropriate preliminary planning requirements at the time of commissioning, final planning requirements prior to termination of facility operations, assurance of funding for decommissioning, environmental review requirements. 26 refs., 7 figs., 68 tabs

  14. TMI-2 [Three Mile Island Unit 2] reactor building dose reduction task force

    International Nuclear Information System (INIS)

    Daniels, R.S.

    1988-01-01

    In late October 1982, the director of Three Mile Island Unit 2 (TMI-2) created the dose reduction task force with the objective of identifying the principal radiological sources in the reactor building and recommending actions to minimize the dose to workers on labor-intensive projects. Members of the task force were drawn form various groups at TMI. Findings and recommendations were presented to the US Nuclear Regulatory Commission in a briefing on November 18, 1982. The task force developed a three-step approach toward dose reduction. Step 1 identified the radiological sources. Step 2 modeled the source and estimated its contribution to the general area dose rates. Step 3 recommended actions to achieve dose reductions consistent with general exposure rate goals

  15. Conversion and correction factors for historical measurements of iodine-131 in Hanford-area vegetation, 1945--1947. Hanford Environmental Dose Reconstruction Project

    Energy Technology Data Exchange (ETDEWEB)

    Mart, E.I.; Denham, D.H.; Thiede, M.E.

    1993-12-01

    This report is a result of the Hanford Environmental Dose Reconstruction (HEDR) Project whose goal is to estimate the radiation dose that individuals could have received from emissions since 1944 at the U.S. Department of Energy`s (DOE) Hanford Site near Richland, Washington. The HEDR Project is conducted by Battelle, Pacific Northwest Laboratories (BNW). One of the radionuclides emitted that would affect the radiation dose was iodine-131. This report describes in detail the reconstructed conversion and correction factors for historical measurements of iodine-131 in Hanford-area vegetation which was collected from the beginning of October 1945 through the end of December 1947.

  16. Dosimetric radiation protection quantities. Impact of the forthcoming ICRP recommendations

    International Nuclear Information System (INIS)

    Pradhan, A.S.; Lee, J.I.; Kim, J.L.; Kim, B.H.

    2008-01-01

    The physical quantities namely fluence, kerma and absorbed dose provide the base for the operational and the protection quantities. The absorbed dose continues to be the fundamental physical quantity for the radiological protection. The most striking feature relating the quantities in the forthcoming recommendations is the updating of the radiation and tissue weighting factors based on the latest available scientific information on radiobiology and the physics of radiation exposure. This is bound to make a significant impact in arriving at the equivalent doses and effective dose. For external exposures of neutrons, the forthcoming recommendations are going to improve the relationship between the operational and protection quantities. The changes in the tissue weighting factors of some tissues/organs, the inclusion of several new tissues/organs for the consideration of tissue weighting factors and the use of the proposed Reference Male and Reference Female voxel phantoms would require new conversion coefficients and dose coefficients for external and internal exposures. The other striking feature appears to be the details of the concepts to ensure that the protections quantities are used for the appropriate and intended purposes only and the misuse is avoided. (author)

  17. External contamination and skin dose. From ICRP and regulations to skin dose evaluation in practice

    International Nuclear Information System (INIS)

    Le Coulteulx, I.; Apretna, D.; Beaugerie, M.; Fenolland, J.; Frey, R.; Gonin, M.; Landry, B.; Laporte, E.; Le Guen, B.; Leval, D.

    2006-01-01

    Dose limitation to the skin is an objective of radiation protection. Our aim is to propose in case of skin contamination in EDF NPPs a simply, quickly and reproducible procedure for evaluating skin dose. French regulation admit an annual limit for skin dose over one square centimeter equal to 500 mSv. ICRP Publication 26 and 60 recommend that dose assessment be performed only if skin dose might be equal to or more than 50 mSv at basal cells. To respect this recommendation, an alert value (A) must be determined. This value is the lowest value of measurement from which dose assessment has to be made, based on the hypothesis that uninterrupted work time in controlled area is no more than four hours. This alert value (A) has been established for three external detection equipments, and for the ten radionuclides commonly detected. In case of external contamination, a first measurement is performed. If the value exceeds value (A), other measurements are instituted because skin dose evaluation needs to know other parameters as: - the radioactivity of the most contaminated square centimeter of the skin, - the identity of the radionuclides and their relative proportion. At the same time, we have to evaluate the length of the exposure. At last, we use different compiled results in a program developed from excel software which allow to calculate automatically the skin dose. This work has allowed us to publish an occupational health guideline about the assessment of skin dose in case of external contamination in EDF NPPs and to create an information booklet for workers. The authors propose to examine used methodology and to demonstrate the software. (authors)

  18. Workers and the ICRP recommendations

    International Nuclear Information System (INIS)

    Zerbib, J.C.

    1979-01-01

    In both the preparation and the application of the recommendations presented by the ICRP one important voice has been absent: that of the workers in the nuclear industry. A large number of specialists are studying their situation from all points of view, in their different capacities as workers, consumers and male or female members of the public, but this extensive study is being done without consulting them, without their opinion even being asked for. The paper discusses such deficiencies, in particular all those aspects which distinguish these recommendations from a legal text. The lack of conciseness in the definition of the limit which the average annual dose to a large group of workers must not exceed (500 mrad) is considered. The possibility of a large number of workers being exposed for a long period is not acceptable if the decision is left to the manager of a nuclear facility alone. Cost-benefit analysis, as it is described in the ICRP text, cannot be considered to provide credible protection from the point of view of workers. Moreover, the various ICRP recommendations fail to mention such important matters as allowance for low-dose effects, disparities in the social security coverage offered to various categories of workers in the event of occupational illness, and the increasing use of migrant workers for difficult decontamination and maitenance tasks. At a time when it is thought that nuclear technology can be standardized, the French Democratic Labour Confederation (CFDT) expresses its fears concerning the practical application of the ICRP recommendations; for example, the text of ICRP Publication 26 has not yet been translated into French, but Euratom has already proposed directives for its application in Member States

  19. Research on environmental impacts of nuclear power and emergency preparedness

    International Nuclear Information System (INIS)

    Vuori, S.

    1994-01-01

    The future needs of nuclear energy research in Finland have been recently reviewed by an expert group. Concerning the research on environmental impacts and emergency preparedness, the group recommended the establishment of a common coordination group for the different projects in this field. The main objectives in this field include efficient accident management and mitigation of off-site consequences with appropriate countermeasures and more reliable real time prediction tools for atmospheric dispersion and radiation dose evaluations as well as efficient and fast real time surveillance and measurement systems. (orig.)

  20. Environmental survey at the AAEC Research Establishment, Lucas Heights - results for 1979

    International Nuclear Information System (INIS)

    Giles, M.S.; Dudaitis, A.

    1980-09-01

    This report presents the results of the environmental survey at the AAEC Research Establishment, Lucas Heights, during 1979. They show that the only radioactivity detected which could be of AAECRE origin and which could also be ingested by humans was due to tritium. The maximum credible dose which a member of the public could receive from this radioactivity is calculated to be one ten thousandth of the derived working limit consistent with the latest recommendations of the International Commission on Radiological Protection

  1. A preliminary examination of audience-related communications issues for the Hanford Environmental Dose Reconstruction Project

    Energy Technology Data Exchange (ETDEWEB)

    Holmes, C.W.

    1991-04-01

    The Hanford Environmental Dose Reconstruction (HEDR) Project will estimate radiation doses people may have received from exposure to radioactive materials released during past operations at the US Department of Energy's (DOE) Hanford Site near Richland, Washington. The HEDR Project was initiated in response to public concerns about possible health impacts from past releases of radioactive materials from Hanford. The TSP recognized early in the project that special mechanisms would be required to effectively communicate to the many different concerned audiences. Accordingly, the TSP directed PNL to examine methods for communicating causes and effects of uncertainties in the dose estimates. After considering the directive and discussing it with the Communications Subcommittee of the TSP, PNL undertook a broad investigation of communications methods to consider for inclusion in the TSP's current communications program. As part of this investigation, a literature review was conducted regarding risk communications. A key finding was that, in order to successfully communicate risk-related information, a thorough understanding of the knowledge level, concerns and information needs of the intended recipients (i.e., the audience) is necessary. Hence, a preliminary audience analysis was conducted as part of the present research. This report summarizes the results of this analysis. 1 ref., 9 tabs.

  2. Development of environmental risk assessment framework using index method

    International Nuclear Information System (INIS)

    Ali, M.W.; Wu, Y.

    2000-01-01

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

  3. Phase 1 study of the investigational Aurora A kinase inhibitor alisertib (MLN8237) in East Asian cancer patients: pharmacokinetics and recommended phase 2 dose.

    Science.gov (United States)

    Venkatakrishnan, Karthik; Kim, Tae Min; Lin, Chia-Chi; Thye, Lim Soon; Chng, Wee Joo; Ma, Brigette; Chen, Ming Huang; Zhou, Xiaofei; Liu, Hua; Kelly, Virginia; Kim, Won Seog

    2015-08-01

    This phase 1 study assessed the pharmacokinetics (PK), maximum tolerated dose (MTD)/recommended phase 2 dose (RP2D), safety, and preliminary efficacy of the investigational Aurora A kinase inhibitor, alisertib, in East Asian patients with advanced solid tumors or lymphomas. Patients received alisertib twice-daily (BID) for 7 days in 21-day cycles. Doses were escalated (3 + 3) from 30 mg BID based on cycle 1 dose-limiting toxicities (DLTs) until the MTD, followed by expansion for PK/safety characterization. Thirty-six patients (61 % Chinese, 36 % Korean, 3 % Malay) received alisertib (30 mg BID, n = 30; 40 mg BID, n = 6; median, 2.5 cycles). Alisertib exposures increased approximately dose proportionally, and mean half-life was 16 h. Geometric mean apparent oral clearance (2.65 L/h) was 40 % lower than previous estimates in Western patients, resulting in approximately 70 % higher mean dose-normalized, steady-state exposures (735 nM*h/mg) in East Asian patients. Two patients experienced DLTs at 40 mg BID (grade 3 stomatitis; grade 4 neutropenia); the MTD/RP2D was 30 mg BID. Common toxicities (grade ≥3 at RP2D) were neutropenia (50 %), diarrhea (13 %), and stomatitis (10 %). One patient with extranodal T-/NK-cell lymphoma (nasal type) achieved a partial response and 18 (51 %) had stable disease. The MTD/RP2D of alisertib in East Asian patients (30 mg BID) was lower than in Western patients (50 mg BID), consistent with higher systemic exposures in the East Asian population. Alisertib was generally well tolerated and showed signs of antitumor activity in East Asian cancer patients.

  4. Dose monitoring in nuclear emergency

    International Nuclear Information System (INIS)

    Nan Hongjie; Yang Zhongping; Lei Xin

    2012-01-01

    In order to protect people from irradiation sickness and rebuild the radiation filed in nuclear emergency, personal and environmental dose need to be monitored. The application of TLD in dose monitoring is discussed in this paper. (authors)

  5. Consideration of the volume dependence of tolerance doses

    International Nuclear Information System (INIS)

    Gremmel, H.; Wendhausen, H.

    1977-01-01

    A general formula for consideration of the dependence of tolerance doses upon volume is obtained by mathematical evaluation of known skin tolerance doses. The validity for different organs is verified using available data of literature. It is recommended to introduce the volume dependence into the Ellis-formula for tolerance doses. (orig.) [de

  6. Atmospheric transport and dispersion modeling for the Hanford Environmental Dose Reconstruction Project

    International Nuclear Information System (INIS)

    Ramsdell, J.V.

    1991-07-01

    Radiation doses that may have resulted from operations at the Hanford Site are being estimated in the Hanford Environmental Dose Reconstruction (HEDR) Project. One of the project subtasks, atmospheric transport, is responsible for estimating the transport, diffusion and deposition of radionuclides released to the atmosphere. This report discusses modeling transport and diffusion in the atmospheric pathway. It is divided into three major sections. The first section of the report presents the atmospheric modeling approach selected following discussion with the Technical Steering Panel that directs the HEDR Project. In addition, the section discusses the selection of the MESOI/MESORAD suite of atmospheric dispersion models that form the basis for initial calculations and future model development. The second section of the report describes alternative modeling approaches that were considered. Emphasis is placed on the family of plume and puff models that are based on Gaussian solution to the diffusion equations. The final portion of the section describes the performance of various models. The third section of the report discusses factors that bear on the selection of an atmospheric transport modeling approach for HEDR. These factors, which include the physical setting of the Hanford Site and the available meteorological data, serve as constraints on model selection. Five appendices are included in the report. 39 refs., 4 figs., 2 tabs

  7. Recommendations to reduce hand exposure for standard nuclear medicine procedures

    International Nuclear Information System (INIS)

    Sans-Merce, M.; Ruiz, N.; Barth, I.; Carnicer, A.; Donadille, L.; Ferrari, P.; Fulop, M.; Ginjaume, M.; Gualdrini, G.; Krim, S.; Mariotti, F.; Ortega, X.; Rimpler, A.; Vanhavere, F.; Baechler, S.

    2011-01-01

    The optimization of the extremity dosimetry of medical staff in nuclear medicine was the aim of the Work Package 4 (WP4) of the ORAMED project, a Collaborative Project (2008–2011) supported by the European Commission within its 7th Framework Programme. Hand doses and dose distributions across the hands of medical staff working in nuclear medicine departments were evaluated through an extensive measurement program involving 32 hospitals in Europe and 139 monitored workers. The study included the most frequently used radionuclides, 99m Tc- and 18 F-labelled radiopharmaceuticals for diagnostic and 90 Y-labelled Zevalin ® and DOTATOC for therapy. Furthermore, Monte Carlo simulations were performed in different predefined scenarios to evaluate separately the efficacy of different radiation protection measures by comparing hand dose distributions according to various parameters. The present work gives recommendations based on results obtained with both measurements and simulations. This results in nine practical recommendations regarding the positioning of the dosemeters for an appropriate skin dose monitoring and the best protection means to reduce the personnel exposure.

  8. Evaluation of radiation dose to neonate on special care baby unit

    International Nuclear Information System (INIS)

    Adam, A. Y. I.

    2012-08-01

    A total of 132 patients in One-armed Maternity Hospital in Khartoum State. ESDs from patient exposure parameters using DosCal software. Effective doses (E) were calculated using published conversion factor and methods recommended by the national Radiological Protection Board (NRPB). The mean patient dose was 80 μGy per procedures. The mean organ doses per procedures were ranged between 0.04 to 0.0002 mGy per procedure. The mean effective dose was 0.02 mSv. Patients' doses showed wide variations. This variation in patient dose could be attributed to the variation in patient weight, tube voltage and tube current time product.The radiation risk per procedures was very low. However, due to their sensitive tissues, additional dose reduction is justifiable. A dedicated x-ray machine with additional filtration is recommended for patient dose reductions. (Author)

  9. Maltese CT doses for commonly performed examinations demonstrate alignment with published DRLs across europe

    International Nuclear Information System (INIS)

    Zarb, F.; McEntee, M.; Rainford, L.

    2012-01-01

    This work recommends dose reference levels (DRLs) for abdomen, chest and head computerised tomography (CT) examinations in Malta as the first step towards national CT dose optimisation. Third quartiles volume CT dose index values for abdomen: 12.1 mGy, chest: 13.1 mGy and head: 41 mGy and third quartile dose-length product values for abdomen: 539.4, chest: 492 and head: 736 mGy cm -1 are recommended as Maltese DRLs derived from this first Maltese CT dose survey. These values compare well with DRLs of other European countries indicating that CT scanning in Malta is consistent with standards of good practice. Further work to minimise dose without affecting image quality and extending the establishment of DRLs for other CT examinations is recommended. (authors)

  10. Prehospital Care for the Adult and Pediatric Seizure Patient: Current Evidence Based Recommendations

    Directory of Open Access Journals (Sweden)

    Eric C. Silverman

    2017-04-01

    Full Text Available Introduction: We sought to develop evidence-based recommendations for the prehospital evaluation and treatment of adult and pediatric patients with a seizure and to compare these recommendations against the current protocol used by the 33 emergency medical services (EMS agencies in California. Methods: We performed a review of the evidence in the prehospital treatment of patients with a seizure, and then compared the seizure protocols of each of the 33 EMS agencies for consistency with these recommendations. We analyzed the type and route of medication administered, number of additional rescue doses permitted, and requirements for glucose testing prior to medication. The treatment for eclampsia and seizures in pediatric patients were analyzed separately. Results: Protocols across EMS Agencies in California varied widely. We identified multiple drugs, dosages, routes of administration, re-dosing instructions, and requirement for blood glucose testing prior to medication delivery. Blood glucose testing prior to benzodiazepine administration is required by 61% (20/33 of agencies for adult patients and 76% (25/33 for pediatric patients. All agencies have protocols for giving intramuscular benzodiazepines and 76% (25/33 have protocols for intranasal benzodiazepines. Intramuscular midazolam dosages ranged from 2 to 10 mg per single adult dose, 2 to 8 mg per single pediatric dose, and 0.1 to 0.2 mg/kg as a weight-based dose. Intranasal midazolam dosages ranged from 2 to 10 mg per single adult or pediatric dose, and 0.1 to 0.2 mg/kg as a weight-based dose. Intravenous/intrasosseous midazolam dosages ranged from 1 to 6 mg per single adult dose, 1 to 5 mg per single pediatric dose, and 0.05 to 0.1 mg/kg as a weight-based dose. Eclampsia is specifically addressed by 85% (28/33 of agencies. Forty-two percent (14/33 have a protocol for administering magnesium sulfate, with intravenous dosages ranging from 2 to 6 mg, and 58% (19/33 allow benzodiazepines to be

  11. Final environmental impact statement. Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    1980-10-01

    This volume contains the appendices for the Final Environmental Impact Statement for the Waste Isolation Pilot Plant (WIPP). Alternative geologic environs are considered. Salt, crystalline rock, argillaceous rock, and tuff are discussed. Studies on alternate geologic regions for the siting of WIPP are reviewed. President Carter's message to Congress on the management of radioactive wastes and the findings and recommendations of the interagency review group on nuclear waste management are included. Selection criteria for the WIPP site including geologic, hydrologic, tectonic, physicochemical compatability, and socio-economic factors are presented. A description of the waste types and the waste processing procedures are given. Methods used to calculate radiation doses from radionuclide releases during operation are presented. A complete description of the Los Medanos site, including archaeological and historic aspects is included. Environmental monitoring programs and long-term safety analysis program are described

  12. Development of environmental radiation control technology

    International Nuclear Information System (INIS)

    Han, M. H.; Kim, E. H.; Keum, D. K.; Kang, M. J.; Jang, B. W.

    2010-04-01

    The objectives of the study are to development of an urban atmospheric dispersion model and data assimilation technique for improving the reliability, to develop the technology for assessing the radiation impact to biota and the surface water transport model, to develop the analytical techniques for the indicator radionuclides on decommissioning of nuclear facilities and nuclear waste disposal sites and to assess of the national environmental radiation impact and establish the optimum management bases of natural radiation. The obtained results might be used; for assessing the radiological effects due to and radiological incident in an urban area, for assessing radiation doses on biota for the environmental protection from ionizing radiation with the application of new concept of the ICP new recommendation, for analyzing the indicator radionuclides on decommissioning of nuclear facilities and nuclear waste disposal sites, and for providing the natural radionuclide database of Korea to international organizations such as UNSCEAR. It can be used for emphasizing relative nuclear safety

  13. Management of pancreatic exocrine insufficiency: Australasian Pancreatic Club recommendations.

    Science.gov (United States)

    Toouli, James; Biankin, Andrew V; Oliver, Mark R; Pearce, Callum B; Wilson, Jeremy S; Wray, Nicholas H

    2010-10-18

    Pancreatic exocrine insufficiency (PEI) occurs when the amounts of enzymes secreted into the duodenum in response to a meal are insufficient to maintain normal digestive processes. The main clinical consequence of PEI is fat maldigestion and malabsorption, resulting in steatorrhoea. Pancreatic exocrine function is commonly assessed by conducting a 3-day faecal fat test and by measuring levels of faecal elastase-1 and serum trypsinogen. Pancreatic enzyme replacement therapy is the mainstay of treatment for PEI. In adults, the initial recommended dose of pancreatic enzymes is 25,000 units of lipase per meal, titrating up to a maximum of 80,000 units of lipase per meal. In infants and children, the initial recommended dose of pancreatic enzymes is 500 units of lipase per gram of dietary fat; the maximum daily dose should not exceed 10,000 units of lipase per kilogram of bodyweight. Oral pancreatic enzymes should be taken with meals to ensure adequate mixing with the chyme. Adjunct therapy with acid-suppressing agents may be useful in patients who continue to experience symptoms of PEI despite high-dose enzyme therapy. A dietitian experienced in treating PEI should be involved in patient management. Dietary fat restriction is not recommended for patients with PEI. Patients with PEI should be encouraged to consume small, frequent meals and to abstain from alcohol. Medium-chain triglycerides do not provide any clear nutritional advantage over long-chain triglycerides, but can be trialled in patients who fail to gain or to maintain adequate bodyweight in order to increase energy intake.

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

    International Nuclear Information System (INIS)

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

    2009-01-01

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

  15. Detection of sub micro Gray dose levels using OSL phosphor LiMgPO{sub 4}:Tb,B

    Energy Technology Data Exchange (ETDEWEB)

    Rawat, N.S., E-mail: naru@barc.gov.in [Radiological Physics and Advisory Division, Bhabha Atomic Research Centre, Trombay, Mumbai (India); Dhabekar, Bhushan [Radiological Physics and Advisory Division, Bhabha Atomic Research Centre, Trombay, Mumbai (India); Muthe, K.P. [Technical Physics Division, Bhabha Atomic Research Centre, Trombay, Mumbai (India); Koul, D.K.; Datta, D. [Radiological Physics and Advisory Division, Bhabha Atomic Research Centre, Trombay, Mumbai (India)

    2017-04-15

    Highlights: • LiMgPO4:Tb,B has been studied and shown to possesses minimum measurable dose (MMD) in sub micro Gray region. • MMD as low as 0.49 µGy in readout time of less than 1 s at stimulation intensity of 32 mW/cm{sup 2} has been achieved. • The OSL measurements for low doses has strengthened and validated this claim. • OSL spectrum shows several emission peaks and the prominent peak around 380 nm. - Abstract: Detection of sub micro Gray doses finds application in personnel and environmental monitoring, and nuclear forensics. Recently developed LiMgPO{sub 4}:Tb,B (LMP) is highly sensitive Optically Stimulated Luminescence (OSL) phosphor with excellent dosimetric properties. The OSL emission spectrum of LMP consists of several peaks attributed to characteristic Tb{sup 3+} emission. The OSL emission peak at 380 nm is favorable for bi-alkali PMT used in RISO reader system. It is demonstrated that significant improvement in dose detection threshold can be realized for LMP by optimization of continuous wave (CW–) OSL parameters like stimulation intensity and readout time. The minimum measurable dose (MMD) as low as 0.49 µGy in readout time of less than 1 s at stimulation intensity of 32 mW/cm{sup 2} has been achieved using this phosphor. The recommendations for choice of parameters for personnel and environmental monitoring are also discussed.

  16. Dose to patients and professionals in cardiology interventional: Progress of multicenter group Doccaci

    International Nuclear Information System (INIS)

    Sanchez, R. M.; Vano, E.; Fernandez, J. M.; Goicolea Ruigomez, J.; Pifarre, X.; Escaned, J.; Rovira, J. J.; Garcia del Blanco, B.; Carrera, F.; Diaz, J. F.; Ordiales, J. M.; Nogales, J. M.; Hernandez, J.; Bosa, F.; Rosales, F.; Saez, J. R.; Soler, M. M.; Romero, M. A.

    2013-01-01

    The multidisciplinary group and multicenter DOCCACI (dosimetry and quality assurance in interventional cardiology), sponsored by the section of haemodynamics of the Spanish society of Cardiology, is intended to propose reference levels to doses received by patients in interventional cardiology procedures such as recommended by the International Commission on radiological protection It also investigates the doses received by professionals, in particular dose in Crystallyne whose recommended limit dose has been reduced recently from 150 to 20 mSv/year. (Author)

  17. Implementation of the ICRP 2007 recommendations in Korea

    International Nuclear Information System (INIS)

    Cho, Kun-Woo

    2008-01-01

    Full text: International Commission on Radiological Protection (ICRP) is about to publish new recommendations on radiation protection. International Atomic Energy Agency (IAEA) is also under process in revising its International Basic Safety Standards (BSS) to take into account of the changes of the ICRP recommendations. As soon as the revision of the BSS is completed, Korean government is considering to implement those changes in the BSS and the ICRP recommendations into its national radiation protection laws and regulations. This paper introduces the current activities and future prospects in this matter. In the 2007 ICRP recommendations, there are some new concepts, principles and quantities such as the changes in the nominal risk coefficient for cancer and hereditary effects, new definitions on the tissue weighting factors and radiation weighting factors for neutron and proton, extended application of the dose constraints in all exposure situations in source-related radiation protection, and the introduction of new system of protection for non-human species. Based on the study carried out by KINS so far, the following points are identified as major areas that need for further in-depth review and consideration for the implementation of the ICRP 2007 recommendations into Korean radiation protection laws and regulations; changes in the radiation risk factors, radiation weighting factors and tissue weighting factors, maintenance of the ICRP 60 dose limits, practical application of the dose constraints and determination of the reference levels in many source to individual exposure relationships, change from process-based system to exposure situation-based system, strengthening of the principle of optimization in all exposure situations, system of radiation protection for the environment, practical application of the exclusion and exemption principles, active participation of the stake holders, changes in glossary etc. The study for the implementation of the ICRP

  18. Environmental survey at the Lucas Heights Research Laboratories. 1983

    International Nuclear Information System (INIS)

    Giles, M.S.; Dudaitis, A.

    1985-12-01

    Results are presented of the environmental survey conducted in the neighbourhood of the Lucas Heights Research Laboratories during 1983. These results are satisfactory. No radioactivity which could have originated from these laboratories was found in samples collected from possible human food chains. All low-level liquid and gaseous waste discharges were within authorised limits. The maximum possible annual dose to the general public from airborne waste discharges during this period is estimated to be less than 0.01 millisieverts, which is 1 per cent of the limit for long-term exposure that is recommended by the National Health and Medical Research Council

  19. The new recommendations of the ICRP

    International Nuclear Information System (INIS)

    Sugier, A.; Metivier, H.

    1991-01-01

    One of the outstanding events that recently occurred in the field of radioprotection is the revision of the recommendations of the International Commission on Radiological Protection. In fact, the latest studies on the survivors from Hiroshima and Nagasaki have led the experts to revise downwards the individual dose limits. What are the new elements in this document

  20. Quality and Dose Optimized CT Trauma Protocol - Recommendation from a University Level-I Trauma Center.

    Science.gov (United States)

    Kahn, Johannes; Kaul, David; Böning, Georg; Rotzinger, Roman; Freyhardt, Patrick; Schwabe, Philipp; Maurer, Martin H; Renz, Diane Miriam; Streitparth, Florian

    2017-09-01

    Purpose  As a supra-regional level-I trauma center, we evaluated computed tomography (CT) acquisitions of polytraumatized patients for quality and dose optimization purposes. Adapted statistical iterative reconstruction [(AS)IR] levels, tube voltage reduction as well as a split-bolus contrast agent (CA) protocol were applied. Materials and Methods  61 patients were split into 3 different groups that differed with respect to tube voltage (120 - 140 kVp) and level of applied ASIR reconstruction (ASIR 20 - 50 %). The CT protocol included a native acquisition of the head followed by a single contrast-enhanced acquisition of the whole body (64-MSCT). CA (350 mg/ml iodine) was administered as a split bolus injection of 100 ml (2 ml/s), 20 ml NaCl (1 ml/s), 60 ml (4 ml/s), 40 ml NaCl (4 ml/s) with a scan delay of 85 s to detect injuries of both the arterial system and parenchymal organs in a single acquisition. Both the quantitative (SNR/CNR) and qualitative (5-point Likert scale) image quality was evaluated in parenchymal organs that are often injured in trauma patients. Radiation exposure was assessed. Results  The use of IR combined with a reduction of tube voltage resulted in good qualitative and quantitative image quality and a significant reduction in radiation exposure of more than 40 % (DLP 1087 vs. 647 mGyxcm). Image quality could be improved due to a dedicated protocol that included different levels of IR adapted to different slice thicknesses, kernels and the examined area for the evaluation of head, lung, body and bone injury patterns. In synopsis of our results, we recommend the implementation of a polytrauma protocol with a tube voltage of 120 kVp and the following IR levels: cCT 5mm: ASIR 20; cCT 0.625 mm: ASIR 40; lung 2.5 mm: ASIR 30, body 5 mm: ASIR 40; body 1.25 mm: ASIR 50; body 0.625 mm: ASIR 0. Conclusion  A dedicated adaptation of the CT trauma protocol (level of reduction of tube voltage and of IR

  1. Statement and recommendations of the International Commission on Radiological Protection from its 1980 meeting

    International Nuclear Information System (INIS)

    1980-01-01

    A short report of the 1980 annual meeting of the ICRP is given along with the recommendations proposed. These are as follows: 1) for the lens of the eye, the annual dose-equivalent limit should be reduced from 0.3Sv to 0.15 Sv, 2) the recommended annual limit for intake by inhalation for radon-222 daughters is 0.02 J and corresponds to an air concentration of 0.4 working levels in previous practical units, 3) the recent information on estimate of radiation risk does not call for changes in the risk factors for stochastic effects or the dose-effect relationships for non-stochastic effects underlying the dose-equivalent limits recommended in ICRP publication 26. The assessment of the total detriment by summation using weighting factors for different organs is also discussed. (U.K.)

  2. AGING FACILITY WORKER DOSE ASSESSMENT

    International Nuclear Information System (INIS)

    R.L. Thacker

    2005-01-01

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

  3. Radiation doses to Finns

    International Nuclear Information System (INIS)

    Rantalainen, L.

    1996-01-01

    The estimated annual radiation doses to Finns have been reduced in the recent years without any change in the actual radiation environment. This is because the radiation types have been changed. The risk factors will probably be changed again in the future, because recent studies show discrepancies in the neutron dosimetry concerning the city of Hiroshima. Neutron dosimetry discrepancy has been found between the predicted and estimated neutron radiation. The prediction of neutron radiation is calculated by Monte Carlo simulations, which have also been used when designing recommendations for the limits of radiation doses (ICRP60). Estimation of the neutron radiation is made on the basis of measured neutron activation of materials in the city. The estimated neutron dose beyond 1 km is two to ten, or more, times as high as the predicted dose. This discrepancy is important, because the most relevant distances with respect to radiation risk evaluation are between 1 and 2 km. Because of this discrepancy, the present radiation risk factors for gamma and neutron radiation, which rely on the Monte Carlo calculations, are false, too. The recommendations of ICRP60 have been adopted in a few countries, including Finland, and they affect the planned common limits of the EU. It is questionable whether happiness is increased by adopting false limits, even if they are common. (orig.) (2 figs., 1 tab.)

  4. Industry disagrees with water quality recommendations

    International Nuclear Information System (INIS)

    Begley, R.

    1992-01-01

    Industry groups are distancing themselves from recommendations on cleaning up the nation's waters issued by Water Quality 2000, a coalition of more than 80 organizations representing industry, environmental groups, government, academia, and professional and scientific societies. The report, open-quotes A National Water Agenda for the 21st Centuryclose quotes, is a result of work begun in 1989. It recommends an approach to water quality that emphasizes pollution prevention, increased individual and collective responsibility for protecting water resources, and reorienting water resource programs and institutions along natural, rather than political, watershed boundaries. It includes 85 specific recommendations, many of which are to be implemented locally. The Natural Resources Defense Council (NRDC; Washington) open-quotes wholeheartedly endorses not only the specific solutions offered today but the process by which these proposals were reached,close quotes says Robert W. Adler, NRDC senior attorney and vice chairman of Water Quality 2000. John B. Coleman, corporate environmental affairs manager for Du Pont and a member of the groups's steering committee, says open-quotes Du Pont and the other industry members of Water Quality 2000 are committedclose quotes to working to make continuous improvements

  5. Viewpoint Reading Conference Recommendations in a Wider ...

    African Journals Online (AJOL)

    Viewpoint Reading Conference Recommendations in a Wider Context of Social Change. ... Southern African Journal of Environmental Education. Journal Home · ABOUT THIS JOURNAL ... AJOL African Journals Online. HOW TO USE AJOL.

  6. Travelers' Health: Vaccine Recommendations for Infants and Children

    Science.gov (United States)

    ... should be taken ≥1 week before potential exposure. YELLOW FEVER VACCINE Yellow fever, a disease transmitted by mosquitoes, is endemic ... a new recommendation that a single dose of yellow fever vaccine provides long-lasting protection and is adequate for ...

  7. American National Standard: neutron and gamma-ray flux-to-dose rate factors

    International Nuclear Information System (INIS)

    Anon.

    1977-01-01

    This Standard presents data recommended for computing biological dose rates due to neutron and gamma-ray radiation fields. Neutron flux-to-dose-rate conversion factors for energies from 2.5 x 10 -8 to 20 MeV are given; the energy range for the gamma-ray conversion factors is 0.01 to 15 MeV. Specifically, this Standard is intended for use by shield designers to calculate wholebody dose rates to radiation workers and the general public. Establishing dose-rate limits is outside the scope of this Standard. Use of this Standard in cases where the dose equivalents are far in excess of occupational exposure guidelines is not recommended

  8. A methodology for practical implementation of ICRP recommendations for optimization

    International Nuclear Information System (INIS)

    Webb, G.A.M.; Clarke, R.H.

    1979-01-01

    The system of dose limitation recommended by the Commission has been restated in its most recent recommendations with the requirements implying cost benefit analysis elevated to pride of place. The main subject of this paper is discussion of the problems involved in carrying out differential cost benefit analysis (optimization) studies. The various quantities such as Effective Dose Equivalent and Collective Effective Dose Equivalent Commitment needed to carry out these studies are discussed, their strengths and weaknesses identified and suggestions made as to how they should be used in practice. In particular the implications underlying the use of the collective quantities as the independent variable in these studies are clarified and examined. The need for the maximum realism in calculational models and parameters used in the calculation of collective quantities for optimization studies is stressed, with the corollary of conservative calculations for comparison with dose limits. The methods for calculating costs are examined, both for the plant or equipment installed to reduce doses and for the cost associated with the consequent reduction in health detriment. Some practical problems are cited in both the theory and practice of optimization. It is concluded that optimization is not yet sufficiently developed in either basic formalism or practical application. Some areas are identified where further work is needed. (author)

  9. The history of critical group doses from the consumption of freshwater fish at Trawsfynydd, North Wales

    International Nuclear Information System (INIS)

    Leonard, D.R.P.

    1992-01-01

    Radionuclides discharged into the aquatic environment from Trawsfynydd power station are, as for all UK facilities, subject to statutory controls to ensure that the resulting public radiation exposure complies with nationally-accepted criteria. Environmental monitoring by MAFF has shown that near this facility the consumption of freshwater fish is radiologically the most important pathway with Cs-137 the dominant radionuclide. Information gathered from consumers over a twenty-five year period has been interpreted so as to derive doses to the public. Committed effective doses (CEDs) are presented using ICRP 1990 methodology and compared with the recommended dose limit of 1 mSv year -1 . Doses to the critical group are shown to have exceeded 1 mSv year -1 for two years but do not exceed this limit when averaged over a period of 5 years. Because of the changing habits of the consumers it is suggested that the average annual CED over the lifetime of any member of the public will not exceed 1 mSv year -1 during the operation of the station. (author)

  10. Environmental dosimetry system based on LiF : Mg, Ti (TLD-100)

    International Nuclear Information System (INIS)

    Saez Vergara, J.C.

    1990-01-01

    The report presents the various tests carried out to the characterize a thermoluminescence environmental dosimetry systems, using the phosphor LiF:mg,Ti (TLD-100) in chip form. The holder has been specifically designed in order to obtain simplicity in the operation and to assure correct measurements in terms of the new operational quantities in radiation protection (ICRU-1985). Some topics in TLD Environmental Monitoring are discussed (Dark Current, Reference Light, Zero Reading, Free-in-Air or Phantom Calibration, Fading Correction, Transit Dose, etc.), and the proposed solutions are exposed. The tests performed have been designed to conform with the different existing international Standards and Recommendations (ANSI : N545-1975; IEC: Draft 45B-1987, ISO : DP 8034-19849. The data from an European Interlaboratory Programm (EUR-8932) have been used to evaluate the performance : the TLD System presented is among the best systems using TLD-100. The results obtained in the characterization (linearity, repeatability, detection threshold, residue, angular response, stability of stored information, etc.) show the optimum performance of this dosimetric system in its application to environmental gamma dose monitoring. Based on these results, two operational procedures have been developed for the application of this Dosimetric System, specially in Quality Assurance Monitoring Programs around Nuclear Plants in Spain. (author)

  11. Performance of a GM tube based environmental dose rate monitor operating in the Time-To-Count mode

    Energy Technology Data Exchange (ETDEWEB)

    Zickefoose, J.; Kulkarni, T.; Martinson, T.; Phillips, K.; Voelker, M. [Canberra Industries Inc. (United States)

    2015-07-01

    The events at the Fukushima Daiichi power plant in the aftermath of a natural disaster underline the importance of a large array of networked environmental monitors to cover areas around nuclear power plants. These monitors should meet a few basic criteria: have a uniform response over a wide range of gamma energies, have a uniform response over a wide range of incident angles, and have a large dynamic range. Many of these criteria are met if the probe is qualified to the international standard IEC 60532 (Radiation protection instrumentation - Installed dose rate meters, warning assemblies and monitors - X and gamma radiation of energy between 50 keV and 7 MeV), which specifically deals with energy response, angle of incidence, dynamic range, response time, and a number of environmental characteristics. EcoGamma is a dual GM tube environmental gamma radiation monitor designed specifically to meet the requirements of IEC 60532 and operate in the most extreme conditions. EcoGamma utilizes two energy compensated GM tubes operating with a Time-To-Count (TTC) collection algorithm. The TTC algorithm extends the lifetime and range of a GM tube significantly and allows the dual GM tube probe to achieve linearity over approximately 10 decades of gamma dose rate (from the Sv/hr range to 100 Sv/hr). In the TTC mode of operation, the GM tube is not maintained in a biased condition continuously. This is different from a traditional counting system where the GM tube is held at a constant bias continuously and the total number of strikes that the tube registers are counted. The traditional approach allows for good sensitivity, but does not lend itself to a long lifetime of the tube and is susceptible to linearity issues at high count rates. TTC on the other hand only biases the tube for short periods of time and in effect measures the time between events, which is statistically representative of the total strike rate. Since the tube is not continually biased, the life of the tube

  12. Performance of a GM tube based environmental dose rate monitor operating in the Time-To-Count mode

    International Nuclear Information System (INIS)

    Zickefoose, J.; Kulkarni, T.; Martinson, T.; Phillips, K.; Voelker, M.

    2015-01-01

    The events at the Fukushima Daiichi power plant in the aftermath of a natural disaster underline the importance of a large array of networked environmental monitors to cover areas around nuclear power plants. These monitors should meet a few basic criteria: have a uniform response over a wide range of gamma energies, have a uniform response over a wide range of incident angles, and have a large dynamic range. Many of these criteria are met if the probe is qualified to the international standard IEC 60532 (Radiation protection instrumentation - Installed dose rate meters, warning assemblies and monitors - X and gamma radiation of energy between 50 keV and 7 MeV), which specifically deals with energy response, angle of incidence, dynamic range, response time, and a number of environmental characteristics. EcoGamma is a dual GM tube environmental gamma radiation monitor designed specifically to meet the requirements of IEC 60532 and operate in the most extreme conditions. EcoGamma utilizes two energy compensated GM tubes operating with a Time-To-Count (TTC) collection algorithm. The TTC algorithm extends the lifetime and range of a GM tube significantly and allows the dual GM tube probe to achieve linearity over approximately 10 decades of gamma dose rate (from the Sv/hr range to 100 Sv/hr). In the TTC mode of operation, the GM tube is not maintained in a biased condition continuously. This is different from a traditional counting system where the GM tube is held at a constant bias continuously and the total number of strikes that the tube registers are counted. The traditional approach allows for good sensitivity, but does not lend itself to a long lifetime of the tube and is susceptible to linearity issues at high count rates. TTC on the other hand only biases the tube for short periods of time and in effect measures the time between events, which is statistically representative of the total strike rate. Since the tube is not continually biased, the life of the tube

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

    International Nuclear Information System (INIS)

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

    2013-02-01

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

  14. Doses from radiation exposure

    CERN Document Server

    Menzel, H G

    2012-01-01

    Practical implementation of the International Commission on Radiological Protection's (ICRP) system of protection requires the availability of appropriate methods and data. The work of Committee 2 is concerned with the development of reference data and methods for the assessment of internal and external radiation exposure of workers and members of the public. This involves the development of reference biokinetic and dosimetric models, reference anatomical models of the human body, and reference anatomical and physiological data. Following ICRP's 2007 Recommendations, Committee 2 has focused on the provision of new reference dose coefficients for external and internal exposure. As well as specifying changes to the radiation and tissue weighting factors used in the calculation of protection quantities, the 2007 Recommendations introduced the use of reference anatomical phantoms based on medical imaging data, requiring explicit sex averaging of male and female organ-equivalent doses in the calculation of effecti...

  15. The implementation of the 1990 recommendations of the ICRP in Korea

    International Nuclear Information System (INIS)

    Yong-Kyu Lim

    1993-01-01

    Over the last three years, the new Recommendations of the International Commission on Radiological Protection (ICRP-60) brought some controversies in radiation protection field. In the course of preparation for implementation of the new Recommendations in Korea, some main issues were critically reviewed including the reduction of dose limits for occupational exposures, the introduction of the concept of dose constraints for proposed practices, and the description of radiological protection system using the concept of practice and intervention. Not only scientific meaning of dose limits but also socio-political impact in different countries must be considered for implementation to the regulatory system. How-to-communicate with the general public on the radiation risk would be more difficult task for specialists than how-to-meet the lower limits. A considerable amount of costs and resources will be required for implementing the new Recommendations. The most dominant portion of the resources would be needed in the education program including the training of personnel in radiation protection field. Education of the general public on the underlying concept of the new system of radiological protection is also important to prevent any unfavorable disturbance on the public acceptance

  16. The environmental chemical tributyltin chloride (TBT) shows both estrogenic and adipogenic activities in mice which might depend on the exposure dose

    International Nuclear Information System (INIS)

    Penza, M.; Jeremic, M.; Marrazzo, E.; Maggi, A.; Ciana, P.; Rando, G.; Grigolato, P.G.; Di Lorenzo, D.

    2011-01-01

    Exposure during early development to chemicals with hormonal action may be associated with weight gain during adulthood because of altered body homeostasis. It is known that organotins affect adipose mass when exposure occurs during fetal development, although no knowledge of effects are available for exposures after birth. Here we show that the environmental organotin tributyltin chloride (TBT) exerts adipogenic action when peripubertal and sexually mature mice are exposed to the chemical. The duration and extent of these effects depend on the sex and on the dose of the compound, and the effects are relevant at doses close to the estimated human intake (0.5 μg/kg). At higher doses (50-500 μg/kg), TBT also activated estrogen receptors (ERs) in adipose cells in vitro and in vivo, based on results from acute and longitudinal studies in ERE/luciferase reporter mice. In 3T3-L1 cells (which have no ERs), transiently transfected with the ERE-dependent reporter plus or minus ERα or ERβ, TBT (in a dose range of 1-100 nM) directly targets each ER subtype in a receptor-specific manner through a direct mechanism mediated by ERα in undifferentiated preadipocytic cells and by ERβ in differentiating adipocytes. The ER antagonist ICI-182,780 inhibits this effect. In summary, the results of this work suggest that TBT is adipogenic at all ages and in both sexes and that it might be an ER activator in fat cells. These findings might help to resolve the apparent paradox of an adipogenic chemical being also an estrogen receptor activator by showing that the two apparently opposite actions are separated by the different doses to which the organism is exposed. - Research highlights: → The environmental organotin tributyltin chloride shows dose-dependent estrogenic and adipogenic activities in mice. → The duration and extent of these effects depend on the sex and the dose of the compound. → The estrogenic and adipogenic effects of TBT occur at doses closed to the estimated

  17. The embryogenesis of dose assessment at Hanford

    International Nuclear Information System (INIS)

    Foster, R.F.

    1990-01-01

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

  18. Optimization of foramsulfuron doses for post-emergence weed control in maize (Zea mays L.)

    Energy Technology Data Exchange (ETDEWEB)

    Pannacci, E.

    2016-11-01

    Four field experiments were carried out from 2011 to 2014 in order to evaluate the effects of foramsulfuron, applied at the recommended (60.8 g a.i./ha) and reduced doses (1/3 and 2/3), on the efficacy against several of the most important weeds in maize. For each “year-weed” combination, dose-response curves were applied to estimate the dose of foramsulfuron required to obtain 90% and 95% weed control (ED90 and ED95). Foramsulfuron phytotoxicity on maize and crop yield were assessed. Foramsulfuron at 1/3 of the recommended dose (20.3 g a.i./ha) provided 95% efficacy against redroot pigweed (Amaranthus retroflexus L.), green foxtail (Setaria viridis (L.) Beauv.), wild mustard (Sinapis arvensis L.) and black nightshade (Solanum nigrum L.). Velvetleaf (Abutilon theophrasti Medik.), common lambsquarters (Chenopodium album L.) and barnyardgrass (Echinochloa crus-galli (L.) Beauv.) were satisfactorily controlled (95% weed efficacy) with ED95 ranged from 20 to 50 g/ha of foramsulfuron (about from 1/3 to 5/6 of the recommended dose) depending on growth stage. The recommended dose was effective against pale smartweed (Polygonum lapathifolium L.) at 2-4 true leaves (12-14 BBCH scale), but this dose did not kill plants larger than 2-4 true leaves. The ranking among weed species based on their susceptibility to foramsulfuron was: redroot pigweed = green foxtail = wild mustard = black nightshade > velvetleaf = common lambsquarters = barnyardgrass > pale smartweed. Dose of foramsulfuron can be reduced below recommended dose depending on weed species and growth stage. Foramsulfuron showed a good crop selectivity and had no negative effect on maize yield. (Author)

  19. Terrestrial gamma radiation dose study to determine the baseline for environmental radiological health practices in Melaka state, Malaysia

    International Nuclear Information System (INIS)

    Ramli, Ahmad Termizi; Sahrone, Sallehudin; Wagiran, Husin

    2005-01-01

    Environmental terrestrial gamma radiation dose rates were measured throughout Melaka, Malaysia, over a period of two years, with the objective of establishing baseline data on the background radiation level. Results obtained are shown in tabular, graphic and cartographic form. The values of terrestrial gamma radiation dose rate vary significantly over different soil types and for different underlying geological characteristics present in the study area. The values ranged from 54 ± 5 to 378 ± 38 nGy h -1 . The highest terrestrial gamma dose rates were measured over soil types of granitic origin and in areas with underlying geological characteristics of an acid intrusive (undifferentiated) type. An isodose map of terrestrial gamma dose rate in Melaka was drawn by using the GIS application 'Arc View'. This was based on data collected using a NaI(Tl) scintillation detector survey meter. The measurements were taken at 542 locations. Three small 'hot spots' were found where the dose rates were more than 350 nGy h -1 . The mean dose rates in the main population areas in the mukims (parishes) of Bukit Katil, Sungai Udang, Batu Berendam, Bukit Baru and Bandar Melaka were 154 ± 15, 161 ± 16, 160 ± 16, 175 ± 18 and 176 ± 18 nGy h -1 , respectively. The population-weighted mean dose rate throughout Melaka state is 172 ± 17 nGy h -1 . This is lower than the geographical mean dose rate of 183 ± 54 nGy h -1 . The lower value arises from the fact that most of the population lives in the central area of the state where the lithology is dominated by sedimentary rocks consisting of shale, mudstone, phyllite, slate, hornfels, sandstone and schist of Devonian origin which have lower associated dose rates. The mean annual effective dose to the population from outdoor terrestrial gamma radiation was estimated to be 0.21 mSv. This value is higher than the world average of 0.07 mSv

  20. Organ doses from computerized tomography examinations

    Energy Technology Data Exchange (ETDEWEB)

    Janeczek, J.

    1995-12-31

    Estimates of mean organs doses from five typical computerized tomography (CT) examinations were obtained. Measurements were done using Rando-Alderson anthropomorphic phantom and thermoluminescent dosemeters (TLD). Radiation dose distributions within a phantom has been measured for each examination and results were used for organ dose calculation. Doses to organs specified by ICPR 60 Recommendations were measured for five CT scanners (CT/T8800, CT 9800, CT MAX - made by General Electric; CT 1200 SX - made by Picker; SOMATOM 2 - made by Siemens). Dose distributions from scattered radiation were measured and indicate that scattered radiation dose to thyroid and eye lens can be reduced by proper examination limits setting. The lowest mean organ doses were obtained from CT/T8800 scanner. More advanced scanners using high intensity continuous radiation were giving higher organ doses. (author). 23 refs, 6 figs, 13 tabs.

  1. Organ doses from computerized tomography examinations

    International Nuclear Information System (INIS)

    Janeczek, J.

    1995-01-01

    Estimates of mean organs doses from five typical computerized tomography (CT) examinations were obtained. Measurements were done using Rando-Alderson anthropomorphic phantom and thermoluminescent dosemeters (TLD). Radiation dose distributions within a phantom has been measured for each examination and results were used for organ dose calculation. Doses to organs specified by ICPR 60 Recommendations were measured for five CT scanners (CT/T8800, CT 9800, CT MAX - made by General Electric; CT 1200 SX - made by Picker; SOMATOM 2 - made by Siemens). Dose distributions from scattered radiation were measured and indicate that scattered radiation dose to thyroid and eye lens can be reduced by proper examination limits setting. The lowest mean organ doses were obtained from CT/T8800 scanner. More advanced scanners using high intensity continuous radiation were giving higher organ doses. (author). 23 refs, 6 figs, 13 tabs

  2. Dose conversion coefficients for high-energy photons, electrons, neutrons and protons

    CERN Document Server

    Sakamoto, Y; Sato, O; Tanaka, S I; Tsuda, S; Yamaguchi, Y; Yoshizawa, N

    2003-01-01

    In the International Commission on Radiological Protection (ICRP) 1990 Recommendations, radiation weighting factors were introduced in the place of quality factors, the tissue weighting factors were revised, and effective doses and equivalent doses of each tissues and organs were defined as the protection quantities. Dose conversion coefficients for photons, electrons and neutrons based on new ICRP recommendations were cited in the ICRP Publication 74, but the energy ranges of theses data were limited and there are no data for high energy radiations produced in accelerator facilities. For the purpose of designing the high intensity proton accelerator facilities at JAERI, the dose evaluation code system of high energy radiations based on the HERMES code was developed and the dose conversion coefficients of effective dose were evaluated for photons, neutrons and protons up to 10 GeV, and electrons up to 100 GeV. The dose conversion coefficients of effective dose equivalent were also evaluated using quality fact...

  3. Self-dose and fading of CaSO4(Dy/Tm) and CaF2 (natural) TL phosphors in environmental radiation monitoring

    International Nuclear Information System (INIS)

    Nambi, K.S.V.

    1982-01-01

    A 'shielded storage experiment' for estimating both the 'self-dose' and 'fading' of TL phosphors under conditions akin to those faced in environmental monitoring applications is described. Using this method, self-dose rates of 0.32 +- 0.10(sigma) μ rad h -1 and 1.16 +- 0.02(sigma) μ rad h -1 have been obtained for CaF 2 (natural) and CaSO 4 (Dy) phosphors; the thermal decay constants at 25 0 C for these phosphors turn out to be 27 X 10 -6 h -6 ad 12 X 10 -6 h -1 , respectively. Estimation of the self-doses from radioactivity measurements of the phosphors concerned is also presented and the differences explained. A very high self-dose rate of 5.6 μ rad h -1 was estimated by the latter method for a sample of CaSO 4 (Tm) phosphor. (orig.)

  4. Continuous-release formulation for environmental doses to moving receptors

    International Nuclear Information System (INIS)

    Piepho, M.G.

    1981-01-01

    Atmospheric dispersion models frequently assume a puff release or several puff releases, each of which are described separately. A dispersion model should better describe a continuous release as more puffs are assumed, but the computational cost and bookkeeping difficulty increases with additional puffs. A new formulism is derived in this work which replaces the puff approximation. With the new continuous release formulation, radioactive dose calculations to moving receptors are more accurately calculated without any great additional computation. There are several advantages of a continuous release formulation. With this formulation, a dose rate to a moving receptor is calculated as a function of time. The dose-rate will increase (decrease) as the bulk of the release gets closer (farther) to (from) the receptor which is at position x(t), y(t). The receptor may follow any x, y trajectory as a function of time, and the dose rate will be calculated along the path

  5. Monitoring program design recommendations for uranium mining communities

    International Nuclear Information System (INIS)

    1978-10-01

    Environmental radiological monitoring requirements and their rationale have been developed for operating uranium mine/mill sites including the pre-operational phase, and for non-operating tailings areas, in order to assess the radiological impact on the environment and follow long-term trends. These recommendations have been based on a review of regulatory standards, sources and nature of releases from mines, mills and tailings, and environmental pathway analysis. Media and measurements considered in the routine on-going programs include airborne radon, airborne particulates, external radiation, terrestrial biota, surface water, drinking water, ground water, fish and sediment. Program implementation guides are provided. An overview of sampling and field technique and specific recommendations have been made. (auth)

  6. Implications of the 1990 ICRP recommendations for the mining industry

    International Nuclear Information System (INIS)

    Fry, R.M.

    1992-01-01

    Significant radiological protection problems arise in the mining and processing of uranium and thorium bearing ores, beach sands and other materials that have enhanced levels of uranium (e.g. phosphate). They are at their most extreme in the underground mining of uranium. Under the new ICRP 60 occupational dose limits it may be necessary to subject virtually all mining operations to some degree of radiological surveillance. There are three principal modes of radiation exposure in uranium mining operations: gamma rays, an external whole body radiation hazard; the inhalation of radon daughter products; and the inhalation of ore dust containing the long-lived alpha emitting daughter products of uranium, principally 230Th and 226Ra. A number of the new recommendations in ICRP60 considered to have significant implications for the mining industry in general and the above mentioned issues in particular are discussed. These include the definition of occupational exposure occupational dose limit, the review of the radon dose limits, the system of radiological protection. The major conclusions and recommendation of the IAEA Technical Committee to Explore the Impact of the new ICRP Occupational Dose Limits in the operation of underground mines are also summarized. 18 refs., 1 tab

  7. Environmental remediation activities at WISMUT GmbH, Germany

    International Nuclear Information System (INIS)

    Saito, Hiroshi; Takahashi, Kuniaki; Miyasaka, Yasuhiko; Yamana, Hajimu

    2007-01-01

    The WISMUT GmbH has carried out environmental remediation activities since 1991 in former GDR (German Democratic Republic) to rehabilitate the environment and landscape which have been adversely affected by decades of unrestrained mining and processing of uranium ores. It is worthy of being mentioned especially that WISMUT GmbH's sites including waste rock dump, mill tailings pond, open pit mine and water treatment facilities with an area of 3,700ha have been rehabilitated practically and extensively, and these activities are planned to terminate in 2015 except for the water treatment. For safety assessment after remediation, the value of 1mSv/y (in excess of the background level) is applied to as an individual effective dose, from the recommendation of ICRP (International Commission on Radiological Protection). This report shows a summary of environmental remediation activities carried out by the WISMUT GmbH and related regulatory laws. (author)

  8. Final environmental impact statement. Waste Isolation Pilot Plant

    Energy Technology Data Exchange (ETDEWEB)

    1980-10-01

    This volume contains the appendices for the Final Environmental Impact Statement for the Waste Isolation Pilot Plant (WIPP). Alternative geologic environs are considered. Salt, crystalline rock, argillaceous rock, and tuff are discussed. Studies on alternate geologic regions for the siting of WIPP are reviewed. President Carter's message to Congress on the management of radioactive wastes and the findings and recommendations of the interagency review group on nuclear waste management are included. Selection criteria for the WIPP site including geologic, hydrologic, tectonic, physicochemical compatability, and socio-economic factors are presented. A description of the waste types and the waste processing procedures are given. Methods used to calculate radiation doses from radionuclide releases during operation are presented. A complete description of the Los Medanos site, including archaeological and historic aspects is included. Environmental monitoring programs and long-term safety analysis program are described. (DMC)

  9. Poker-camp: a program for calculating detector responses and phantom organ doses in environmental gamma fields

    International Nuclear Information System (INIS)

    Koblinger, L.

    1981-09-01

    A general description, user's manual and a sample problem are given in this report on the POKER-CAMP adjoint Monte Carlo photon transport program. Gamma fields of different environmental sources which are uniformly or exponentially distributed sources or plane sources in the air, in the soil or in an intermediate layer placed between them are simulated in the code. Calculations can be made on flux, kerma and spectra of photons at any point; and on responses of point-like, cylindrical, or spherical detectors; and on doses absorbed in anthropomorphic phantoms. (author)

  10. Recommendations concerning classification of and discharge standards for radionuclide laboratories

    International Nuclear Information System (INIS)

    1985-01-01

    In the report recommendations are made for the limitation of the radioactive gaseous and liquid effluents from radionuclide laboratories. The recommended values are based on a radiation exposure for members of a critical group in the population corresponding to 1% of the dose limit for individual members of the public as recommended by the ICRP. Based on these standards a classification of radionuclide laboratories is proposed. It is recommended to retain the present Dutch classification in A-, B-, C- and D-laboratories. The report contains appendices with detailed data about the transport routes of radionuclides in the environment and the subsequent irradiation of members of the public. (orig.)

  11. Environmentally important radionuclides in nonproliferative fuel cycles

    International Nuclear Information System (INIS)

    Kaye, S.V.; Till, J.E.

    1978-01-01

    Our analyses indicate that more in-depth research should be done on 3 H, 14 C, 99 Tc, and 232 U, especially because of their presence in nonproliferative fuel cycles. For increased 3 H production by fast reactors, we can only speculate that such research could show that environmental releases might be significantly greater than for LWRs. Carbon-14 will likely not be a problem if a suitable decontamination factor can be agreed upon for reprocessing facilities and if a satisfactory regulatory limit can be established for global populations. Additional experimental research is urgently needed to determine the uptake of low levels of 99 Tc by plants. These data are essential before an accurate assessment of 99 Tc releases can be made. Finally, we recommend that investigators take a closer look at the potential problems associated with 232 U and daughters. This radionuclide could contribute a significant portion of the dose in both environmental and occupational exposures from the nonproliferative fuels

  12. Education in Environmental Chemistry: Setting the Agenda and Recommending Action

    Science.gov (United States)

    Zoller, Uri

    2005-01-01

    The effective utilization of Education in Environmental Chemistry (EEC) in addressing global and societal environmental problems requires integration between educational, technical, financial, ethical and societal considerations. An interdisciplinary approach is fundamental to efforts to achieve long-term solutions.

  13. [Recommendations for the use of methotrexate in patients with juvenile idiopathic arthritis].

    Science.gov (United States)

    Calvo, I; Antón, J; López Robledillo, J C; de Inocencio, J; Gamir, M L; Merino, R; Lacruz, L; Camacho, M; Rua, M J; Bustabad, S; Díaz Cordovés-Rego, G

    2016-03-01

    To develop a consensus document of recommendations for the use of methotrexate (MTX) in patients with juvenile idiopathic arthritis (JIA). A group of eleven experts proposed several clinical questions on the use of MTX in patients with JIA. A systematic review was conducted and the evidence and recommendations for each question were extracted. The results were discussed and validated by the experts in a work session to establish the final recommendations. MTX is recommended as the first drug for inducing remission in JIA, and its indication should be made according to the clinical category of the patient. Prior to treatment, it is recommended to perform a complete blood count, including white cells, levels of liver enzymes, serum creatinine, and other analytical parameters according to specific risk factors. Treatment should be initiated with a dose of 10-15 mg/m(2)/week. In cases of uveitis or polyarthritis, an initial dose of 15 mg/m(2)/week should be considered. For a better bioavailability and tolerability, it is preferable to administer MTX parenterally if the dose is ≥15 mg/m(2)/week. It is necessary to periodically perform an analytical monitoring of the patient and to assess possible alterations in liver enzymes to make changes if necessary. Combinations with biological agents may be necessary, as well as the concomitant addition of folic or folinic acid. This document describes the main recommendations for the appropriate use of MTX in JIA patients, according to scientific evidence and clinical experience. Copyright © 2015 Asociación Española de Pediatría. Published by Elsevier España, S.L.U. All rights reserved.

  14. 40 CFR 246.201-6 - Recommended procedures: Transportation to market.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 24 2010-07-01 2010-07-01 false Recommended procedures: Transportation to market. 246.201-6 Section 246.201-6 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY... Procedures § 246.201-6 Recommended procedures: Transportation to market. Transportation to market may be...

  15. Receptor dose and patient dose in radiographic exposures: a 15 year review

    International Nuclear Information System (INIS)

    Peet, D.J.; Tyler, N.; Pryor, M.; Hollaway, P.; Strudley, C.; Leavesley, L.

    2008-01-01

    A patient dose programme has been established locally for the last 15 years across 109 hospitals and 250 X-ray rooms in line with the National Protocol, in conjunction with a programme to look at routine performance of these rooms. Routine performance checks initially looked primarily at film density and AEC performance but with the introduction of Computerised Radiography (CR) across UK hospitals and a revision of recommended procedures in the UK, the emphasis has shifted to assessing receptor dose under AEC control. Results show a wide variation in film density in the early years indicating sub optimal performance and dose. The spread was reduced over later years. The introduction of CR has led to a variety of approaches by the CR companies, X-ray companies and local sites. Receptor doses vary widely as a result. Large variations within hospitals were also observed. The doses over the last 15 years are reviewed and compared against diagnostic reference levels and with the performance of the imaging chain. Results show that patient dose programmes and optimisation strategies were having an impact, but the introduction of CR requires renewed efforts to ensure images and doses are optimised. (author)

  16. Analysis of occupational doses in radioactive and nuclear facilities

    International Nuclear Information System (INIS)

    Curti, A.; Gomez P, I.; Pardo, G.; Thomasz, E.

    1996-01-01

    Occupational doses were analyzed in the most important nuclear and radioactive facilities in Argentina, on the period 1988-1994. The areas associated with uranium mining and milling, and medical uses of radiation facilities were excluded from this analysis. The ICRP publication 60 recommendations, adopted in 1990, and enforced in Argentine in 1994, keep the basic criteria of dose limitation system and recommend a substantial reduction in the dose limits. The reduction of the dose limits will affect the individual dose distributions, principally in those installations with occupational doses close to 50 mSv. It were analyzed Occupational doses, principally in the following facilities: Atucha-I and Embalse Nuclear Power Plants, radioisotope production plants, research reactors and radioactive waste management plants. The highest doses were identified in each facility, as well as the task associated with them. Trends in the individual dose distribution and collective and average doses were analyzed. It is concluded, that no relevant difficulties should appear in accomplishing with the basic standards for radiological safety, except for the Atucha-I Nuclear Power Plant. In this NPP a significant effort for the optimization of radiological safety procedures in order to diminish the occupational doses, and a change of the fuel channels by new ones free of cobalt are being carried out. (authors). 4 refs., 3 figs., 3 tabs

  17. Controllable dose: the ICRP discussion paper does not go far enough

    International Nuclear Information System (INIS)

    Carter, M.W.

    2000-01-01

    The current ICRP recommendations and the associated dosimetry have confused the public, lawyers and politicians and have been the subject of dissension within the Health Physics Community. Currently recommended limits are different for occupational exposure, exposure of the public, exposure to radon in dwellings and exposure to radon in workplaces. Current recommendations do not cover exposure in accident situations. The recommended limits do not apply to natural background radiation exposures. This suggests that the unit of radiation dose is variable depending on the circumstances and that artificially produced radiation is more harmful than natural radiation. The use of collective dose and the LNT model has resulted, in the opinion of some, in waste of money spent in trying to reduce doses that may be already too small to produce detectable harm. The recent discussion papers (Clarke, 1998, Clarke 1999), introducing the concept of controllable dose, are a valuable starting point for changing and improving the basis on which regulations are made. It is the author's opinion that the discussion paper does not go far enough and that the confusion is largely the result of failing to separate the scientific aspects from the regulatory aspects of controlling radiation dose. Only by making such a separation can we provide understandable regulations without compromising scientific research into radiation risks. Copyright (2000) Australasian Radiation Protection Society Inc

  18. Outdoor γ-ray dose rate in Shariki Village and environmental factors affecting outdoor γ-ray dose rate in IES

    International Nuclear Information System (INIS)

    Iyogi, Takashi; Hisamatsu, Shun'ichi; Inaba, Jiro

    2000-01-01

    Previously, we surveyed the outdoor γ-ray dose rate throughout Aomori Prefecture from 1992 to 1995, and found an annual mean dose rate of 51 nGy h -1 . Relatively high dose rates were also observed in several areas (municipalities) of the survey locations. In this study, we examined the detailed distribution of the γ-ray dose rate in one such high dose rate area, Shariki Village. Glass dosemeters were used for the monitoring of cumulative γ-ray dose rate at 10 locations in the village. The dose rate from each radioactive nuclide in the ground at the monitoring locations was measured by using an in situ γ-ray spectrometer with a Ge detector. The results obtained with the glass dosemeters showed that the γ-ray dose rates in Shariki Village varied from 49 to 55 nGy h -1 . Although the dose rates were generally higher than the mean dose in Aomori Prefecture (1992-1995), the rates were lower than other high dose rate areas which had already been measured. The in situ γ-ray spectrometry revealed that these relatively high dose rates were mainly caused by 40 K and Th series radionuclides in the village. The effect of meteorological conditions on the γ-ray dose rate was studied at a monitoring station in the IES site. The dose rate was continuously recorded by a DBM NaI(Tl) scintillation detector system. The mean dose rate obtained when precipitation was sensed was 27 nGy h -1 and higher than when no precipitation was sensed (25 nGy h -1 ). (author)

  19. Outdoor γ-ray dose rate in Mutsu city and environmental factors affecting outdoor γ-ray dose rate in IES

    International Nuclear Information System (INIS)

    Iyogi, Takashi; Hisamatsu, Shun'ichi; Inaba, Jiro

    2001-01-01

    Previously, we surveyed outdoor γ-ray dose rates throughout Aomori Prefecture from 1992 to 1995, and found a mean annual dose rate of 28 nGy h -1 . Relatively high dose rates were also observed in several areas (municipalities) of the survey locations. In this study, we examined the detailed distribution of the γ-ray dose rate in one such high dose rate area, Mutsu City. Glass dosemeters were used for the monitoring of cumulative γ-ray dose rate at 10 locations in the city. The dose rate from each radioactive nuclide in the ground at the monitoring locations was measured by using an in situ γ-ray spectrometer with a Ge detector. The results obtained with the glass dosemeters showed that the γ-ray dose rates in Mutsu City varied from 17 to 32 nGy h -1 . Although the dose rates were almost the same as the mean dose in Aomori Prefecture (1992-1995), the rates were lower than other high dose rate areas which had already been measured. The in situ γ-ray spectrometry revealed that these relatively high dose rates were mainly caused by 40 K and Th series radionuclides in the local ground. The effect of meteorological conditions on the γ-ray dose rate was studied at a monitoring station in the IES site. The dose rate was continuously recorded by a DBM NaI(Tl) scintillation detector system. The mean dose rate obtained when precipitation was sensed was 26 nGy h -1 and higher than when no precipitation was sensed (24 nGy h -1 ). (author)

  20. Use of dose constraints for occupational exposure

    International Nuclear Information System (INIS)

    Kaijage, Tunu

    2015-02-01

    The use of dose constraints for occupational exposure was reviewed in this project. The role of dose constraints as used in optimization of protection of workers was described. Different issues to be considered in application of the concept and challenges associated with their implementation were also discussed. The situation where dose constraints could be misinterpreted to dose limits is also explained as the two are clearly differentiated by the International Commission of Radiological Protection (ICRP) Publication 103. Moreover, recommendations to all parties responsible for protection and safety of workers were discussed. (au)

  1. Organ doses and effective doses in some medical and industrial applications

    International Nuclear Information System (INIS)

    Keshavkumar, Biju

    2000-01-01

    The ICRP recommends radiation protection standards for the safe use of radiation and also prescribes the radiation protection quantities and periodically reviews them. In this context, the quantities like organ doses and effective doses are defined by ICRP. In this work we calculate these quantities and hence the conversion functions for the industrial radiation sources and those for CT and diagnostic X-ray exposures. Workers who are occupationally exposed to radiation are regularly monitored to evaluate the radiation dose received by them. It is quite possible that in an accident situation, the worker involved in the accident might not have worn a personal monitor, popularly known as the monitoring badge. In addition, even some non radiation workers (who are obviously not monitored) may also have received exposure. Under these circumstances, the persons involved are interviewed, the accident site inspected, and on the basis of realistic assumptions, the likely doses received by the exposed persons are estimated

  2. Dose assessment of natural radioactivity in fly ash and environmental materials from Morupule a coal-fired power station in Botswana

    International Nuclear Information System (INIS)

    Mudiwa, J

    2015-01-01

    above to be 0.048 mSv, 0.091 mSv, 0.136 mSv, 0.070 mSv, 0.048 mSv, 0.041 mSv and 0.039 mSv respectively. Likewise, the reconstructed average annual effective doses for water were 0.0016 mSv, 0.0049 mSv, 0.0083 mSv, 0.0033 mSv, 0.0016 mSv, 0.0011 mSv and 0.0010 mSv respectively. All estimated and reconstructed average annual effective doses are within the recommended public and occupational dose limits of 1 mSv and 20 mSv respectively. The radium equivalent activity, representative level index, external and internal hazard indices for all samples are within recommended international values for their safe use as building materials. Results from this study reveal that there is no significant radiological impact to both the workers and the public within Morupule, a Coal-Fired Power Station and its environs. (au)

  3. Low doses and non-targeted effects in environmental radiation protection; where are we now and where should we go?

    Science.gov (United States)

    Mothersill, Carmel; Rusin, Andrej; Seymour, Colin

    2017-11-01

    The field of low dose radiobiology has advanced considerably in the last 30 years from small indications in the 1980's that all was not simple, to a paradigm shift which occurred during the 1990's, which severely dented the dose-driven models and DNA centric theories which had dominated until then. However while the science has evolved, the application of that science in environmental health protection has not. A reason for this appears to be the uncertainties regarding the shape of the low dose response curve, which lead regulators to adopt a precautionary approach to radiation protection. Radiation protection models assume a linear relationship between dose (i.e. energy deposition) and effect (in this case probability of an adverse DNA interaction leading to a mutation). This model does not consider non-targeted effects (NTE) such as bystander effects or delayed effects, which occur in progeny cells or offspring not directly receiving energy deposition from the dose. There is huge controversy concerning the role of NTE with some saying they reflect "biology" and that repair and homeostatic mechanisms sort out the apparent damage while others consider them to be a class of damage which increases the size of the target. One thing which has recently become apparent is that NTE may be very critical for modelling long-term effects at the level of the population rather than the individual. The issue is that NTE resulting from an acute high dose such as occurred after the A-bomb or Chernobyl occur in parallel with chronic effects induced by the continuing residual effects due to radiation dose decay. This means that if ambient radiation doses are measured for example 25 years after the Chernobyl accident, they only represent a portion of the dose effect because the contribution of NTE is not included. Copyright © 2017. Published by Elsevier Inc.

  4. Social Cognitive Predictors of Interest in Environmental Science: Recommendations for Environmental Educators

    Science.gov (United States)

    Quimby, Julie L.; Seyala, Nazar D.; Wolfson, Jane L.

    2007-01-01

    The authors examined the influence of social cognitive variables on students' interest in environmental science careers and investigated differences between White and ethnic minority students on several career-related variables. The sample consisted of 161 undergraduate science majors (124 White students, 37 ethnic minority students). Results of…

  5. Environmental protection in the frame of radiation protection. Recommendation of the Commission on radiological protection including justification and explanation; Schutz der Umwelt im Strahlenschutz. Empfehlung der Strahlenschutzkommission mit Begruendung und Erlaeuterung

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2017-01-15

    The environmental protection is part of the radiation protection but without defined regulations concerning the protection of non-human species and the ecological systems. In 2008 the SSK (Strahlenschutzkommission) was asked to elaborate measures for environmental radiation protection. Part of the recommendation was the application of sustainability concepts on radioactive materials.

  6. Controllable dose; Dosis controlable

    Energy Technology Data Exchange (ETDEWEB)

    Alvarez R, J T; Anaya M, R A [ININ, A.P. 18-1027, 11801 Mexico D.F. (Mexico)

    2004-07-01

    With the purpose of eliminating the controversy about the lineal hypothesis without threshold which found the systems of dose limitation of the recommendations of ICRP 26 and 60, at the end of last decade R. Clarke president of the ICRP proposed the concept of Controllable Dose: as the dose or dose sum that an individual receives from a particular source which can be reasonably controllable by means of any means; said concept proposes a change in the philosophy of the radiological protection of its concern by social approaches to an individual focus. In this work a panorama of the foundations is presented, convenient and inconveniences that this proposal has loosened in the international community of the radiological protection, with the purpose of to familiarize to our Mexican community in radiological protection with these new concepts. (Author)

  7. 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.

  8. 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

  9. Selecting environmental indicator for use in strategic environmental assessment

    International Nuclear Information System (INIS)

    Donnelly, Alison; Jones, Mike; O'Mahony, Tadhg; Byrne, Gerry

    2007-01-01

    The primary aim of carrying out Strategic Environmental Assessment (SEA) is to provide for a high level of environmental protection and to integrate environmental considerations into the planning process. The SEA Directive (2001/42/EC) recommends monitoring to determine the environmental impact of the implementation of plans and programmes. Environmental indicators are a useful tool by which this impact may be measured. However, careful consideration must be given to developing a set of indicators in order to isolate, plan or programme specific impacts. Here, we demonstrate the effectiveness of a workshop-based approach to develop appropriate criteria for selecting environmental indicator for use in SEA. A multi-disciplinary team was used in the approach which consisted of representatives from each of four environmental fields i.e. biodiversity, water, air and climatic factors, together with SEA experts, planning experts, academics and consultants. The team reviewed various sets of criteria, already in existence, for environmental indicator development but not specifically for SEA indicators. The results of this review together with original criteria were applied to the final list agreed upon. Some of the criteria recommended includes, relevance to plan, ability to prioritise, and ability to identify conflict with other plan or SEA objectives

  10. Implications of ICRP recommendations on the management of radiation protection of workers

    International Nuclear Information System (INIS)

    Huyskens, C.J.

    1992-01-01

    The new ICRP recommendations [1] give a slightly revised definition of occupational exposure. Guidance is given with respect to the exposure at work related no natural radiation sources. Where ICRP recommends a source related definition of occupational exposure, the Basic Safety Standards of the European Communities [3] and consequently legislation in member states depart from an effect related definition of workers. Mutual divergence regarding this identification issue will be discussed in this paper. Operational radiation protection is commonly based on the principles of classification of workers, classification of working conditions and classification of places of work. From the management view point, the rationale for applying classification is to balancing the nature and the scale of control measures, monitoring and surveillance, using resources in the most appropriate way. In previous recommendations [2] ICRP has given criteria for classification, based on the projected level of individual annual dose, relative to the recommended dose limits for occupational exposure. This guidance is now regarded as crude and arbitrary and therefore withdrawn. This paper will address some consequences of the revised recommendations as well as options for implementation in the European Community basic safety standards. (author)

  11. Recommended general safety requirements for nuclear power plants

    International Nuclear Information System (INIS)

    1983-06-01

    This report presents recommendations for a set of general safety requirements that could form the basis for the licensing of nuclear power plants by the Atomic Energy Control Board. In addition to a number of recommended deterministic requirements the report includes criteria for the acceptability of the design of such plants based upon the calculated probability and consequence (in terms of predicted radiation dose to members of the public) of potential fault sequences. The report also contains a historical review of nuclear safety principles and practices in Canada

  12. Estimation of internal exposure dose caused by 3H releasted at QNPP base

    International Nuclear Information System (INIS)

    Liang Meiyan; Ma Yongfu; Ni Shiying; Zhang Xinyu

    2010-01-01

    QNPP III is the first heavy water reactors nuclear power plant in China, with its 1, 2 units generating electricity in November 2002 and June 2003, respectively. This paper, based on the monitoring data of tritium concentration in environmental samples at Xiajiawan, Yangliucun, Qinlian, Qinshanzheng and Wuyuanzheng (sampling points) in the external environment around QNPP Base, in combination with the study on living and eating habits of residents around QNPP Base, presents estimated annual tritium intake of air, drinking water and food for residents (not including the organic combination tritium). In accordance with the new dose coefficient at different ages recommended by ICRP 72 Publication, it is calculated that the tritium annual intake by various approaches for infants, children and adults (at the Xiajiawan resident point) are 5.75, 9.59, 15.7 kBq/a, respectively; the annual committed effective dose are 0.33, 0.18, 0.23 μSv/a respectively. The infant group would receive the largest committed effective dose from tritium, 0.33/μSv/a, but this is only less than 1% of the effective target dose (0.05 mSv). In all, the tritium impact on surrounding areas of QNPP Phase III is very small under the normal and safe operation of HWR. (authors)

  13. Environmental quality model in centralised radiopharmacy units: Guidelines from French Society of Radiopharmacy

    International Nuclear Information System (INIS)

    Bruel, D.; Duez, C.; Ebel-Lao, S.; Garrigue, H.; Le Meur, C.

    2011-01-01

    The preparation of radiopharmaceutical drugs refers to the assessment of both pharmaceutical drugs and radionuclides preparations regulations. It should avoid microbiological contamination while ensuring staff as well as environmental protection from radioactive exposure. Therefore, in order to warranty sterility of injected doses, the environmental quality, specifically units indoor air quality and surfaces quality must be guaranteed. The aim of this work is to propose guidelines pertaining to environmental quality monitoring in the special field of radiopharmacy. These propositions are based on available guidances, including regulations, treating about methodology to apply for evaluation and control of hospital's environment. Throughout this report, the French College of Radiopharmacy proposals both improve the methodology for control and data analysis (targeted grade of environment, threshold for notification and corrective actions) and ensure follow-up and management of nonconformities. These recommendations represent a model for harmonization of radio-pharmacists practices with regards to frequency of environmental quality controls for facilities and equipments in their centralised radiopharmacy units. (authors)

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

    International Nuclear Information System (INIS)

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

    2000-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2000-10-01

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

  16. Policy and technical matters for the application of ICRP 1977 recommendations to Japanese radiation protection regulations

    International Nuclear Information System (INIS)

    Hamada, Tatsuji

    1987-01-01

    Tens years has passed since 1977 when the ICRP recommendations were made, and the work of revising the Japanese radiation regulations in response to the recommendations is almost completed. The work has been conducted mainly by an elemental group established under the Radiation Council. The elemental group submitted the first interim report to the Council in 1980, which presented recommendations on the objectives of radiation protection, dose equivalent limits for the general public, facilities inspection and products testing, medical surveillance, etc. After making deliberations in response to studies by the ICRP working group, the elemental group compiled the second interim report in July 1981. Further studies were conducted and the final report was submitted to the Council in March 1983. The final report covered the definitions of such terms as 'dose equivalent', dose equivalent limit for workers, exposure dose in the event of emergency, dose equivalent limit for the general public, various standards for protection, classification of workers by working conditions, classification of work sites monitoring of exposure dose, and implementation of medical surveillance. After making deliberations, the Council submitted a report in 1986 to government agencies concerned, whose contents are almost the same as those of the above final report except for some amendments. (Nogami, K.)

  17. Comments on ICRP-60 rationale for dose limits for the pregnant worker

    International Nuclear Information System (INIS)

    Myers, D.K.

    1992-06-01

    ICRP Publication 60 has recently recommended new dose limits for the radiation exposure of pregnant workers. These new dose limits for pregnant workers are more restrictive than the current limits in force in Canada. Recent presentations by Dr. R.H. Mole have faulted the arguments provided by ICRP as justification for reducing the previously recommended limits for pregnant radiation workers. The present paper provides a brief review of the development of the human conceptus, of the biological effects of low doses of radiation on the foetus, and discusses R.H. Mole's comments on ICRP-60. On the critical issues concerning the presence or absence of threshold doses for induction of specific biological endpoints, Dr. Mole and ICRP-60 appear to be in agreement. The basic disagreement between Dr. Mole and ICRP-60 seems to revolve around the philosophical question of whether dose limits should be based on quantitative risks to the foetus or whether dose limits to the pregnant worker should provide a standard of protection to the foetus which is broadly comparable with that provided for members of the general public. Further research is recommended on one of the topics raised by Dr. Mole, namely, foetal doses from radionuclides inhaled or ingested by the mother

  18. Recommendations for the delineation of organs at risk in ENT radiotherapy

    International Nuclear Information System (INIS)

    Ali, D.; Halimi, P.; Berges, O.; Deberne, M.; Botti, M.; Giraud, P.; Servagi-Vernat, S.

    2011-01-01

    Based on a literature survey, the authors propose recommendations for the delineation of the pharyngeal constrictor muscles, inner ear, larynx, buccal cavity, and temporomandibular joint. These recommendations of delineation of organs at risk are related to the functional anatomy of the considered structures, and correspond to volumes used in published surveys on dose-volume toxicity. They are simple and reproducible. Short communication

  19. Radiation doses and risks from internal emitters

    International Nuclear Information System (INIS)

    Harrison, John; Day, Philip

    2008-01-01

    This review updates material prepared for the UK Government Committee Examining Radiation Risks from Internal Emitters (CERRIE) and also refers to the new recommendations of the International Commission on Radiological Protection (ICRP) and other recent developments. Two conclusions from CERRIE were that ICRP should clarify and elaborate its advice on the use of its dose quantities, equivalent and effective dose, and that more attention should be paid to uncertainties in dose and risk estimates and their implications. The new ICRP recommendations provide explanations of the calculation and intended purpose of the protection quantities, but further advice on their use would be helpful. The new recommendations refer to the importance of understanding uncertainties in estimates of dose and risk, although methods for doing this are not suggested. Dose coefficients (Sv per Bq intake) for the inhalation or ingestion of radionuclides are published as reference values without uncertainty. The primary purpose of equivalent and effective dose is to enable the summation of doses from different radionuclides and from external sources for comparison with dose limits, constraints and reference levels that relate to stochastic risks of whole-body radiation exposure. Doses are calculated using defined biokinetic and dosimetric models, including reference anatomical data for the organs and tissues of the human body. Radiation weighting factors are used to adjust for the different effectiveness of different radiation types, per unit absorbed dose (Gy), in causing stochastic effects at low doses and dose rates. Tissue weighting factors are used to take account of the contribution of individual organs and tissues to overall detriment from cancer and hereditary effects, providing a simple set of rounded values chosen on the basis of age- and sex-averaged values of relative detriment. While the definition of absorbed dose has the scientific rigour required of a basic physical quantity

  20. Implementations of new ICRP recommendations in the operation of the spanish nuclear power plants

    International Nuclear Information System (INIS)

    Sollet Sanudo, E.

    1992-01-01

    The International Commission on Radiological Protection (ICRP) has recently reviewed its basic recommendations including a strong reduction in the annual dose limit for exposed workers to ionising radiation, New dose limits in occupational exposure will have a direct impact in all activities concerning radiation exposure. The likely effect on the nuclear industry of a major decrease in exposure limits is discussed and the approaches taken to minimize radiation exposures is presented. Changes to the philosophy of radiation protection that would allow accommodation of lower limits are suggested. Improvements to dose tracking and dose monitoring techniques are discussed. Methods for reducing existing radiation fields and for preventing future radiation field increases are briefly reviewed. Additionally, actions taken in the Spanish nuclear industry to identify collective groups and tasks potentially affected by the reduced new recommended limits are presented. (author)