WorldWideScience

Sample records for radiological protection monitoring

  1. Present state and problems of radiological protection monitoring for high energy electron accelerator facilities in SPring-8

    International Nuclear Information System (INIS)

    Miyamoto, Yukihiro; Harada, Yasunori; Ueda, Hisao

    1998-09-01

    The present state and problems of the radiological protection monitoring for the high-energy electron accelerator are summarized. In the radiological protection monitoring for SPring-8, a third generation synchrotron radiation facility, there are many problems specific to the high-energy electron accelerator. This report describes the monitoring technique of pulsed radiation, high-energy radiation and low-energy radiation, and their problems. The management of induced radioactivity and the effects of electro-magnetic noise to monitoring instruments are also discussed. (author)

  2. Occupational radiological protection in diagnostic radiology

    International Nuclear Information System (INIS)

    Mota, H.C.

    1983-01-01

    The following topics are discussed: occupational expossure (the ALARA principle, dose-equivalent limit, ICRP justification); radiological protection planning (general aspects, barrier estimation) and determination of the occupational expossures (individual monitoring). (M.A.) [pt

  3. Program of environmental radiological monitoring

    International Nuclear Information System (INIS)

    2005-11-01

    This Regulation refers to the requirement of the Regulation CNEN-NN.3.01, 'Basic Act of Radiological Protection', as expressed in the section 5.14, related to the Program of Environmental Radiological Monitoring (PMRA)

  4. Radiological protection Program of CDTN

    International Nuclear Information System (INIS)

    1983-01-01

    Radiological protection program of CDTN, its purposes and rules, responsabilities, physical control, monitoring, personnel radiation protection, radiation sources and radioactive wastes control, emergency and accidents and siting are described. (C.M.) [pt

  5. Radiation protection and monitoring

    International Nuclear Information System (INIS)

    Thomas, P.

    1982-01-01

    The present paper deals with the following topics: - Radiological quantities and units - Principles of radiological protection - Limits of doses and activity uptake - Activity discharges and monitoring - Radiation exposure and its calculation - Environmental monitoring - Personnel dosimetry. (orig./RW)

  6. Radiological protection of the unborn child. Recommendation of the Commission on Radiological Protection and scientific grounds

    International Nuclear Information System (INIS)

    Sarenio, O.

    2006-01-01

    The Commission on Radiological Protection was asked to give advice on the practical implications of the absorption of the maximum possible activity values that, under the Radiological Protection Ordinance, may be incorporated in women of child-bearing age occupationally exposed to radiation with regard to incorporation monitoring and compliance with the dose limit for the protection of the unborn child. An unborn child's conceivable level of exposure to radiation in the least favourable case due to continuous and single incorporations of radionuclides in the mother was determined on a nuclide-specific basis by the Federal Office for Radiation Protection with the aid of the mathematical metabolic models provided in ICRP 88. At the proposal of the Commission on Radiological Protection, the Federal Office for Radiation Protection considered the following very conservative scenarios: - the mother's maximum possible exposure due to a continuous intake of activity over 10 years prior to the pregnancy and in the first 10 weeks postconception based on the limits set out in the Radiological Protection Ordinance; - the mother's maximum possible exposure due to a single intake at the most unfavourable time in the first 10 weeks postconception based on the limits set out in the Radiological Protection Ordinance. Examination of these scenarios found that, with a few exceptions, the dose to the unborn child attributable to the incorporation of radiation in the mother summed up over 70 years is less than that to the mother. The committed effective dose to the unborn child from certain radionuclides may exceed the value of 1 mSv when the dose to the mother reaches the maximum limit. The Commission on Radiological Protection was therefore asked 1. to examine whether compliance with the limit of 1 mSv effective dose is sufficient for the protection of the unborn child or whether any additional limitation is required for individual organs, 2. to discuss the implications for

  7. Radiological Protection and Environmental Monitoring in Bolivia

    International Nuclear Information System (INIS)

    MartInez Pacheco, J.

    1979-01-01

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

  8. Implementation of a remote system for monitoring of radiological areas of radiological areas

    International Nuclear Information System (INIS)

    Velazquez E, Walter; Galuppo G, Emiliano; Gutierrez G, Jorge; Reyes R, Jerson

    2008-01-01

    Full text: Introduction: The present work shows the development of a radiation remote monitoring system which control radiological areas in the principal facilities at CCHEN and the development in the last years to use this system called SMARR (Remote Radiological Area Monitoring System). This is an important issue in radiological safety is to know 'on line' and in a 'continuously way' the radiological variables of areas, especially if in these areas people manage radioactive sources or material, the monitoring system are operative on La Reina and Lo Aguirre Nuclear Centers. This 'knowledge' gets a good support to the radiological safety to safeguard the environment and people in the facilities. Nuclear Chilean Commission: Actually, this system is daily operating to register the background radiation and level operation, for example of the facilities research reactor, cyclone, irradiators, in order to probe the behaviors under operational requirements. The system was made using common Geiger Muller and NaI detectors. This signal is received, data by data, for a collector computer which uses a Labview program to do this displayed on a screen computer using graphics to show the activity on a radiological area, and when the lectures pass a setting value automatically the system send by e-mail and text message which also can be received for cell phones enabled for this for the supervisor. Each monitored facility is completely independent of each other and store a data backup, also every installation are monitoring with server computer, it's concentrating the information and allow to view it on line in real time, trough the intranet and internet network. In addition, the information is stored in the special report in the server and available for to do a statistics and identify the operation periods, and control of radioactive sources. The Industry: The radiological protection on industry is necessary today, the typical instrumentation on the industry is growing up in the

  9. ICRP Publication 139: Occupational Radiological Protection in Interventional Procedures.

    Science.gov (United States)

    López, P Ortiz; Dauer, L T; Loose, R; Martin, C J; Miller, D L; Vañó, E; Doruff, M; Padovani, R; Massera, G; Yoder, C

    2018-03-01

    In recent publications, such as Publications 117 and 120, the Commission provided practical advice for physicians and other healthcare personnel on measures to protect their patients and themselves during interventional procedures. These measures can only be effective if they are encompassed by a framework of radiological protection elements, and by the availability of professionals with responsibilities in radiological protection. This framework includes a radiological protection programme with a strategy for exposure monitoring, protective garments, education and training, and quality assurance of the programme implementation. Professionals with responsibilities in occupational radiological protection for interventional procedures include: medical physicists; radiological protection specialists; personnel working in dosimetry services; clinical applications support personnel from the suppliers and maintenance companies; staff engaged in training, standardisation of equipment, and procedures; staff responsible for occupational health; hospital administrators responsible for providing financial support; and professional bodies and regulators. This publication addresses these elements and these audiences, and provides advice on specific issues, such as assessment of effective dose from dosimeter readings when an apron is worn, estimation of exposure of the lens of the eye (with and without protective eyewear), extremity monitoring, selection and testing of protective garments, and auditing the interventional procedures when occupational doses are unusually high or low (the latter meaning that the dosimeter may not have been worn).

  10. Radiological monitoring of food in Cuba

    International Nuclear Information System (INIS)

    Jerez V, S.F.

    1996-01-01

    The appearing of the problem for protecting the environment from radioactive contamination is not an accidental matter. The introduction into the earth crust of radioactive material coming from nuclear weapons, accidents, wastes, etc, has caused, as a consequence, the contamination of the biosphere. The extensive trade of food in our country has made necessary the establishment of radiological monitoring in food, which was organized by the Department of Public Health. The structure, functions, characteristics and aspects related to radiological monitoring of food in Cuba are shown in the present paper. The organization and resources for performing the monitoring program, both for normal conditions and for nuclear and/or radiological emergency cases, are detailed. (author). 12 refs., 2 figs

  11. Radiological protection and quality control for diagnostic radiology in China

    International Nuclear Information System (INIS)

    Baorong, Yue

    2008-01-01

    Full text: There are 43,000 diagnostic departments, nearly 70,000 X-ray diagnostic facilities, 7,000 CT, 250 million for the annual total numbers of X-ray examinations, 120,000 occupationally exposed workers in diagnostic radiology. 'Basic standards for protection against ionizing radiation and for the safety of radiation sources' is promulgated on October, 2002. This basic standard follows the BSS. 'Rule on the administration of radio-diagnosis and radiotherapy', as a order of the Ministry of Health No. 46, is promulgated by Minister of Health on January 24, 2006. It includes general provisions, requirements and practice, establishment and approval of radio-diagnosis and radiotherapy services, safeguards and quality assurance, and so on. There are a series of radiological protection standards and quality control standards in diagnostic radiology, including 'radiological protection standard for the examination in X-ray diagnosis', 'radiological health protection standards for X-ray examination of child-bearing age women and pregnant women', 'radiological protection standards for the children in X-ray diagnosis', 'standards for radiological protection in medical X-ray diagnosis', 'specification for radiological protection monitoring in medical X-ray diagnosis', 'guide for reasonable application of medical X-ray diagnosis', 'general aspects for quality assurance in medical X-ray image of diagnosis', 'specification of image quality control test for the medical X-ray diagnostic equipment', 'specification of image quality assurance test for X-ray equipment for computed tomography', 'specification for testing of quality control in computed radiography (CR)' and 'specification for testing of quality control in X-ray mammography'. With the X-ray diagnostic equipment, there are acceptant tests, status tests and routing tests in large hospitals. It is poor for routing test in middle and smaller hospitals. CT is used widely in diagnostic radiology, however most workers in CT

  12. Neutron monitoring for radiological protection

    International Nuclear Information System (INIS)

    Gibson, J.A.B.

    1985-01-01

    Neutron monitoring is a subject of increasing general interest and considerable attention is being paid to the development of improved techniques and methods for neutron monitoring. The Agency, therefore, considered it important to prepare a guide on the subject of neutron monitoring for radiation protection purposes. The present Manual is intended for those persons or authorities in Member States, particularly developing countries, who are responsible for the organization of neutron monitoring programmes and practical neutron monitoring. This Manual consequently, deals with topics such as neutron dosimetry, sources of neutrons and neutron detection as well as field instruments and operational systems used in this context

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2017-07-01

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

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

    International Nuclear Information System (INIS)

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

    2017-01-01

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

  15. Radiological protection

    International Nuclear Information System (INIS)

    Azorin N, J.; Azorin V, J. C.

    2010-01-01

    This work is directed to all those people related with the exercise of the radiological protection and has the purpose of providing them a base of knowledge in this discipline so that they can make decisions documented on technical and scientist factors for the protection of the personnel occupationally exposed, the people in general and the environment during the work with ionizing radiations. Before de lack of a text on this matter, this work seeks to cover the specific necessities of our country, providing a solid presentation of the radiological protection, included the bases of the radiations physics, the detection and radiation dosimetry, the radiobiology, the normative and operational procedures associates, the radioactive wastes, the emergencies and the transport of the radioactive material through the medical and industrial applications of the radiations, making emphasis in the relative particular aspects to the radiological protection in Mexico. The book have 16 chapters and with the purpose of supplementing the given information, are included at the end four appendixes: 1) the radioactive waste management in Mexico, 2-3) the Mexican official standards related with the radiological protection, 4) a terms glossary used in radiological protection. We hope this book will be of utility for those people that work in the investigation and the applications of the ionizing radiations. (Author)

  16. Radiological protection in underground uranium mines

    International Nuclear Information System (INIS)

    Napolitano, Celia Marina

    1978-01-01

    The radiosanitary hazards that workers of an uranium ore can suffer were studied. The more used control methods for the the evaluation of doses received by the workers was studied too. It was developed a technique using the scintillation chamber method for the detection of radon. Emanation and diffusion methods were used for extraction of radon from water. A program of radiological protection based on ICRP recommendation was analysed for uranium mines. This program includes: ventilation needs calculation methods, a study of radiological protection optimization based on 'cost-benefit' analysis, a monitoring plan and a study about radioactive waste management. (author)

  17. Evolution of the radiological protection paradigms

    International Nuclear Information System (INIS)

    Sordi, Gian Maria A.A.

    2009-01-01

    We consider as initial radiological protection paradigms those in vigour after the release of the atomic energy for pacific usages in 1955. In that occasion, only one paradigm was introduced, presently named dose limitation system. After arguing about the basis that raised the paradigm, we introduced the guidance, that is, the measurements to be implemented to comply with the paradigm. In that occasion, they were two, i.e., the radiation dose monitoring and the workplace classification. Afterwards, the reasons that caused the radiological protection paradigms changes in force until 1995 are discussed. The initial paradigm was modified introducing the justification and the optimization principles, adding that the radiological protection should be economical and effective. The guidance also increased to four: personal monitoring, workplace classification, reference level and workers classification. Afterwards, we give the main justifications for the present paradigms that besides the formers were added the dose constraints, the potential exposure and the annual risk limits. Due to these modifications, the workers classifications were eliminated from the guidance, but the potential exposure and the search for the dose constraints were added. Eventually, we discuss the tendencies for the next future and the main changes introduced by the ICRP in the Publication 103, 2007. (author)

  18. Radiological protection report 2012

    International Nuclear Information System (INIS)

    2013-06-01

    Two years after the massive release of radiation from the nuclear power plants at Fukushima Dai-ichi, the repercussions continue to preoccupy the radiological and emergency protection community, both in Switzerland and internationally. In Switzerland the Swiss Federal Nuclear Safety Inspectorate (ENSI) has initiated measures as part of the European Union Stress Tests and has its own Fukushima Action Plan. In this Annual Report, ENSI focuses on radiological protection in Swiss nuclear facilities. The average individual dose has changed little compared with previous years. At 0.7 mSv, it is significantly below the limit both for persons exposed to radiation during their work (20 mSv) and the annual average rate of exposure for the population in Switzerland as a whole (5.5 mSv). In terms of collective doses, the extensive maintenance work at the Leibstadt power plant (KKL) resulted in a doubling of rates compared with recent years. However, in the remaining nuclear facilities the rates have not changed significantly. The highest individual dose during the year under review was 13 mSv. Exposure rates in 2012 for all those exposed to radiation during work in facilities subject to ENSI surveillance were below the maximum limit. Greater attention is now being given to work in high and variable radiation fields and in difficult conditions. Swiss nuclear facilities continue to operate a consistent radiological protection approach. Measuring equipment plays an important role in radiological protection. Having conducted a range of inspections and comparative measurements of aerosol-iodine filters and waste water sampling together with measurements in the field of personal dosimetry, ENSI has concluded that the required measuring equipment for radiological protection exists, that this equipment is correctly used and provides reliable data. ENSI maintains a test laboratory that analyses samples from nuclear facilities and their immediate vicinity and also conducts field

  19. Status of radiation protection in interventional radiology. Assessment of inspections in 2009 by the ASN

    International Nuclear Information System (INIS)

    2011-01-01

    This report first describes the organization of inspections performed in health institutions, indicates the inspected establishments, the types of fixed installations in interventional radiology, the use of imagery in the operating theatre, and discusses the regulatory arrangements applicable to interventional radiology (in the Public Health Code, in the Labour Code). Then, the report discusses the results of inspections regarding radiation protection in interventional radiology: application of public health code arrangements (justification, patient training in radiation protection, radiological procedures and protocols, patient dosimetry monitoring), application of Labour Code arrangements (designation of the person with expertise in radiation protection, risk assessment and delimitation of monitored and controlled areas, workstation analysis, workers' training in radiation protection, individual protection equipment, workers' dosimetric monitoring, workers' medical monitoring, radiation protection technical controls), significant events, radiation protection in operating theatre. Propositions are stated regarding the differences noticed within or between the health establishments, the methodological and organisational difficulties faced by persons with expertise in radiation protection (PCR), the need of an interdisciplinary team

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

    International Nuclear Information System (INIS)

    1995-10-01

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

  1. Suitability of monitoring methods for the optimisation of Radiological Protection in the case of internal exposure through inhalation

    International Nuclear Information System (INIS)

    Degrange, J.P.; Gibert, B.; Basire, D.

    2000-01-01

    The radiological protection system recommended by the International Commission for Radiological Protection (ICRP) for justified practices relied pn the limitation and optimisation principles. The monitoring of internal exposure is most often based on the periodic assessment of individual exposure in order to essentially insure the simple compliance with the annual dose limits. Optimisation of protection implies a realistic, sensitive and analytical assessment of individual and collective exposures in order to allow the indentification of the main sources of exposure (main sources of contamination, most exposed operators, work activities contributing the most to the exposure) and the selection of the optimal protection options. Therefore the monitoring methods must allow the realistic assessment of individual dose levels far lower than annual limits together with measurements as frequent as possible. The aim of this presentation is to discuss the ability of various monitoring methods (collective and individual air sampling, in vivo and in vitro bioassays) to fulfil those needs. This discussion is illustrated by the particular case of the internal exposure to natural uranium compounds through inhalation. Firstly, the sensitivity and the degree to which each monitoring method is realistic are quantified and discussed on the basis of the application of the new ICRP dosimetric model, and their analytical capability for the optimisation of radiological protection is then indicated. Secondly, a case study is presented which shows the capability of individual air sampling techniques to analyse the exposure of the workers and the inadequacy of static air sampling to accurately estimate the exposures when contamination varies significantly over time and space in the workstations. As far as exposure to natural uranium compounds through inhalation is concerned, the study for assessing the sensitivity, analytic ability and accuracy of the different measuring systems shows that

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

    International Nuclear Information System (INIS)

    1996-08-01

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

  3. Introduction of radiological protection; Pengenalan kepada perlindungan radiologi

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1988-12-31

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

  4. Federal Radiological Monitoring and Assessment Center Overview of FRMAC Operations

    International Nuclear Information System (INIS)

    1998-01-01

    In the event of a major radiological emergency, 17 federal agencies with various statutory responsibilities have agreed to coordinate their efforts at the emergency scene under the umbrella of the Federal Radiological Emergency Response Plan. This cooperative effort will ensure that all federal radiological assistance fully supports their efforts to protect the public. the mandated federal cooperation ensures that each agency can obtain the data critical to its specific responsibilities. This Overview of Federal Radiological Monitoring and Assessment Center (FRMAC) describes the FRMAC response activities to a major radiological emergency. It also describes the federal assets and subsequent operational activities which provide federal radiological monitoring and assessment of the off-site areas

  5. Federal Radiological Monitoring and Assessment Center: Phase I Response

    International Nuclear Information System (INIS)

    Riland, C.; Bowman, D.R.; Lambert, R.; Tighe, R.

    1999-01-01

    A Federal Radiological Monitoring and Assessment Center (FRMAC) is established in response to a Lead Federal Agency (LFA) or State request when a radiological emergency is anticipated or has occurred. The FRMAC coordinates the off-site monitoring, assessment, and analysis activities during such an emergency. The FRMAC response is divided into three phases. FRMAC Phase 1 is a rapid, initial-response capability that can interface with Federal or State officials and is designed for a quick response time and rapid radiological data collection and assessment. FRMAC Phase 1 products provide an initial characterization of the radiological situation and information on early health effects to officials responsible for making and implementing protective action decisions

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

    International Nuclear Information System (INIS)

    Thome, D.J.

    1995-01-01

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

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

    International Nuclear Information System (INIS)

    Thome, D.J.

    1994-01-01

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

  8. Report by the work-group on radiation protection in interventional radiology. Recommendations related to the improvement of radiation protection in interventional radiology

    International Nuclear Information System (INIS)

    2010-01-01

    This report aims at proposing recommendations for the improvement of the quality of radiation protection of workers and patients in the field of interventional radiology. These recommendations concern the training of health personnel, the application of the optimization principle to health professionals and patients, dosimetry and the definition of diagnosis reference levels. More particularly, these recommendations concern professions involved in interventional radiology, and take into account the experience of other European Union State members and recommendations made by the IAEA. The authors analyze the equipment, radiological actions, procedures and doses, practitioners, equipment used for radio-guided interventions. They discuss doses received by patients, patient monitoring and radio-induced lesions. Then, they address the role and training of the different interveners in radiation protection, the equipment maintenance issue, and personnel dosimetry and protection

  9. Training in radiological protection at the Institute of Naval Medicine

    International Nuclear Information System (INIS)

    Powell, P.E.; Robb, D.J.

    1991-01-01

    The Training Division at the Institute of Naval Medicine, Alverstoke, UK, provides courses in radiological protection for government and military personnel who are radiation protection supervisors, radiation safety officers, members of naval emergency monitoring teams and senior medical officers. The course programmes provide formal lectures, practical exercises and tabletop exercises. The compliance of the Ministry of Defence with the Ionising Radiations Regulations 1985 and the implementation of Ministry of Defence instructions for radiological protection rely to a large extent on its radiation protection supervisors understanding of the training he receives. Quality assurance techniques are therefore applied to the training. (author)

  10. Federal Radiological Monitoring and Assessment Center (FRMAC): Overview of FRMAC operations

    International Nuclear Information System (INIS)

    1993-09-01

    The purpose of this Management Overview of the Federal Radiological Monitoring and Assessment Center (FRMAC) is to explain the federal preparation for a radiological accident and to describe the subsequent response activities which provide radiological monitoring and assessment outside the boundaries of the monitoring which support the radiological accident site. In the event of a radiological accident, federal agencies with various statutory responsibilities have agreed to coordinate their efforts at the accident scene under the umbrella of the Federal Radiological Emergency Response Plan (FRERP). This cooperative effort will assure the state(s) and the Lead Federal Agency (LFA) that all federal technical assistance is fully supporting their efforts to protect the public and will provide these monitoring results in a working data center for immediate use by the state(s) and LFA decision makers. The federal agencies do not relinquish their statutory responsibilities. However, the mandated federal cooperation ensures that each agency can obtain the data critical to its specific responsibility

  11. Division of Radiological Protection : progress report, 1989-1991

    International Nuclear Information System (INIS)

    Gupta, B.L.; Nagarajan, P.S.; Bhatt, B.C.; Seethapathy, A.; Pradhan, A.S.; Vishwakarma, R.R.

    1992-01-01

    This report describes the work of the Division of Radiological Protection during 1989-91, for implementation of radiation safety in all institutions in the country using radiation sources for medical, industrial and research applications. It gives information about personnel monitoring using photographic film and TLD badges, neutron monitoring badges, dosimetric techniques developed, calibration techniques for high-dose irradiators, design and fabrication of special radiation protection instruments, advisory and licensing services, regulation and transport of radioactive materials, periodic protection survey, education and training related to radiation safety programmes. About 164 publications by the staff of this Division are listed. (author). 1 index., 1 tab

  12. Radiological protection in interventional radiology

    International Nuclear Information System (INIS)

    Padovani, R.

    2001-01-01

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

  13. Notes on basic radiological protection. 2. ed.

    International Nuclear Information System (INIS)

    McDowell, D.J.

    1990-01-01

    A booklet has been compiled giving a basic guide to anyone who has to work with ionising radiations and radioactive and the nature of radiation, radiological units, biological radiation effects, legislation and radiation dose limits, radiation and contamination monitoring and finally methods of protection from both external and internal radiation. (UK)

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

    International Nuclear Information System (INIS)

    Doyle, J.F. III.

    1986-01-01

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

  15. Radiological Protection Science and Application

    International Nuclear Information System (INIS)

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

    2016-01-01

    Since the discovery of radiation at the end of the 19. century, the health effects of exposure to radiation have been studied more than almost any other factor with potential effects on human health. The NEA has long been involved in discussions on the effects of radiation exposure, releasing two reports in 1994 and 2007 on radiological protection science. This report is the third in this state-of-the-art series, examining recent advances in the understanding of radiation risks and effects, particularly at low doses. It focuses on radiobiology and epidemiology, and also addresses the social science aspects of stakeholder involvement in radiological protection decision making. The report summarises the status of, and issues arising from, the application of the International System of Radiological Protection to different types of prevailing circumstances. Reports published by the NEA Committee on Radiation Protection and Public Health (CRPPH) in 1998 and 2007 provided an overview of the scientific knowledge available at that time, as well as the expected results from further research. They also discussed the policy implications that these results could have for the radiological protection system. The 2007 report highlighted challenges posed by developments in relation to medical exposure and by intentions to include the environment (i.e. non-human species), within the scope of the radiological protection system. It also addressed the need to be able to respond to a radiological terrorist attack. This report picks up on where the 1998 and 2007 reports left off, and addresses the state of the art in radiological prevention science and application today. It is divided into five chapters. Firstly, following broadly the structural topics from the 1998 and 2007 reports, the more purely scientific aspects of radiological protection are presented. These include cancer risk of low dose and dose rates, non-cancer effects and individual sensitivity. In view of the increasing

  16. Radiological protection report 2012; Strahlenschutzbericht 2012

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-06-15

    Two years after the massive release of radiation from the nuclear power plants at Fukushima Dai-ichi, the repercussions continue to preoccupy the radiological and emergency protection community, both in Switzerland and internationally. In Switzerland the Swiss Federal Nuclear Safety Inspectorate (ENSI) has initiated measures as part of the European Union Stress Tests and has its own Fukushima Action Plan. In this Annual Report, ENSI focuses on radiological protection in Swiss nuclear facilities. The average individual dose has changed little compared with previous years. At 0.7 mSv, it is significantly below the limit both for persons exposed to radiation during their work (20 mSv) and the annual average rate of exposure for the population in Switzerland as a whole (5.5 mSv). In terms of collective doses, the extensive maintenance work at the Leibstadt power plant (KKL) resulted in a doubling of rates compared with recent years. However, in the remaining nuclear facilities the rates have not changed significantly. The highest individual dose during the year under review was 13 mSv. Exposure rates in 2012 for all those exposed to radiation during work in facilities subject to ENSI surveillance were below the maximum limit. Greater attention is now being given to work in high and variable radiation fields and in difficult conditions. Swiss nuclear facilities continue to operate a consistent radiological protection approach. Measuring equipment plays an important role in radiological protection. Having conducted a range of inspections and comparative measurements of aerosol-iodine filters and waste water sampling together with measurements in the field of personal dosimetry, ENSI has concluded that the required measuring equipment for radiological protection exists, that this equipment is correctly used and provides reliable data. ENSI maintains a test laboratory that analyses samples from nuclear facilities and their immediate vicinity and also conducts field

  17. Radiological protection in dentistry

    Energy Technology Data Exchange (ETDEWEB)

    Holliday, B

    1974-01-01

    Information that would allow an assessment of the standard of radiological protection in dentistry in the United Kingdom is sparse. The National Radiological Protection Board (previously the Radiological Protection Service) has provided a monitoring and advisory service to dentists for many years but very limited use has been made of this service. In a recent survey, 114 dentists were visited in representative practices in South East England and it was established that only 6.5% of dentists in general practice do not use radiography as an adjunct to their practice (Smith, 1969). In the 88 x-ray sets which were examined, 24% had less than the recommended thickness of aluminium filtration, while 25% had a fixed field size which was larger than necessary for dental radiography; in addition, 27% of the timers were found to have an error of greater than 20% in repetition of the pre-set exposure time. The exposure rate at the cone tip of a dental x-ray unit is generally in the range 1 to 4 R/s. A fault in the timer unit coupled with a failure on the part of the dentist to notice that x-rays are being generated (normally indicated by a red warning light) would rapidly lead to excessive exposure of the patient. Furthermore, a dentist continually holding films in the mouth of his patient would certainly incur a dose well in excess of the permissible hand dose, assuming anaverage work load for the x-ray equipment. Three case histories are given to illustrate the type of hazard that might arise from faulty equipment or bad operating technique.

  18. Radiological Protection Institute of Ireland activities and responsibilities

    International Nuclear Information System (INIS)

    1994-01-01

    This brochure describes the Radiological Protection Institute of Ireland's functions and responsibilities which relate principally to the monitoring of radioactivity in the environment and of radiation doses received by people occupationally or otherwise; regulation of the uses of ionising radiation in medicine, industry and elsewhere; assistance in developing national preparedness for response to a radiological emergency; and providing information and advice to government, other organisations and the general public on matters relating to ionising radiation. ills

  19. A project: 'Radiological protection in radiology', IAEA - Universidad Central de Venezuela

    International Nuclear Information System (INIS)

    Diaz, A.R.; Salazar, G.; Fermin, R.; Gonzalez, M.

    2001-01-01

    For several years a reference center of the UCV has been working on the project VEN/9/007 on dose reduction in diagnostic radiology sponsored by the IAEA. The dose and quality image was evaluated for different types of radiological study (conventional radiology, CT, mammography, interventional radiology) in different facilities at Caracas and others regions of the Venezuela. TL dosimeters were used to assess dose and reduction in dose. Based on the recommendations given by CEC documents on diagnostic quality criteria, a quality control program in radiological protection of patients and staff has been developed, for example: Pilot study by using TLD in personnel radiation monitoring. Comparative study between high and low kVp in chest. Evaluation and dose reduction in chest pediatric. Reduction of radiation dose in studies of billiards via Quality Image and reduction of the dose in studies of colon by enema. Radiation dose of staff in fluoroscopy procedures. Evaluation and dose reduction in dental radiography in public Institutions. A mammography accreditation program for Venezuela, applied to public hospitals. (author)

  20. Evaluation of the conditions and practices of radiological protection technicians in radiology, according to Ordinance 453

    International Nuclear Information System (INIS)

    Costa, Rogerio Ferreira da

    2013-01-01

    Professionals in radiology suffer whole body exposure to low doses for long periods . The system of radiological protection should keep exposures below recommended thresholds, thus avoiding the stochastic effects that can be triggered with any dose level value, and there is not a threshold for induction of the same. Therefore it is important to use personal dosimeter for monitoring doses and protective equipment. The increase in procedures using ionizing radiation in recent years has been noted with concern, since many companies are not complying with the standards of protection. This is because some procedures may be performed without the need of surgery, which presents a greater risk to the patient. Furthermore, Brazilians are being exposed to radiation without necessity. The reasons range from radiological equipment miscalibrated to poorly trained staff. Thus we evaluate the conditions and practices of radiation protection technicians in radiology according to Ordinance 453 in Goiania, GO, Brazil. Through a descriptive survey with a quantitative approach, we used the technique of gathering information based on a questionnaire. From this survey, we identified the procedures used by radiation protection professionals and concluded that there are failures in the procedures for protecting patients and accompanying and in the training of the professionals. (author)

  1. Generic procedures for monitoring in a nuclear or radiological emergency

    International Nuclear Information System (INIS)

    1999-06-01

    One of the most important aspects of managing a radiological emergency is the ability to promptly and adequately assess the need for protective actions. Protective action accident management must make use of the key relevant information available. Decision-making and accident assessment will be an iterative and dynamic process aimed at refining the initial evaluation as more detailed and complete information becomes available. Emergency monitoring is one of the main sources for obtaining needed information. This publication is in the scope of the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency (Legal Series No. 14) under which the IAEA is authorized to assist a State Party or a Member State among other matters in developing appropriate radiation monitoring programmes, procedures and standards (Article 5). The scope of this manual is restricted to practical guidance for environmental and source monitoring during a nuclear or other radiological emergency. It does not address emergency response preparedness, nor does it cover the emergency management aspects of accident assessment. This manual is organised into sections relating to measurements in order of priority of a major reactor accident, namely: ambient gamma/beta dose rates from plume, ground deposition or source; radionuclide concentrations in air; deposition maps for 131 I and 137 Cs and other important radionuclides; radionuclide mix in deposition and radionuclide concentrations in food, drinking water and other samples. The introductory section provides an overview of the design of emergency monitoring and sampling programmes, monitoring teams and their qualifications and training, monitoring equipment and instrumentation, protective actions for emergency monitoring teams and quality assurance and quality control checks

  2. Division of Radiological Protection progress report 1982-1988

    International Nuclear Information System (INIS)

    Gupta, B.L.; Bhat, R.M.; Narayan, G.R.

    1989-01-01

    This report describes the work of the Division of Radiological Protection during 2-88, for implementation of radiation safety in all institutions in the country using radiation sources for medical, industrial and research applications. It gives information about personnel monitoring using photographic film and TLD badges, neutron monitoring badges, dosimetric techniques developed, calibration facilities and maintenance of national standards for radiation and radioactivity, design and fabrication of special radiation protection instruments, development of coloured indicators for indentification of radiation sterilized medical products, advisory and licencing services, regulation and transport of radioactive materials, periodic protection survey, education and training related to radiation safety programmes. About 500 publications by the staff of this Division are listed. (author). 46 figs

  3. Federal Radiological Monitoring and Assessment Center (FRMAC) overview of FRMAC operations

    International Nuclear Information System (INIS)

    1996-02-01

    In the event of a major radiological emergency, 17 federal agencies with various statutory responsibilities have agreed to coordinate their efforts at the emergency scene under the umbrella of the Federal Radiological Emergency Response plan (FRERP). This cooperative effort will assure the designated Lead Federal Agency (LFA) and the state(s) that all federal radiological assistance fully supports their efforts to protect the public. The mandated federal cooperation ensures that each agency can obtain the data critical to its specific responsibilities. This Overview of the Federal Radiological Monitoring and Assessment Center (FRMAC) Operations describes the FRMAC response activities to a major radiological emergency. It also describes the federal assets and subsequent operational activities which provide federal radiological monitoring and assessment of the off-site areas. These off-site areas may include one or more affected states

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

    International Nuclear Information System (INIS)

    2001-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-03-01

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

  6. Training for Radiation Protection in Interventional Radiology

    International Nuclear Information System (INIS)

    Bartal, G.; Sapoval, M.; Ben-Shlomo, A.

    1999-01-01

    Program in radiological equipment has incorporated more powerful x-ray sources into the standard Fluoroscopy and CT systems. Expanding use of interventional procedures carries extensive use of fluoroscopy and CT which are both associated with excessive radiation exposure to the patient and personnel. During cases of Intravenous CT Angiography and direct Intraarterial CT Angiography, one may substitute a substantial number of diagnostic angiography checks. Basic training in interventional radiology hardly includes some of the fundamentals of radiation protection. Radiation Protection in Interventional Radiology must be implemented in daily practice and become an integral part of procedure planning strategy in each and every case. Interventional radiological most master all modern imaging modalities in order to choose the most effective, but least hazardous one. In addition, one must be able to use various imaging techniques (Fluoroscopy, CTA, MM and US) as a stand-alone method, as well as combine two techniques or more. Training programs for fellows: K-based simulation of procedures and radiation protection. Special attention should be taken in the training institutions and a basic training in radiation protection is advised before the trainee is involved in the practical work. Amendment of techniques for balloon and stent deployment with minimal use of fluoroscopy. Attention to the differences between radiation protection in cardiovascular and nonvascular radiology with special measures that must be taken for each one of them (i.e., peripheral angiography vs. stenting, Endo luminal Aortic Stent Graft, or nonvascular procedures such as biliary or endo urological stenting or biliary intervention). A special emphasis should be put on the training techniques of Interventional Radiologists, both beginners and experienced. Patient dose monitoring by maintaining records of fluoroscopic time is better with non-reset timer, but is optional. Lee of automated systems that

  7. Radiological protection act, 1991

    International Nuclear Information System (INIS)

    1991-01-01

    This Act provides for the establishment of the Radiological Protection Institute of Ireland and dissolves An Bord Fuinnimh Nuicleigh (the Board), transferring its assets and liabilities to the Institute. It sets out a range of radiation protection measures to be taken by various Ministers in the event of a radiological emergency and gives effect at national level to the Assistance Convention, the Early Notification Convention and the Physical Protection Convention. The Institute is the competent Irish authority for the three Conventions. (NEA) [fr

  8. The future policy for radiological protection

    International Nuclear Information System (INIS)

    2003-01-01

    The international system of radiological protection is currently being revised with the aim of making it more coherent and concise. The International Commission on Radiological Protection (ICRP) has published its draft reflections on the system's evolution, and has opened discussions with the radiological protection community in order to seek a broad range of stakeholder input. This open dialogue will help bring about a common level of understanding of the issues at stake and contribute to the evolution of new ICRP recommendations. These proceedings present a significant block of stakeholder input, comprising the views of policy makers, regulators, radiological protection professionals, industry and representatives of both non-governmental and intergovernmental organisations. (author)

  9. Radiological protection aspects regarding to assistance of the cesium-137 radiation accident victims in Goiania

    International Nuclear Information System (INIS)

    Hunt, John Graham; Oliveira Filho, Denizart Silveira de; Rabelo, Paulo Ney Pamplona

    1997-01-01

    The radiological protection measures taken in the general hospital of Goiania (HGG/INAMPS) and in the FEBEM institution, due to the accident involving Cesium-137 are described, as well as the work of the IRD personnel in the areas of: radiological protection of the medical and auxiliary staff, contamination control of the ward, radiological monitoring of the patients, waste management, personnel and area decontamination and patient transportation. (author)

  10. White paper on radiological monitoring of workers exposures

    International Nuclear Information System (INIS)

    Shettle, Jennifer

    2016-01-01

    This article comments the content of a white paper which aimed at proposing new regulatory bases to update the French Code of Labour and other legal texts related to the radiation protection of workers. The author briefly comments the objectives of this white paper (to put the initial regulatory basis into question again), briefly describes the adopted approach, the new definition of risk related to ionizing radiations within the frame of a global approach to the prevention of occupational risks. She notices and comments the removal of a reference to an exposure limit for the public as input criterion in the system of radiological monitoring of workers exposures. She also comments the introduction of some concepts: the concept of a worker submitted to a risk related to ionizing radiation, and the concept of exposure value entailing a strengthened preventive action. She indicates the different modalities adopted for exposure monitoring (radiological monitoring and dose follow-up), addresses the issue of communication of dosimetry data and the access to all dosimetry information for the person in charge of radiation protection, and finally briefly evokes the idea of publishing guides for each specific sectors

  11. Radiological protection system in the era of nuclear renaissance expectation for development of radiological protection system

    International Nuclear Information System (INIS)

    Toyomatsu, Hideki

    2008-01-01

    The current radiological protection system, which was established mainly by the ICRP and UNSCEAR, has contributed to the prevention of potential radiological health hazards, and has been a fundamental concept during the development of nuclear energy. Through a detailed discussion regarding the new ICRP recommendations, the world nuclear industry has reached a consensus that the current radiological protection system keeps its integrity in principle although it involves some remaining issues, such as the disposal of radioactive waste. In order to maximize the advantages of nuclear energy while keeping the integrity of radiological protection system, it is essential to address the characteristics of radiation, which is specific to nuclear energy, so that nuclear energy can coexist with other energy sources. The three basic principles of radiological protection (i.e., justification, optimization and dose limits), which were completed in the 1990 recommendations of ICRP, should be retained as the basic concepts for the future radiological protection system in order to maintain the continuity and consistency of the radiological protection system. The radiological protection system can be furthermore developed only by combining the above three principles with best practices extracted from utilities' field experience. The significant reduction of radiation exposures received by members of the public and radiation workers in the field has resulted from the efforts by the world utilities to achieve the optimization. In order to correctly apply the theory to the work practices, it is essential to see how the theory is practically used in the field. Such a process should be also emphasized in the revision work of the IAEA Basic Safety Standards (BSS), which is currently under progress. Integrating the theory in the work practices is the key to the true development of nuclear renaissance, which could lead to the establishment of the nuclear safety regime. (author)

  12. Science and values in radiological protection: impact on radiological protection decision making

    International Nuclear Information System (INIS)

    Salomaa, Sisko; Pinak, Miroslav

    2008-01-01

    Full text: This work summarises the main ideas and achievements of the Science and Values in Radiological Protection Workshop that was held on 15-17 January 2008 in Helsinki, Finland. In the view of developing of new radiological applications and emerging scientific phenomena it has been recognized a need to develop a shared understanding of emerging challenges for radiological protection among scientific and regulatory communities, public and other concerned stake holders. In response to this the Committee of Radiation Protection and Public Health of the OECD Nuclear Energy Agency and Radiation and Nuclear Safety Authority of Finland tried to initiate a process of longer-term reflection on scientific and societal issues that might challenge radiological protection in the coming years. Among general issues like radiological policy issues, improvement of understanding between research and policy communities, sharing views on emerging scientific issues, there were addressed several scientific issues, like non-targeted effects, individual sensitivity; and circulatory diseases. The main focus of these discussions was to elaborate potential 'what if' scenarios and propose feasible solutions at various levels. These discussions addressed effects that are not direct and evident consequence of the initial lesions produced at the cellular and DNA level like bystander responses, genomic instability, gene induction, adaptive responses and low dose. Particular interest was paid to an extrapolation of risk estimates to low doses and role of Linear Non-Threshold theory in setting regulatory principles. Individual radio-sensitivity and identification of genes that are suspected of having an influence on it were also discussed in one of the Breakout Sessions. Another Breakout Session addressed circulatory diseases. There is emerging evidence in the A-bomb survivors and in other exposed groups that ionising radiation also causes other diseases than cancer, such as circulatory

  13. Radiological protection report 2016

    International Nuclear Information System (INIS)

    2017-06-01

    on the basis of international recommendations. ENSI uses inspections and comparative measurements to ensure that the necessary calibrated radiological protection measurement equipment is available and that it is used for its intended purpose in order to determine correct values. For this purpose, it operates a test centre accredited to ISO 17025. The network operated by ENSI for automatically monitoring the dose rate in the vicinity of nuclear power plants measures dose rates in the vicinity of nuclear power stations all year round and 24 hours a day. The 10-minute, hourly and daily mean rates measured can be viewed on ENSI's web site in real time. This monitoring network serves to secure evidence for the authorities and in dealings with the public. No local increases in dose rates that could be attributed to discharges from nuclear power plants were detected in the reporting year. Sporadic, locally high measurements are due to fluctuations in natural background radiation, e.g. after rainfall. The programme JRODOS (Java-based Realtime Online DecisiOn Support system) has been used since the beginning of 2016 to model atmospheric spread and calculate the dose, should an event occur. JRODOS allows the direct use of 3D weather forecast data from the COSMO-1 model routinely used by MeteoSwiss with a grid size of 1 km. The COSMO-1 model supplies forecasts stretching up to 24 hours into the future with high spatial and temporal resolution. In order to reflect the small scale structure of the Swiss countryside and that of southern Germany, JRODOS uses the very high resolution elevation model from the Swiss Federal Office of Topography. This means that together with the aerial radiometric equipment, there are invaluable, precise instruments available at all times for making current assessments (diagnoses) as well as forecasts of the radiological situation. In the reporting year, all thresholds contained in the Federal Ordinance on radiation protection were met. There

  14. Routine Radiological Environmental Monitoring Plan

    International Nuclear Information System (INIS)

    Bechtel Nevada

    1998-01-01

    The U.S. Department of Energy manages the Nevada Test Site in a manner that meets evolving DOE Missions and responds to the concerns of affected and interested individuals and agencies. This Routine Radiological Monitoring Plan addressess complicance with DOE Orders 5400.1 and 5400.5 and other drivers requiring routine effluent monitoring and environmental surveillance on the Nevada Test Site. This monitoring plan, prepared in 1998, addresses the activities conducted onsite NTS under the Final Environmental Impact Statement and Record of Decision. This radiological monitoring plan, prepared on behalf of the Nevada Test Site Landlord, brings together sitewide environmental surveillance; site-specific effluent monitoring; and operational monitoring conducted by various missions, programs, and projects on the NTS. The plan provides an approach to identifying and conducting routine radiological monitoring at the NTS, based on integrated technical, scientific, and regulatory complicance data needs

  15. Web-based system for radiological protection programs: a repository for research, consultation and information

    Energy Technology Data Exchange (ETDEWEB)

    Levy, Denise S.; Sordi, Gian Maria A.A., E-mail: gmsordi@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2014-07-01

    In order to establish a Radiation Protection Plan or a Radiation Emergency Plan, Brazilian facilities should take into account all procedures based on national and international guidelines and recommendations. This information can be found in several documents published by different organizations over the past decades: the International Commission on Radiological Protection (ICRP), International Atomic Energy Agency (IAEA) and Comissao Nacional de Energia Nuclear (CNEN). Therefore, this project aims the informatization of the radiological protection programs in a single system in order to offer unified programs and inter-related information in Portuguese, providing Brazilian facilities a complete repository for research, consultation and information, combining computer technology and radiological protection in order to enhance the best benefits from information technology. This research work includes programs about: (1) Monitoring of Workplace (Monitoring for External Radiation, Monitoring for Surface Contamination, Monitoring for Air Contamination) and (2) Individual Monitoring (Monitoring of External Exposure and Monitoring of Internal Exposure, Monitoring for Skin and Clothing). WEB platform tools and functionalities were developed according to target public needs, regarding new possibilities of media, mobile access, and information sharing. The servers processing power added to the technology of relational databases allow to integrate information from different sources, enabling complex queries with reduced response time. Moreover, taking into account this is a pioneer project with the prospect of long-term use, the challenge involves the combination of multiple computer technologies that allows a robust, effective and flexible system, which can be easily adapted to future technological innovations. (author)

  16. Web-based system for radiological protection programs: a repository for research, consultation and information

    International Nuclear Information System (INIS)

    Levy, Denise S.; Sordi, Gian Maria A.A.

    2014-01-01

    In order to establish a Radiation Protection Plan or a Radiation Emergency Plan, Brazilian facilities should take into account all procedures based on national and international guidelines and recommendations. This information can be found in several documents published by different organizations over the past decades: the International Commission on Radiological Protection (ICRP), International Atomic Energy Agency (IAEA) and Comissao Nacional de Energia Nuclear (CNEN). Therefore, this project aims the informatization of the radiological protection programs in a single system in order to offer unified programs and inter-related information in Portuguese, providing Brazilian facilities a complete repository for research, consultation and information, combining computer technology and radiological protection in order to enhance the best benefits from information technology. This research work includes programs about: (1) Monitoring of Workplace (Monitoring for External Radiation, Monitoring for Surface Contamination, Monitoring for Air Contamination) and (2) Individual Monitoring (Monitoring of External Exposure and Monitoring of Internal Exposure, Monitoring for Skin and Clothing). WEB platform tools and functionalities were developed according to target public needs, regarding new possibilities of media, mobile access, and information sharing. The servers processing power added to the technology of relational databases allow to integrate information from different sources, enabling complex queries with reduced response time. Moreover, taking into account this is a pioneer project with the prospect of long-term use, the challenge involves the combination of multiple computer technologies that allows a robust, effective and flexible system, which can be easily adapted to future technological innovations. (author)

  17. Radiation protection and monitoring

    International Nuclear Information System (INIS)

    Bruecher, L.; Langmueller, G.; Tuerschmann, G.

    1997-01-01

    The safety, the quality and efficiency of the radiological monitoring systems for block one and two of the NPP Mochovce, designed and delivered by the general designer, should be increased by EUCOM Siemens. Modern, accident resistant and/or more powerful monitoring systems have been designed by Siemens will be added to the existing systems. To achieve this radiation measuring units will be installed inside the hermetic zone, in the reactor hall, at the stack, at the release water system and in the environment in the vicinity of the NPP. The presentation, the storage distribution and the processing of all measuring results also will be optimised by installing a modern high-performance computer system, the so-called Central Radiological Computer System 'CRCS', featuring a high availability. The components will be installed in the relevant control rooms all over the plant. With this computer system it is easy to control the radiation level inside and outside the NPP during normal operation and during and after an accident. Special programs, developed by Siemens support the staff by interpreting the consequences of radioactive releases into the environment and by initiating protection procedures during and after an accident. All functions of the system are available for emergency protection drills and training the staff interruption of the normal control procedure. For the personal protection a digital personal dosimetry system completely considering with the requirements of ICRP 60 and several contamination monitors will be installed. (authors)

  18. Hanford Radiological Protection Support Services Annual Report for 2000

    Energy Technology Data Exchange (ETDEWEB)

    Lynch, Timothy P.; Bihl, Donald E.; Johnson, Michelle L.; Maclellan, Jay A.; Piper, Roman K.

    2001-05-07

    During calendar year 2000, the Pacific Northwest National Laboratory performed its customary radiological protection support services in support of the U.S. Department of Energy Richland Operations Office and the Hanford contractors. These services included: 1) external dosimetry, 2) internal dosimetry, 3) in vivo monitoring, 4) radiological records, 5) instrument calibration and evaluation, and 6) calibration of radiation sources traceable to the National Institute of Standards and Technology. Each program summary describes the routine operations, program changes and improvements, program assessments, supporting technical studies, and professional activities.

  19. Radiological assessments, environmental monitoring, and study design

    International Nuclear Information System (INIS)

    Hansen, W.R.; Elle, D.R.

    1980-01-01

    Studies of the behavior of transuranic elements in the environment form the basic data for applied programs in radiological assessment, environmental monitoring, derivation of radiation-protection standards, and environmental impact statements. This chapter introduces some of the major information requirements of these applications of transuranic research data. Characteristics of the source terms from nuclear activities usually are needed for an analysis of environmental pathways or deployment of monitoring systems. Major inhalation and ingestion pathways are considered in assessments of hazards from transuranics and are discussed from the viewpoint of research needed

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

    International Nuclear Information System (INIS)

    Thome, D.J.

    2000-01-01

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

  1. Training on Radiological Protection in Peru

    International Nuclear Information System (INIS)

    Medina Gironzini, E.

    2004-01-01

    Since they were created in 1973 and 1988 respectively, the Superior Center of Nuclear Studies (CSEN) of the Peruvian Institute of Nuclear Energy (IPEN), together with the Peruvian Radioprotection Society (SPR) have carried out different training courses on radiological protection so that people can work safely with ionizing radiations in medicine, industry and investigation. Additionally, radiological protection is taught to pre graduate students of Medical Technology in four Universities. These courses are a must since national regulations demand that people working with ionizing radiations have an authorization, which is granted by the Technical Office of the National Authority - the technical organ of IPEN - after the candidate demonstrates that he or she knows the specific use of the technique using radiations, as well as all aspects related to safety and radiological protection. The analysis of the radiological protection programs is presented in this document. These programs were carried out by CSEN, during the last 30 years, and by the SRP, and they allowed the training of more than 2200 and 1500 people in the country, respectively. The content of both courses is aimed at specific work with radiations (diagnostic radiology, dental radiology, nuclear medicine, radiotherapy, industrial radiography, nuclear gauges, gamma irradiator, etc..) and fulfill the regulatory requirements. The Universities have different programs on radiological protection for the students of Medical Technology. (Author)

  2. The future policy for radiological protection

    International Nuclear Information System (INIS)

    2004-01-01

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

  3. Aspects of radiation protection to attend the victims of radiological accident with cesium 137 in Goiania

    International Nuclear Information System (INIS)

    Hunt, J.G.; Oliveira Filho, D.S. de; Rabello, P.N.P.

    1988-01-01

    The radiological protection measures taken in the general hospital of Goiania (HGG/INAMPS) and in the FEBEM institution, due do the accident involving cesium 137 are described, as well the work of the NUCLEI personnel in the areas of: radiological protection of the medical and auxiliary staff, contamination control of the ward, radiological monitoring of the patients, waste management, personnel and area decontamination and patient transportation. (author) [pt

  4. Radiologic protection in intensive therapy units

    International Nuclear Information System (INIS)

    Andrea, H.; Juliana, C.; Gerusa, R.; Laurete, M.B.; Suelen, S.; Derech, Rodrigo D.A.

    2013-01-01

    The discovery of X-ray was a great achievement for humanity, especially for the medical community. In Intensive Care Units (ICUs), the RX tests, performed with mobile devices, add immense value to the diagnosis of inpatients who do not have the option to carry them out of bed. Following the technology and its improvements, fatalities arose from misuse of ionizing radiation, which mostly gave up for lack of knowledge of the biological effects caused by them, which leads to fear among professionals and often prevents a quick job and effectively by professionals of radiological techniques. The research it is a systematic review of the literature and justified by the scarcity of materials that reflect on the radiological protection in ICUs. For this study we found the Virtual Health Library (VHL) and Pubmed were indexed terms radiological protection and intensive care units, the search in Portuguese and English terms were used radiological protection and intensive care unit. The study aims to inform professionals of ICUs on the main aspects that refer to X-rays in hospital beds, the standards of radiological protection and personal protective equipment, thus avoiding possible damage to the biological health of workers, addressing subjects in rules and laws about the X radiation, emphasizing the protection of professionals in intensive care. It is clear, finally, that little research is conducted in the context of radiological protection of workers ICU's and this is a place that receives daily RX equipment, deserving more attention to protect the worker. (author)

  5. Radiological protection report 2014; Strahlenschutzbericht 2014

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2015-06-15

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

  6. Radiation protection in pediatric radiology

    International Nuclear Information System (INIS)

    Fendel, H.; Stieve, F.E.

    1983-01-01

    Because of the high growth rate of cell systems in phases of radiation exposure radiological investigations on children should not be considered unless there is a strong indication. The National Council on Radiation Protection and Measurements has worked out recommendations on radiation protection which have been published as an NCRP report. This report is most important even outside the USA. The present translation is aimed to contribute to better understanding of the bases and aims of radiation protection during radiological investigations on children. It addresses not only those physicians who carry out radiological investigations on children themselves but also all physicians requiring such investigations. For these physicians, but also for parents who are worried about the radiation risk to their children the report should be a useful source of information and decision aid ensuring, on the one hand, that necessary radiological investigations are not shunned for unjustified fear of radiation and that, on the other hand, all unnecessary exposure of children to radiation is avoided. Thus, it is to be hoped, the quality of pediatric radiological diagnostics will be improved. (orig./MG) [de

  7. Protective effect of lead aprons in medical radiology

    International Nuclear Information System (INIS)

    Huyskens, C.J.

    1995-01-01

    This article summarizes the results of an ongoing study regarding the protective effect that lead aprons, as used in medical radiology, have on the resulting effective dose for medical personnel. By means of model calculations we have analyzed the protection efficacy of lead aprons for various lead thicknesses, in function of tube potential and of variations in exposure geometry as they occur in practice. The degree of efficacy appears to be highly dependent on the fit of aprons because of the dominating influence of the equivalent dose of partially unshielded organs on the resulting effective dose. Also by model calculations we investigated the ratio between the effective dose and the operational quantify for personal dose monitoring. Our study enables the choice of appropriate correction factors for convering personal dosimetry measurements into effective dose, for typical exposure situations in medical radiology. (orig.) [de

  8. Radiological protection in medical facilities and applications and around accelerator facilities

    International Nuclear Information System (INIS)

    Reiners, C.; Harder, D.; Messerschmidt, O.

    1992-01-01

    The proceedings of the meeting of radiation protection experts present the invited papers, of which 37 have been analysed and indexed for retrieval from the database. The papers discuss a broad spectrum of topics in the field of radiologic safety, as e.g. the fundamentals of assessing the effects of low-level ionizing radiation, new releases of international recommendations, the legal basis of activities for an optimization of radiological protection, including the tasks of the radiation protection officers, and recent developments in dose monitoring and measurement. There are papers dealing with topical aspects of radiation protection around accelerators for radiotherapy or radionuclide production, and at accelerators in research and industry. Experts in the field of diagnostic X-ray examination present the latest knowledge contributing to minimizing the radiation exposure from conventional or from novel, digital examination techniques, and recent developments in the field of quality assurance. In connection with the handling of unsealed radioactive materials, there are some papers discussing the monitoring and limits of intakes of radionuclides by workers. (orig./HP) With 124 figs., 72 tabs [de

  9. The regulation of the radiological protection in Mexico

    International Nuclear Information System (INIS)

    Eibenschutz H, J.

    2008-12-01

    The regulation antecedents in nuclear question in Mexico are placed in 1950, with the promulgation of L aw that declares national mining reserves the uranium deposits, thorium and the other substances of which obtains fissionable isotopes that can produce nuclear energy , instrument that stipulated the control of uranium, thorium, as to its it indicated it name, and other fissionable substances, on the part of the state, although they were without a doubt the respective institutions, the National Commission of Nuclear Energy in 1955, and the one of the National Commission of Nuclear Safety and Safeguards (CNSNS) in 1979, those that allowed the development of a prescribed frame in the nuclear and radiological areas. One characteristic of the regulation in radiological protection is the variety in the authorities type that have incidence in the regulation, as a result of the different approaches with which it can be approached. For example, in Mexico normative instruments with content in radiological protection exist and are watched over the Health Secretary, who is oriented to the protection of the patient, their relatives and the medical body; Work and Social Welfare Secretary, with a labor approach; Communications and Transport Secretary, which regulates the transport of nuclear and radioactive materials; Finance and Public Credit Secretary, who regulates the import and export of radioactive materials; Environment and Natural Resources Secretary, which regulates the environment protection; Energy Secretary who has responsibilities inside of the p rescribed law of article 27 constitutional in nuclear matter ; and within the energy sector, the CNSNS that expedite and watch the fulfillment of normative in radiological protection and nuclear safety. In order to resist effects of on regulation; frequently inter institutional agreements are carried out in which the areas of monitoring are agreed by each authority. The regulation in radiological protection demands the

  10. Perception of radiological technicians on radiation protection

    International Nuclear Information System (INIS)

    Viana, E.; Borges, L.M.; Camozzato, T.S.C.

    2017-01-01

    The objective of this study was to know the professionals' perception of radiological techniques about radiation protection in the work process in Nuclear Medicine. The research was carried out with nine professionals of the radiological techniques of two private institutions located in the South of Brazil. An interview was applied through recording and transcription. The analysis of the data took place through a thematic analysis. The professionals' perception of radiological techniques regarding the radiological protection in the work process is evidenced when professionals mention the basic rules of radiation protection: time, shielding and distance as attitudes used to minimize the exposure to ionizing radiation. However, it was verified the fragility in the knowledge about the norms and legislation of the radiological protection

  11. Worker radiological protection: occupational medical aspects

    International Nuclear Information System (INIS)

    Cardenas Herrera, Juan; Fernandez Gomez, Isis Maria

    2008-01-01

    Radiation exposures experienced by workers are widely explained. The first evidences of biological effects, the implications for human health and the radiological protection have been covered. The conceptual structure that covers the radiological protection and adequate protection without limiting benefits, the scientific basis of radiology, the benefits and risks of the radiological protection are specified. The effective per capita doses are exposed in medical uses both for Latin America and for other regions in the average radiology, dental radiology, nuclear medicine and radiotherapy. The manners of occupational exposures in the medicine are presented. Industrial uses have also its average effective dose in the industrial irradiation, industrial radiography and radioisotopes production. Within the natural radiation the natural sources can significantly contribute to occupational exposure and have their average effective dose. Occupational medical surveillance to be taken into industrial sites is detailed. In addition, the plan of international action for the solution of dilemmas of occupational exposures is mentioned and the different dilemmas of radioactive exposure are showed. The external irradiation, the acute diseases by radiations, the cutaneous syndrome of the chronic radiation, the radioactive contamination, the internal radioactive contamination, the combined lesion and accidental exposures are also treated [es

  12. The application of geographic information system to radiological and nuclear emergency monitoring

    International Nuclear Information System (INIS)

    Sadaniowski, I.V.; Rodriguez, M.; Rojas, C.A.; Jordan, O.D.

    2010-01-01

    The Geographic Information System (GIS) implementation for the preparation and response in case of to radiological and nuclear emergencies is being developed in the Emergency Control Center of the Argentina Nuclear Regulatory Authority, since many years ago. Additionals features have been incorporated such as integration with the results of radiological monitoring, improving and expanding its benefits both in the preparation stage and during the work of emergency response. This paper shows the specific application of GIS to radiological monitoring in case of emergency situations such as during the search of orphan sources and the characterization of geographic context around nuclear power plants and atomic centers. The GIS provides essential data cartographic for the monitoring with sophisticated detectors, to integrate with the information received with infrastructure, urban and rural population maps, physical features of the place, satellite images, etc. The monitoring results are analyzed and compared with relevant information for decision making during the response, like evacuation routes, affected population, security forces in the area, radiological characterization, application of protective actions, hospitals, schools, etc. These two integrated tools improve preparedness and response system in case of radiological or nuclear emergency. (authors) [es

  13. Principles to establish a culture of the radiological protection

    International Nuclear Information System (INIS)

    Tovar M, V. M.

    2013-10-01

    The term of Culture of the Radiological Protection means the way in which the radiological protection is founded, regulated, managed, preserved and perceived in the job places, with the use of the ionizing radiations, in the industry, in medicine and in any daily activity that reflects the activities, beliefs, perceptions, goals and values that all the involved parts concern in relation to the radiological protection. The principles to establish a culture of the radiological protection that should be established by the professionals of the radiological protection, following the recommendations of the International Radiological Protection Association (IRPA) are presented. (author)

  14. Skin dosimetry - radiological protection aspects of skin dosimetry

    International Nuclear Information System (INIS)

    Dennis, J.A.

    1991-01-01

    Following a Workshop in Skin Dosimetry, a summary of the radiological protection aspects is given. Aspects discussed include routine skin monitoring and dose limits, the need for careful skin dosimetry in high accidental exposures, techniques for assessing skin dose at all relevant depths and the specification of dose quantities to be measured by personal dosemeters and the appropriate methods to be used in their calibration. (UK)

  15. Training in radiological protection: Curricula and programming

    International Nuclear Information System (INIS)

    1964-01-01

    An important activity of the International Atomic Energy Agency is the promotion of training in radiological protection. Through its organized training courses, its fellowship training programme and its field experts, the Agency has assisted many Member States to train an essential group of scientists in radiological protection. Many Member States are now developing their own national training programmes in radiological protection and this report has been prepared to provide the guidance that may be required in this development. In the report the various types of training which are encountered in a radiological protection programme are fully discussed, curricula are suggested and examples of established training courses are annexed

  16. Proceedings of the Session of Radiological Protection in Medicine

    International Nuclear Information System (INIS)

    2016-01-01

    The Argentine Society for Radiation Protection has organized the Radiological Protection Session in Medicine 2016 in order to continue with the radiological update on specific radiological topics in radiology, nuclear medicine and interventional medicine, as well as to optimize the radiological protection of workers, patients and the public. [es

  17. Radiological Protection Miscellaneous Provisions Act 2014

    International Nuclear Information System (INIS)

    Irish Legislation

    2014-07-01

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

  18. Strengthening the scientific basis of radiological protection

    International Nuclear Information System (INIS)

    Lazo, Edward

    2016-01-01

    The overarching objective of the radiological protection system is to contribute to an appropriate level of protection against the harmful effects of radiation exposure, without unjustifiably limiting the desired results from the human activity causing exposure. Such a balance is achieved by understanding as best as possible the scientific characteristics of radiation exposure and the related health effects, and by taking this knowledge into consideration when judging which protection decisions will ensure the best balance between social and economic aspects and risks. In general, the existing radiological protection system, on which national regulations are built in virtually every country in the world, works well and does not underestimate protection needs for either individuals or exposed populations as a whole. The latest International Commission on Radiological Protection (ICRP) recommendations, which define this protection system, were formed after a long and open dialogue with the public, where expert views were actively collected and discussed at national, regional and international levels. Although the radiological protection system is very effective, and there is no current need for a prompt revision, it is important nonetheless to keep a watchful eye on the latest scientific results, and to work to ensure that the entire radiological protection community is kept up to date on evolving and emerging scientific issues. In this way, potential or actual scientific changes can be appropriately identified and in turn can stimulate reflection on changes that might be needed in the protection system, in policy, in regulation and in practice. Such reflection should benefit from the input of other scientific disciplines and interested stakeholders. To contribute to this process, the NEA Committee on Radiological Protection and Public Health (CRPPH) has periodically reviewed and released reports on the state of the art in radiological protection science (see NEA

  19. Evolution of the system of radiological protection

    International Nuclear Information System (INIS)

    2004-01-01

    The development of new radiological protection recommendations by the International Commission on Radiological Protection (ICRP) continues to be a strategically important undertaking, both nationally and internationally. With the growing recognition of the importance of stakeholder aspects in radiological protection decision making, regional and cultural aspects have also emerged as having potentially significant influence on how protection of the public, workers and the environment are viewed. Differing cultural aspects should therefore be considered by the ICRP in its development of new recommendations. Based on this assumption, the NEA organised the Asian Regional Conference on the Evolution of the System of Radiological Protection to express and explore views from the Far East. Held in Tokyo on 24-25 October 2002, the conference included presentations by the ICRP Chair as well as by radiological protection experts from Japan, the Republic of Korea, China and Australia. The distinct views and needs of these countries were discussed in the context of their regional and cultural heritages. These views, along with a summary of the conference results, are presented in these proceedings. (author)

  20. Radiological protection issues arising during and after the Fukushima nuclear reactor accident

    International Nuclear Information System (INIS)

    González, Abel J; Akashi, Makoto; Sakai, Kazuo; Yonekura, Yoshiharu; Boice Jr, John D; Chino, Masamichi; Homma, Toshimitsu; Ishigure, Nobuhito; Kai, Michiaki; Kusumi, Shizuyo; Lee, Jai-Ki; Menzel, Hans-Georg; Niwa, Ohtsura; Yamashita, Shunichi; Weiss, Wolfgang

    2013-01-01

    Following the Fukushima accident, the International Commission on Radiological Protection (ICRP) convened a task group to compile lessons learned from the nuclear reactor accident at the Fukushima Daiichi nuclear power plant in Japan, with respect to the ICRP system of radiological protection. In this memorandum the members of the task group express their personal views on issues arising during and after the accident, without explicit endorsement of or approval by the ICRP. While the affected people were largely protected against radiation exposure and no one incurred a lethal dose of radiation (or a dose sufficiently large to cause radiation sickness), many radiological protection questions were raised. The following issues were identified: inferring radiation risks (and the misunderstanding of nominal risk coefficients); attributing radiation effects from low dose exposures; quantifying radiation exposure; assessing the importance of internal exposures; managing emergency crises; protecting rescuers and volunteers; responding with medical aid; justifying necessary but disruptive protective actions; transiting from an emergency to an existing situation; rehabilitating evacuated areas; restricting individual doses of members of the public; caring for infants and children; categorising public exposures due to an accident; considering pregnant women and their foetuses and embryos; monitoring public protection; dealing with ‘contamination’ of territories, rubble and residues and consumer products; recognising the importance of psychological consequences; and fostering the sharing of information. Relevant ICRP Recommendations were scrutinised, lessons were collected and suggestions were compiled. It was concluded that the radiological protection community has an ethical duty to learn from the lessons of Fukushima and resolve any identified challenges. Before another large accident occurs, it should be ensured that inter alia: radiation risk coefficients of

  1. Radiological protection issues arising during and after the Fukushima nuclear reactor accident.

    Science.gov (United States)

    González, Abel J; Akashi, Makoto; Boice, John D; Chino, Masamichi; Homma, Toshimitsu; Ishigure, Nobuhito; Kai, Michiaki; Kusumi, Shizuyo; Lee, Jai-Ki; Menzel, Hans-Georg; Niwa, Ohtsura; Sakai, Kazuo; Weiss, Wolfgang; Yamashita, Shunichi; Yonekura, Yoshiharu

    2013-09-01

    Following the Fukushima accident, the International Commission on Radiological Protection (ICRP) convened a task group to compile lessons learned from the nuclear reactor accident at the Fukushima Daiichi nuclear power plant in Japan, with respect to the ICRP system of radiological protection. In this memorandum the members of the task group express their personal views on issues arising during and after the accident, without explicit endorsement of or approval by the ICRP. While the affected people were largely protected against radiation exposure and no one incurred a lethal dose of radiation (or a dose sufficiently large to cause radiation sickness), many radiological protection questions were raised. The following issues were identified: inferring radiation risks (and the misunderstanding of nominal risk coefficients); attributing radiation effects from low dose exposures; quantifying radiation exposure; assessing the importance of internal exposures; managing emergency crises; protecting rescuers and volunteers; responding with medical aid; justifying necessary but disruptive protective actions; transiting from an emergency to an existing situation; rehabilitating evacuated areas; restricting individual doses of members of the public; caring for infants and children; categorising public exposures due to an accident; considering pregnant women and their foetuses and embryos; monitoring public protection; dealing with 'contamination' of territories, rubble and residues and consumer products; recognising the importance of psychological consequences; and fostering the sharing of information. Relevant ICRP Recommendations were scrutinised, lessons were collected and suggestions were compiled. It was concluded that the radiological protection community has an ethical duty to learn from the lessons of Fukushima and resolve any identified challenges. Before another large accident occurs, it should be ensured that inter alia: radiation risk coefficients of potential

  2. Advanced radiological protection course 1993: 15 November - 3 December

    International Nuclear Information System (INIS)

    1993-01-01

    This pamphlet describes an advanced radiological protection course organised by the NRPB and aimed at experienced health physicists and others who have worked in radiological protection for some years. A knowledge of basic radiological protection is assumed. The course concentrates on developing awareness of the policies and philosophy upon which radiological protection is based. Emphasis is given to managerial and professional responsibilities in radiological protection and to involvement with problems of industrial and public relations. The 1994 course is 3 - 21st October. (Author)

  3. Calibration of instrument and personnel monitoring in radiological protection

    International Nuclear Information System (INIS)

    Abdul Aziz Mohamad Ramli; Wan Saffiey Wan Abdullah

    1987-01-01

    It is difficult to choose radioprotection equipments that are not too expensive and suit the purpose. Some of the dosimetric characteristics of good dosemeters outlined by ISO 4071-1978 (E) namely scale linearity, energy dependence, radiation quality dependence and angular dependence for some of the commercially available dosemeters are discussed. The calibration procedures practised at the National Secondary Standard Dosimetry Laboratory (SSDL), of the Nuclear Energy Unit (NEU) is also explained. The radiological equipments for personnel monitoring such as film badge and TLD are widely used to estimate the radiation dose delivered to the whole or partial body of a personnel. Both of the personnel monitoring procedures have been established at the NEU. The objective, use and maintenance of the devices are also discussed in detail. The evaluation of the monthly dose received by a personnel from various establishments in the country are also presented. (author). 17 figs

  4. The Society for Radiological Protection - 40 years on from 1963

    International Nuclear Information System (INIS)

    Dunster, H John

    2003-01-01

    The Society for Radiological Protection was created in 1963 at a time when the structure of radiological protection in the United Kingdom was already well established. From its creation 40 years ago to the present, most of the features of British radiological protection stem from the recommendations of the International Commission on Radiological Protection. This review of the development of radiological protection has been produced to celebrate the 40 years of the Society's support of radiological protection, both in the United Kingdom and internationally. (review)

  5. Continuing training in radiological protection as an effective means of avoiding radiological accidents

    International Nuclear Information System (INIS)

    Lima, C.M.A.; Pelegrineli, S.Q.; Martins, G.; Lima, A.R.; Silva, F.C.A. da

    2017-01-01

    it is notorious that one of the main causes of radiological accidents is the lack of knowledge of radiological protection of workers. In order to meet the needs of professionals in acquiring a solid base in radiological protection and safety, was created in 2013, by the Casa Branca School / SP and technically supported by the company MAXIM Cursos, the 'Post-Graduation Course Lato Sensu de Radiological Protection in Medical, Industrial and Nuclear Applications', which offers a broad improvement in radiation protection. The course of 380 hours and duration of 18 months is divided into 13 modules, including theoretical classes, in person and online using the virtual classroom and practical training in radiation protection in general. In the end students should present a monograph, guided by a course teacher and reviewed by an Examining Bank. Five classes have been formed in these four years, totaling 92 students. In all, 51 monographs have been defended on topics of technical and scientific interest. For this, the Faculty consists of 25 professors, being 9 Doctors, 13 Masters and 3 Specialists in Radiological Protection

  6. Requirements to obtain the recognition of radiological protection experts

    International Nuclear Information System (INIS)

    Arguelles, R.; Villarroel, R.; Senderos, V.; Campos, R.; Pinos, M.; Ponjuan, G.; Franco, P.; Rueda, D.

    2003-01-01

    The scope of this paper is to summarize the general requirements related to education, training and skill of the individual to obtain the recognition of radiological protection experts on ionizing radiation (experts on radiological protection- RP). There has been established two levels according to the grade of responsibility: Qualified expert provided with a diploma given by de Nuclear Safety Council. Technician expert on radiological protection whose certification is made by the Qualified expert that supervise their work. To obtain the diploma of qualified expert is required an official degree, a title of Architecture, Engineering or equivalent in case of no national degrees; specific training on radiological protection (300 hours) and the knowledge on safety and radiological protection of the facilities to be supervised. Three years of experience on radiological protection must be proved. To get the recognition of technician expert on radiological protection is required Formacion Profesional de Grado Superior or equivalent and specific training on safety and radiological protection. Knowledge on basis and principles of radiological protection are required. According to the type of the facilities to be supervised there are two models: A model: to deal with facilities included in RD 1836/1999 (nuclear and radioactive facilities). B model: to deal with medical X rays facilities approved under RD 1891/1991 three months of experience on the selected model must be proved. (Author)

  7. National Radiological Protection Board accounts 1986-87

    International Nuclear Information System (INIS)

    1987-05-01

    The 1986-87 accounts of the Radiological Protection Board are presented in accordance with the Radiological Protection Act 1970. The report of the Comptroller and Auditor General is also given. (U.K.)

  8. National Radiological Protection Board accounts 1986-87

    Energy Technology Data Exchange (ETDEWEB)

    1987-01-01

    The 1986-87 accounts of the Radiological Protection Board are presented in accordance with the Radiological Protection Act 1970. The report of the Comptroller and Auditor General is also given. (U.K.).

  9. Proceedings of the 5. Regional congress on radiation protection and safety; 2. Iberian and Latin American Congress on Radiological Protection Societies; Regional IRPA Congress

    International Nuclear Information System (INIS)

    2001-01-01

    The Fifth Regional Congress on Radiation Protection and Nuclear Safety has been held in Recife (Brazil), from 29th April to 4th May 2001. The congress was hosted by the Brazilian Radiation Protection Society, under the joint sponsorship of FRALC and UFPE-DEN Department of Nuclear Energy. Its designation as a Regional IRPA Congress has been requested. The main purpose of the meeting was to bring together professionals from the industry, universities and research laboratories to present and discuss the latest research results, and to review the state of the art on applied and fundamental aspects of the radiation protection. These specialists have talked about nuclear safety and radiological protection, radiation natural exposure, biological effect of radiation, radiotherapy and medical radiological safety, radiological safety in industry and research. In their discussions, also were included subjects related to radiological safety of nuclear and radioactive facilities, radioactive waste management, radioactive material transport, environmental radiological monitoring program, radiological emergency and accidents, instruments and dosimetry, basic safety standards of protection against radiation

  10. Science and Values in Radiological Protection

    International Nuclear Information System (INIS)

    Lochard, J.; Eggermont, G.; Britt-Marie, Drottz Sjoberg; Tirmarche, M.; Geard, Ch.R.; Atkinson, M.; Murith, Ch.; Grant, K.G.; Luccioni, C.; Mays, C.; Sisko, Salomaa; Kelly, N.G.; Oughton, D.; Shannoun, F.; Grant, K.G.; Cooper, J.; Mays, C.; Weiss, V.; Oughton, D.; Kazuo, Sakai; Carroll, S.

    2010-01-01

    The workshop provides a forum for exchange of information and experience among regulators, scientists and governmental and non-governmental organisations in the areas of radiological protection and public health. This is the second in the series of NEA workshops on this subject. The first Science and Values in Radiological Protection workshop was held in Helsinki in January 2008 and hosted by the Radiation and Nuclear Safety Authority of Finland (STUK). The workshop focussed on developing a shared understanding between various stakeholders and identifying the elements of a framework more suited to the integration of new scientific and technological developments and socio-political considerations in radiological protection. This second workshop focusses on radiological protection issues that are currently facing us, and that continue to pose challenges to our world today. This document gathers the available slides of the presentations given at the workshop: - Science and Values in Radiological Protection: Towards a Framework (Jacques Lochard): This talk makes the link with the Science and Values in Radiological Protection workshop in Helsinki, and lay out the overall goals of the present workshop. It explains the format of plenary/break-out sessions. - Public Health Perspective in Radiological Protection in Challenging Topical Areas (Gilbert Eggermont): This talk gives more detail on the choice of the three case topics and the linkage to public health concerns in radiological protection. It makes a specific link with Helsinki workshop findings and the CRPPH Expert Group on the Public Health. Perspective in Radiological Protection work. - Civil Society Needs (Britt-Marie Drottz Sjoeberg): This talk briefly reviews the radiation protection concerns and communication needs of civil society. It points out different categories of stakeholders and their understanding of radiation risks implied by the three case topics. It addresses the question of how radiological

  11. Evolution of the radiological protection paradigms; Evolucao dos paradigmas de protecao radiologica

    Energy Technology Data Exchange (ETDEWEB)

    Sordi, Gian Maria A.A. [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil). Programa de Pos-Graduacao em Tecnologia Nuclear], E-mail: gmsordi@ipen.br

    2009-10-15

    We consider as initial radiological protection paradigms those in vigour after the release of the atomic energy for pacific usages in 1955. In that occasion, only one paradigm was introduced, presently named dose limitation system. After arguing about the basis that raised the paradigm, we introduced the guidance, that is, the measurements to be implemented to comply with the paradigm. In that occasion, they were two, i.e., the radiation dose monitoring and the workplace classification. Afterwards, the reasons that caused the radiological protection paradigms changes in force until 1995 are discussed. The initial paradigm was modified introducing the justification and the optimization principles, adding that the radiological protection should be economical and effective. The guidance also increased to four: personal monitoring, workplace classification, reference level and workers classification. Afterwards, we give the main justifications for the present paradigms that besides the formers were added the dose constraints, the potential exposure and the annual risk limits. Due to these modifications, the workers classifications were eliminated from the guidance, but the potential exposure and the search for the dose constraints were added. Eventually, we discuss the tendencies for the next future and the main changes introduced by the ICRP in the Publication 103, 2007. (author)

  12. Research and development in radiological protection

    International Nuclear Information System (INIS)

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

    2004-01-01

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

  13. Evolution of the system of radiological protection

    International Nuclear Information System (INIS)

    2005-11-01

    One of the main challenges facing radiological protection experts is how to integrate radiological protection within modern concepts of and approaches to risk governance. It is within this context that the International Commission on Radiological Protection (ICRP) decided to develop new general recommendations to replace its Publication 60 recommendations of 1990. In the process of developing these new recommendations, the views of the ICRP have evolved significantly, largely due to stakeholder involvement that has been actively solicited by the ICRP. In this regard, it was upheld during the First Asian Regional Conference organised by the NEA in October 2002 that the implementation of the new system must allow for regional, societal and cultural differences. In order to ensure appropriate consideration of these differences, the NEA organised the Second Asian Regional Conference on the Evolution of the System of Radiological Protection. Held in Tokyo on 28-29 July 2004, the conference included presentations by the ICRP Chair as well as by radiological experts from Australia, China, Japan and Korea. Within their specific cultural and socio-political milieu, Asia-Pacific and western ways of thought on how to improve the current system of radiological protection were presented and discussed. These ways of thinking, along with a summary of the conference results, are described in these proceedings. (author)

  14. Aspects of radiological protection in nuclear installations

    International Nuclear Information System (INIS)

    Hunt, J.G.; Oliveira Filho, D.S.; Rabello, P.N.P.

    1987-01-01

    Due to the short term, long term and genetic effects of radiation, the work with radioactive materials requires special protection measures. The objective of radiological protection is to assure the occupational health of the workers by maintaining the dose levels as low as reasonably achievable. The radiological protection measures implanted in the NUCLEBRAS fuel element factory are described. The philosophy and practical measures taken are explained, and a comparison between radiation protection and industrial safety norms is made. The result of this work shows that the radiological safety of the element factory is assured. (author) [pt

  15. Radiological Protection Plan an ethic responsibility

    International Nuclear Information System (INIS)

    Huhn, Andrea; Vargas, Mara Ambrosina de Oliveira

    2014-01-01

    The Radiological Protection Plan - PPR, quoted by the Regulatory Standard 32, requires to be maintained at the workplace and at the disposal of the worker's inspection the PPR, for it to be aware of their work environment and the damage that can be caused by misuse of ionizing radiation. Objective: to discuss the interface between PPR and ethical reflection. Method: this is a reflective study. Discussion and results: regulatory norm 32 points out that the worker who conducts activities in areas where there are sources of ionizing radiation should know the risks associated with their work. However, it is considered that the sectors of hospital radiology the multidisciplinary health team is exposed to ionizing radiation and has not always aware of the harm caused by it, so end up unprotected conduct their activities. Concomitantly, recent studies emphasize the radiological protection and concern for the dangers of radiation on humans, but rather refer to the legislation about the radiological protection. In this context an ethical reflection is necessary, seeking to combine work ethics liability to care in protecting themselves and the other with the institutional conditions for this protection becomes effective

  16. Radiological protection and its organization in radiotherapy

    International Nuclear Information System (INIS)

    Gaona, E.; Canizal, C.; Garcia, M.A.

    1996-01-01

    By means of a research carried out in Radiotherapy Centers in Mexico City, divided in 7 public institutions and 5 private, aspects related to the radiological safety and its organization in radiotherapy were evaluated. The population being studied was: medical and technical personnel, that works in the selected radiotherapy centers. The survey was made with 36 dichotomic variables, being obtained 90 surveys. The personnel characteristics are: 76% works for more than 3 years in radiotherapy, 93% has updated information about radiological protection, 67% knows the general radiological safety regulations, 93% knows the radiological emergency project and 95% makes use of personal dosemeter. As result of this research we found that the main problems that the radiological protection have are: lack of personnel training in radiological protection, although the 93% states to have updated information, the few number of persons that takes part in clinical meetings and professional associations. (authors). 7 refs., 3 tabs

  17. Model for the elaboration of program of environmental radiological monitoring reports

    International Nuclear Information System (INIS)

    2005-11-01

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

  18. Radiological protection report 2013; Strahlenschutzbericht 2013

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2014-06-15

    for the Swiss population as a whole of 5.5 mSv. The highest individual dose was below 11 mSv and affected one person. All doses received by persons professionally exposed to radiation and subject to ENSI surveillance were significantly less than the radiation limit. Increasing attention is being given to work in high and variable radiation fields and to those working in difficult conditions. ENSI has concluded that Swiss nuclear facilities continue to operate a consistent approach to radiological protection. Measuring equipment plays an extremely important role in radiological protection. Based on inspections and comparative measurements of aerosol and iodine filters and wastewater sampling together with measurements in the field of personal dosimetry, ENSI has concluded that the required calibrated measuring equipment for radiological protection exists, that this equipment is correctly used and provides reliable test data. For the purpose of monitoring environmental radioactivity, ENSI has operated a network that automatically monitors dose rates in the vicinity of nuclear power plants (MADUK). The results are made available to the Swiss National Emergency Operations Centre, the Ministry of the Environment in Baden-Wuerttemberg (Germany) and the European Radiological Data Exchange Platform (EURDEP). It is possible to deploy mobile lanthanum bromide detectors if MADUK registers an increase in dose rates. These detectors facilitate a gamma spectrum analysis in the event of a recorded increase. ENSI has maintained a test laboratory accredited under ISO 17025 that analyses samples from nuclear facilities and their immediate vicinity and also conducts field measurements. In the field of dispersion, hourly simulations are calculated based on current 3D wind precipitation fields as provided by MeteoSwiss with a spatial resolution of 2 km. These calculations, together with the annual aero-radiometric test flights, are a valuable and precise tool that can be used to analyse

  19. Virtual pilot course in radiological protection

    International Nuclear Information System (INIS)

    Gonzalez Romero, Angela Maria; Plazas, Maria Cristina

    2008-01-01

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

  20. [Regulating radiological protection and the role of health authorities].

    Science.gov (United States)

    Arias, César F

    2006-01-01

    This article summarizes the development of protection against ionizing radiation and explains current thinking in the field. It also looks at the decisive role that regulatory agencies for radiological protection must play and the important contributions that can be made by health authorities. The latter should take an active part in at least three aspects: the formal education of health personnel regarding radiological protection; the medical care of individuals who are accidentally overexposed, and the radiological protection of patients undergoing radiological procedures. To this end, health professionals must possess sufficient knowledge about radiological protection, promote the use of proper equipment, and apply the necessary quality assurance procedures. Through their effective intervention, national health authorities can greatly contribute to reducing unnecessary doses of radiation during medical procedures involving radiation sources and decrease the chances that radiological accidents will take place.

  1. History and Organizations for Radiological Protection.

    Science.gov (United States)

    Kang, Keon Wook

    2016-02-01

    International Commission on Radiological Protection (ICRP), an independent international organization established in 1925, develops, maintains, and elaborates radiological protection standards, legislation, and guidelines. United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR) provides scientific evidence. World Health Organization (WHO) and International Atomic Energy Agency (IAEA) utilise the ICRP recommendations to implement radiation protection in practice. Finally, radiation protection agencies in each country adopt the policies, and adapt them to each situation. In Korea, Nuclear Safety and Security Commission is the governmental body for nuclear safety regulation and Korea Institute of Nuclear Safety is a public organization for technical support and R&D in nuclear safety and radiation protection.

  2. Assessment of radiological protection systems among diagnostic radiology facilities in North East India.

    Science.gov (United States)

    Singh, Thokchom Dewan; Jayaraman, T; Arunkumar Sharma, B

    2017-03-01

    This study aims to assess the adequacy level of radiological protection systems available in the diagnostic radiology facilities located in three capital cities of North East (NE) India. It further attempts to understand, using a multi-disciplinary approach, how the safety codes/standards in diagnostic radiology framed by the Atomic Energy Regulatory Board (AERB) and the International Atomic Energy Agency (IAEA) to achieve adequate radiological protection in facilities, have been perceived, conceptualized, and applied accordingly in these facilities. About 30 diagnostic radiology facilities were randomly selected from three capitals of states in NE India; namely Imphal (Manipur), Shillong (Meghalaya) and Guwahati (Assam). A semi-structured questionnaire developed based on a multi-disciplinary approach was used for this study. It was observed that radiological practices undertaken in these facilities were not exactly in line with safety codes/standards in diagnostic radiology of the AERB and the IAEA. About 50% of the facilities had registered/licensed x-ray equipment with the AERB. More than 80% of the workers did not use radiation protective devices, although these devices were available in the facilities. About 85% of facilities had no institutional risk management system. About 70% of the facilities did not carry out periodic quality assurance testing of their x-ray equipment or surveys of radiation leakage around the x-ray room, and did not display radiation safety indicators in the x-ray rooms. Workers in these facilities exhibited low risk perception about the risks associated with these practices. The majority of diagnostic radiology facilities in NE India did not comply with the radiological safety codes/standards framed by the AERB and IAEA. The study found inadequate levels of radiological protection systems in the majority of facilities. This study suggests a need to establish firm measures that comply with the radiological safety codes/standards of the

  3. Routine Radiological Environmental Monitoring Plan. Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    Bechtel Nevada

    1999-12-31

    The U.S. Department of Energy manages the Nevada Test Site in a manner that meets evolving DOE Missions and responds to the concerns of affected and interested individuals and agencies. This Routine Radiological Monitoring Plan addressess complicance with DOE Orders 5400.1 and 5400.5 and other drivers requiring routine effluent monitoring and environmental surveillance on the Nevada Test Site. This monitoring plan, prepared in 1998, addresses the activities conducted onsite NTS under the Final Environmental Impact Statement and Record of Decision. This radiological monitoring plan, prepared on behalf of the Nevada Test Site Landlord, brings together sitewide environmental surveillance; site-specific effluent monitoring; and operational monitoring conducted by various missions, programs, and projects on the NTS. The plan provides an approach to identifying and conducting routine radiological monitoring at the NTS, based on integrated technical, scientific, and regulatory complicance data needs.

  4. Radiological protection report 2016; Strahlenschutzbericht 2016

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2017-06-15

    on the basis of international recommendations. ENSI uses inspections and comparative measurements to ensure that the necessary calibrated radiological protection measurement equipment is available and that it is used for its intended purpose in order to determine correct values. For this purpose, it operates a test centre accredited to ISO 17025. The network operated by ENSI for automatically monitoring the dose rate in the vicinity of nuclear power plants measures dose rates in the vicinity of nuclear power stations all year round and 24 hours a day. The 10-minute, hourly and daily mean rates measured can be viewed on ENSI's web site in real time. This monitoring network serves to secure evidence for the authorities and in dealings with the public. No local increases in dose rates that could be attributed to discharges from nuclear power plants were detected in the reporting year. Sporadic, locally high measurements are due to fluctuations in natural background radiation, e.g. after rainfall. The programme JRODOS (Java-based Realtime Online DecisiOn Support system) has been used since the beginning of 2016 to model atmospheric spread and calculate the dose, should an event occur. JRODOS allows the direct use of 3D weather forecast data from the COSMO-1 model routinely used by MeteoSwiss with a grid size of 1 km. The COSMO-1 model supplies forecasts stretching up to 24 hours into the future with high spatial and temporal resolution. In order to reflect the small scale structure of the Swiss countryside and that of southern Germany, JRODOS uses the very high resolution elevation model from the Swiss Federal Office of Topography. This means that together with the aerial radiometric equipment, there are invaluable, precise instruments available at all times for making current assessments (diagnoses) as well as forecasts of the radiological situation. In the reporting year, all thresholds contained in the Federal Ordinance on radiation protection were met. There

  5. ICRP PUBLICATION 121: Radiological Protection in Paediatric Diagnostic and Interventional Radiology

    International Nuclear Information System (INIS)

    Khong, P-L.; Ringertz, H.; Donoghue, V.; Frush, D.; Rehani, M.; Appelgate, K.; Sanchez, R.

    2013-01-01

    Paediatric patients have a higher average risk of developing cancer compared with adults receiving the same dose. The longer life expectancy in children allows more time for any harmful effects of radiation to manifest, and developing organs and tissues are more sensitive to the effects of radiation. This publication aims to provide guiding principles of radiological protection for referring clinicians and clinical staff performing diagnostic imaging and interventional procedures for paediatric patients. It begins with a brief description of the basic concepts of radiological protection, followed by the general aspects of radiological protection, including principles of justification and optimisation. Guidelines and suggestions for radiological protection in specific modalities – radiography and fluoroscopy, interventional radiology, and computed tomography – are subsequently covered in depth. The report concludes with a summary and recommendations. The importance of rigorous justification of radiological procedures is emphasised for every procedure involving ionising radiation, and the use of imaging modalities that are non-ionising should always be considered. The basic aim of optimisation of radiological protection is to adjust imaging parameters and institute protective measures such that the required image is obtained with the lowest possible dose of radiation, and that net benefit is maximised to maintain sufficient quality for diagnostic interpretation. Special consideration should be given to the availability of dose reduction measures when purchasing new imaging equipment for paediatric use. One of the unique aspects of paediatric imaging is with regards to the wide range in patient size (and weight), therefore requiring special attention to optimisation and modification of equipment, technique, and imaging parameters. Examples of good radiographic and fluoroscopic technique include attention to patient positioning, field size and adequate collimation

  6. Radiological monitoring plan for the Oak Ridge Y-12 Plant: Surface Water

    International Nuclear Information System (INIS)

    1997-10-01

    The Y-12 Plant conducts a surface water monitoring program in response to DOE Orders and state of Tennessee requirements under the National Pollutant Discharge Elimination System (NPDES). The anticipated codification of DOE Order 5400.5 for radiation protection of the public and the environment (10 CFR Part 834) will require an environmental radiation protection plan (ERPP). The NPDES permit issued by the state of Tennessee requires a radiological monitoring plan (RMP) for Y-12 Plant surface waters. In a May 4, 1995 memo, the state of Tennessee, Division of Water Pollution Control, stated their desired needs and goals regarding the content of RMPs, associated documentation, and data resulting from the RMPs required under the NPDES permitting system (L. Bunting, General Discussion, Radiological Monitoring Plans, Tennessee Division of Water Pollution Control, May 4,1995). Appendix A provides an overview of how the Y-12 Plant will begin to address these needs and goals. It provides a more complete, documented basis for the current Y-12 Plant surface water monitoring program and is intended to supplement documentation provided in the Annual Site Environmental Reports (ASERs), NPDES reports, Groundwater Quality Assessment Reports, and studies conducted under the Y-12 Plant Environmental Restoration (ER) Program. The purpose of this update to the Y-12 Plant RMP is to satisfy the requirements of the current NPDES permit, DOE Order 5400.5, and 10 CFR Part 834, as current proposed, by defining the radiological monitoring plan for surface water for the Y-12 Plant. This plan includes initial storm water monitoring and data analysis. Related activities such as sanitary sewer and sediment monitoring are also summarized. The plan discusses monitoring goals necessary to determine background concentrations of radionuclides, to quantify releases, determine trends, satisfy regulatory requirements, support consequence assessments, and meet requirements that releases be ''as low as

  7. [Radiation protection in interventional radiology].

    Science.gov (United States)

    Adamus, R; Loose, R; Wucherer, M; Uder, M; Galster, M

    2016-03-01

    The application of ionizing radiation in medicine seems to be a safe procedure for patients as well as for occupational exposition to personnel. The developments in interventional radiology with fluoroscopy and dose-intensive interventions require intensified radiation protection. It is recommended that all available tools should be used for this purpose. Besides the options for instruments, x‑ray protection at the intervention table must be intensively practiced with lead aprons and mounted lead glass. A special focus on eye protection to prevent cataracts is also recommended. The development of cataracts might no longer be deterministic, as confirmed by new data; therefore, the International Commission on Radiological Protection (ICRP) has lowered the threshold dose value for eyes from 150 mSv/year to 20 mSv/year. Measurements show that the new values can be achieved by applying all X‑ray protection measures plus lead-containing eyeglasses.

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-10-01

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

  9. Radiological protection in medicine: work of ICRP Committee 3

    International Nuclear Information System (INIS)

    Vañó, E.; Cosset, J.M.; Rehani, M.M.

    2012-01-01

    Committee 3 of the International Commission on Radiological Protection (ICRP) is concerned with protection in medicine, and develops recommendations and guidance on the protection of patients, staff, and the public against radiation exposure in medicine. This paper presents an overview of the work of Committee 3 over recent years, and the work in progress agreed at the last annual meeting in Bethesda, MD in October 2011. The reports published by ICRP dealing with radiological protection in medicine in the last 10 years cover topics on: education and training in radiological protection; preventing accidental exposures in radiation therapy; dose to patients from radiopharmaceuticals; radiation safety aspects of brachytherapy; release of patients after therapy with unsealed radionuclides; managing patient dose in digital radiology and computed tomography; avoidance of radiation injuries from medical interventional procedures; pregnancy and medical radiation; and diagnostic reference levels in medical imaging. Three new reports will be published in the coming months dealing with aspects of radiological protection in fluoroscopically guided procedures outside imaging departments; cardiology; and paediatric radiology. The work in progress agreed by Committee 3 is also described.

  10. Comparison between radiological protection against ionizing radiation and non-ionizing radiation

    International Nuclear Information System (INIS)

    Jammet, H.P.

    1988-01-01

    The comparison of doctrines concerning protection against ionizing and non-ionizing radiation is a difficult task, because of the many areas in which it is applied. Radiological pollution has grown during the century, but its evolution has not been concomitant. This has resulted in a distortion that can be identified in the successive steps of the evaluation and protection against such radiation. For a better understanding, this discussion deals with the differences in interaction with matter and the induction of the related risks, on the varieties of protection systems and monitoring procedures

  11. International Society of Radiology and Radiation Protection

    International Nuclear Information System (INIS)

    Standertskjoeld-Nordenstam, C.G.

    2001-01-01

    The purpose of the International Society of Radiology (ISR), as being the global organization of radiologists, is to promote and help co-ordinate the progress of radiology throughout the world. In this capacity and as a co-operating organization of the IAEA, the ISR has a specific responsibility in the global radiological protection of patients. Globally, there are many users of medical radiation, and radiology may be practised in the most awkward circumstances. The individuals performing X ray studies as well as those interpreting them may be well trained, as in industrialized parts of the world, but also less knowledgeable, as in developing areas. The problems of radiological protection, both of patients and of radiation workers, still exist, and radiation equipment is largely diffused throughout the world. That is why a conference like this is today as important as ever. Radiation protection is achieved through education, on the one hand, and legislation, on the other. Legislation and regulation are the instruments of national authorities. The means of the ISR are education and information. Good radiological practice is something that can be taught. The ISR is doing this mainly through the biannual International Congress of Radiology (ICR), now arranged in an area of radiological need; the three previous ICRs were in China, in India and in South America; the next one is going to be in Mexico in 2002. The goal of the ICR is mainly to be an instructive and educational event, especially designed for the needs of its surrounding region. The ISR is aiming at producing educational material. The International Commission on Radiological Education (ICRE), as part of the ISR, is launching the production of a series of educational booklets, which also include radiation protection. The ICRE is actively involved in shaping and organizing the educational and scientific programme of the ICRs

  12. Fifty years of radiological protection

    International Nuclear Information System (INIS)

    2007-01-01

    On 21 March 1957, the Steering Committee for Nuclear Energy of the Organisation for European Economic Co-operation established the Working Party on Public Health and Safety. From this early date onwards, radiological protection formed a central part of the work of what was to become the OECD Nuclear Energy Agency. Now, 50 years later, the Committee on Radiation Protection and Public Health (CRPPH) has commissioned this historical review of half a century of work and accomplishments. Over this period, the key topics in radiological protection have been identified, debated and addressed by the CRPPH. This report brings this history to life, presenting the major questions in the context of their time, and of the personalities who worked to address them. The developments and views of the past condition how we are able to assess and manage radiological risks today, as well as how we may adjust to challenges that will or could emerge in the coming years. This heritage is thus an important element for the CRPPH to consider as it looks forward to its next 50 years of accomplishments. (author)

  13. Hyperion technology enables unified meteorological and radiological monitoring

    International Nuclear Information System (INIS)

    Zigic, A.; Saponjic, D.; Arandjelovic, V.; Zunic, Z. . E-mail address of corresponding author: alex@vin.bg.ac.yu; Zigic, A.)

    2005-01-01

    The present state of meteorological and radiological measurement and monitoring are quite localized to smaller areas which implies the difficulties in knowing the measurement results in the wider region instantly. The need for establishing a distributed, flexible, modular and centralized measurement system for both meteorological and radiological parameters of environment is arising. The measurement and monitoring of radiological parameters of environment are not sufficient since there is a strong correlation between radiological and meteorological parameters which implies a unified distributed automatic monitoring system. The unified monitoring system makes it possible to transfer, process and store measured data in local and central databases. Central database gives a possibility of easy access to all measured data for authorized personnel and institutions. Stored measured data in central database gives a new opportunity to create a base for meteorological and radiological modelling and studies. (author)

  14. Radiation Protection in Paediatric Radiology

    International Nuclear Information System (INIS)

    2012-01-01

    Over the past decade and a half, special issues have arisen regarding the protection of children undergoing radiological examinations. These issues have come to the consciousness of a gradually widening group of concerned professionals and the public, largely because of the natural instinct to protect children from unnecessary harm. Some tissues in children are more sensitive to radiation and children have a long life expectancy, during which significant pathology can emerge. The instinct to protect children has received further impetus from the level of professional and public concern articulated in the wake of media responses to certain publications in the professional literature. Many institutions have highlighted the need to pay particular attention to the special problems of protecting paediatric patients. The International Commission on Radiological Protection has noted it and the IAEA's General Safety Requirements publication, Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards (BSS), requires it. This need has been endorsed implicitly in the advisory material on paediatric computed tomography scanning issued by bodies such as the US Food and Drug Administration and the National Cancer Institute in the United States of America, as well as by many initiatives taken by other national and regional radiological societies and professional bodies. A major part of patient exposure, in general, and paediatric exposure, in particular, now arises from practices that barely existed two decades ago. For practitioners and regulators, it is evident that this innovation has been driven both by the imaging industry and by an ever increasing array of new applications generated and validated in the clinical environment. Regulation, industrial standardization, safety procedures and advice on best practice lag (inevitably) behind industrial and clinical innovations. This Safety Report is designed to consolidate and provide timely advice on

  15. Radiologic protection: technical and legal aspects

    International Nuclear Information System (INIS)

    Pinto, A.V.A.

    1987-01-01

    Radiologic units are described with the aim to decodify the technical dosimetric language. The legal aspect of radiologic protection in Brazil is reported. Information about help in case of radiation accident is presented. (M.A.C.) [pt

  16. Impact of the application of criteria of internal monitoring in radiological protection programmes in nuclear medicine services

    International Nuclear Information System (INIS)

    Dantas, B.M.; Dantas, A.L.A.; Juliao, L.Q.C.; Lourenco, M.C.; Melo, D.R.

    2005-01-01

    The manipulation of open sources in Nuclear Medicine services involves risks of external exposure and internal contamination. The radiological protection plan of facilities licensed by CNEN - Brazilian Nuclear Energy Commission - must include the evaluation of such risks and propose a programme of individual monitoring to control exposure and ensure the maintenance of conditions of radiation safety. The IAEA - International Atomic Energy Agency - recommendations presented in the Safety Guide RS-G-1.2 suggest that an internal worker monitoring program be implemented where there is a possibility of internal contamination lead to effective dose committed annual values equal to or greater than 1 mSv. This paper presents the application of such criteria to the radionuclides most frequently used in the field of Nuclear Medicine, taking into account the normal conditions of handling and the ranges of activity authorized by CNEN. It is concluded that iodine 131 manipulation for therapeutic purposes is the practice that presented the greatest risk of internal exposure of workers, requiring the adoption of a programme of internal monitoring of Nuclear Medicine services

  17. Advances in radiation protection monitoring

    International Nuclear Information System (INIS)

    1978-01-01

    The requirement to keep radiation exposure as low as reasonably achievable, linked with the growing number of workers whose exposure to radiation must be strictly controlled, requires intensified efforts directed towards the provision of adequate radiation monitoring programmes. This symposium was intended to review the advances that have been made in methods, techniques and instrumentation for radiation protection monitoring. Thus the symposium complemented the detailed consideration that had already been given to two closely related topics, that of environmental monitoring and of monitoring radioactive airborne and liquid discharges from nuclear facilities. The first topic had been dealt with in detail in an Agency symposium held in November 1973 in Warsaw and the second was treated in an Agency symposium held in September 1977 in Portoroz. The present symposium covered a broad range of topics under the following main headings: Monitoring of external exposure (three sessions),Contamination monitoring (three sessions), Radiation monitoring programmes (one session), Calibration, and use of computers (two sessions). An introductory paper described the purpose of radiation protection monitoring and its historical development. It drew attention to the gradual change from the threshold dose hypothesis to the hypothesis of direct proportionality between dose and effect and discussed practical implications of the recommendations recently issued by the International Commission on Radiological Protection (ICRP). It became apparent that guidance on the application of these recommendations is urgently needed. This guidance is presently being prepared by ICRP

  18. Training in radiological protection

    International Nuclear Information System (INIS)

    Medina G, E.

    2014-08-01

    In the Peru, according to the current regulations, people that work with ionizing radiations should have an authorization (individual license), which is granted by the Technical Office of the National Authority that is the technical body of the Instituto Peruano de Energia Nuclear (IPEN) manager of the control of ionizing radiations in the country. The individual license is obtained after the applicant fulfills the requested requirements, as having safety knowledge and radiological protection. Since its founding in 1972, the Centro Superior de Estudios Nucleares (CSEN) of the IPEN has carried out diverse training courses in order to that people can work in a safe way with ionizing radiations in medicine, industry and research, until the year 2013 have been organized 2231 courses that have allowed the training of 26213 people. The courses are organized according to the specific work that is carried out with radiations (medical radio-diagnostic, dental radiology, nuclear medicine, radiotherapy, industrial radiography, nuclear meters, logging while drilling, etc.). In their majority the courses are directed to people that will make use of radiations for first time, but refresher courses are also granted in the topic. The CSEN also carries out the Master degree programs highlighting the Second Professional Specialization in Radiological Protection carried out from the year 2004 with the support of the National University of Engineering. To the present has been carried out 2 programs and there is other being developed. In this work is shown the historical evolution of the radiological protection courses as well as the important thing that they are to work in a safe way in the country. (Author)

  19. Radiological monitoring. Controlling surface water pollution

    International Nuclear Information System (INIS)

    Morin, Maxime

    2018-01-01

    Throughout France, surface waters (from rivers to brooks) located at the vicinity of nuclear or industrial sites, are subject to regular radiological monitoring. An example is given with the radiological monitoring of a small river near La Hague Areva's plant, where contaminations have been detected with the help of the French IRSN nuclear safety research organization. The sampling method and various measurement types are described

  20. Radiological protection report 2015; Strahlenschutzbericht 2015

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2016-06-15

    In the 2015 annual report on radiological protection, the Swiss Federal Nuclear Safety Inspectorate (ENSI) reports on occupational radiation doses, releases of radioactive material and the monitoring of environmental radiation in the areas subject to its surveillance. It concludes that Swiss nuclear facilities continue to maintain a consistent approach to radiological protection. ENSI has identified an increasing public interest in data concerning radiation and has therefore introduced a number of new concepts, such as the online availability of monthly nuclear power plant releases. There is also a new development concerning the data from the network for automatic measurement of dose rates in the vicinity of nuclear power plants (MADUK) which has been in operation since 1994. It is now possible to view dose rates since 1994 averaged over periods of ten minutes, one hour and one day. A special chapter of this report deals with {sup 14}C releases, which are the subject of enquiries from interested parties. The mean annual individual occupational radiation dose remains at 0.6 mSv, being significantly less than the mean annual radiation dose of the population in Switzerland of 5.5 mSv. The highest annual individual dose was almost 11 mSv so that once again in 2015 the annual limit of 20 mSv was not exceeded. The collective doses lie within the range of past years. However, the trend towards a higher collective dose noted at the Leibstadt Nuclear Power Plant has continued. Planning by the operators of nuclear facilities in the field of radiological protection is of a high standard so that the resulting collective doses generally closely match the projected values. In 2015, nuclear power plant operators have again complied with the release limits specified by the authorities, to some extent by a considerable margin. Emissions from Swiss nuclear power plants resulted in a dose of less than 0.01 mSv per year in their immediate surroundings. Liquid releases from Swiss

  1. Radiological Protection Act 1970

    International Nuclear Information System (INIS)

    1970-01-01

    This Act provides for the establishment of a Radiological Protection Board to undertake research and advise on protection from radiation hazards. Its functions include provision of advice to Government departments with responsibilities in relation to protection of sectors of the community or the community as a whole against the hazards of ionizing radiation. The Act, which lays down that the Board shall replace certain departments concerned with radiation protection, repeals several Sections of the Radioactive Substances Act 1948 and the Science and Technology Act 1965. (NEA) [fr

  2. Data Quality Objectives Supporting Radiological Air Emissions Monitoring for the PNNL Site

    Energy Technology Data Exchange (ETDEWEB)

    Barnett, J. Matthew; Meier, Kirsten M.; Snyder, Sandra F.; Fritz, Brad G.; Poston, Ted M.; Rhoads, Kathleen

    2010-05-25

    This document of Data Quality Objectives (DQOs) was prepared based on the U.S. Environmental Protection Agency (EPA) Guidance on Systematic Planning Using the Data Quality Objectives Process, EPA, QA/G4, 2/2006 (EPA 2006) as well as several other published DQOs. Pacific Northwest National Laboratory (PNNL) is in the process of developing a radiological air monitoring program for the PNNL Site that is distinct from that of the nearby Hanford Site. Radiological emissions at the PNNL Site result from Physical Sciences Facility (PSF) major emissions units. A team was established to determine how the PNNL Site would meet federal regulations and address guidelines developed to monitor and estimate offsite air emissions of radioactive materials. The result is a program that monitors the impact to the public from the PNNL Site.

  3. Account 1983-1984. [National Radiological Protection Board

    Energy Technology Data Exchange (ETDEWEB)

    1984-01-01

    Account prepared pursuant to section 3 (4) of the Radiological Protection Act 1970 of the receipts and payments of the National Radiological Protection Board for the year ended 31st March 1984; together with the Report of the Comptroller and Auditor General thereon. (In continuation of House of Commons Paper No. 149 of 1983-84).

  4. Feasibility study for a realistic training dedicated to radiological protection improvement

    International Nuclear Information System (INIS)

    Courageot, E.; Kutschera, R.; Gaillard-Lecanu, E.; Jahan, S.; Riedel, A.; Therache, B.

    2013-01-01

    An evident purpose of the radiological protection training is to use suitable protective equipment and to behave correctly if unexpected working conditions happen. A major difficulty of this training consist in having the most realistic reading from the monitoring devices for a given exposure situation, but without using real radioactive sources. A new approach is developed at EDF R/D for radiological protection training. This approach combines different technologies, in an environment representative of the workplace but geographically separated from the nuclear power plant: a training area representative of a workplace, a Man Machine Interface used by the trainer to define the source configuration and the training scenario, a geo-localization system, fictive radiation monitoring devices and a particle transport code able to calculate in real time the dose map due to the virtual sources. In a first approach, our real-time particles transport code, called Moderato, used only an attenuation low in straight line. To improve the realism further, we would like to switch a code based on the Monte Carlo transport of particles like Geant 4 or MCNPX instead of Moderato. The aim of our study is the evaluation of the code in our application, in particular, the possibility to keep a real time response of our architecture. (authors)

  5. Second Professional Specialization in Radiological Protection in Peru

    International Nuclear Information System (INIS)

    Medina-Gironzini, E.

    2004-01-01

    Considering that professionals with studies, training and experience in Radiological Protection as a Second Professional Specialization must be recognized, the Peruvian Institute of Nuclear Energy (IPEN), which is the institution responsible for the promotion and control of ionizing radiations in the country, has sign a specific agreement with the Universidad Nacional Mayor de San Marcos, in order to develop these courses. They are based on the content of the Post Graduate Course on Radiological Protection and Nuclear Safety of the Universidad de Buenos Aires, in Argentina, where more than 360 people from 27 different countries have been trained in the last 20 years. People who have a professional degree in Sciences or Engineering, and who fulfill the requirements demanded by the University, study this Second Professional Specialization in Radiological Protection. The studies last 2 years and the courses cover the following subjects: Nuclear Physics, Basic Mathematics, Basic Biology, Radiation Sources, Interaction between Radiation and Matter, Radiation Detection and Measurement, Biological effects of ionizing radiations, Radiological protection in the use of radiations in industry and medicine, Regulatory aspects, and nuclear safety - radiological protection interface. IPEN has taken the responsibility to carry out these studies due to its experience in the organization, together with different Universities, of six Masters in Nuclear Energy, four Masters in Medical Physics, one Master in Nuclear Physics, one Master in Nuclear Chemistry, and two Specialization in Nuclear Medicine. For this purpose, IPEN has the Superior Center of Nuclear Studies (CSEN), which has trained more than 2200 people in radiological protection in more than 30 years. CSEN is the first center in the country to train people in the area of nuclear energy and radiological protection. It has the best staff of professors with a both a great education and professional experience, as well as

  6. Second Professional Specialization in Radiological Protection in Peru

    Energy Technology Data Exchange (ETDEWEB)

    Medina-Gironzini, E.

    2004-07-01

    Considering that professionals with studies, training and experience in Radiological Protection as a Second Professional Specialization must be recognized, the Peruvian Institute of Nuclear Energy (IPEN), which is the institution responsible for the promotion and control of ionizing radiations in the country, has sign a specific agreement with the Universidad Nacional Mayor de San Marcos, in order to develop these courses. They are based on the content of the Post Graduate Course on Radiological Protection and Nuclear Safety of the Universidad de Buenos Aires, in Argentina, where more than 360 people from 27 different countries have been trained in the last 20 years. People who have a professional degree in Sciences or Engineering, and who fulfill the requirements demanded by the University, study this Second Professional Specialization in Radiological Protection. The studies last 2 years and the courses cover the following subjects: Nuclear Physics, Basic Mathematics, Basic Biology, Radiation Sources, Interaction between Radiation and Matter, Radiation Detection and Measurement, Biological effects of ionizing radiations, Radiological protection in the use of radiations in industry and medicine, Regulatory aspects, and nuclear safety - radiological protection interface. IPEN has taken the responsibility to carry out these studies due to its experience in the organization, together with different Universities, of six Masters in Nuclear Energy, four Masters in Medical Physics, one Master in Nuclear Physics, one Master in Nuclear Chemistry, and two Specialization in Nuclear Medicine. For this purpose, IPEN has the Superior Center of Nuclear Studies (CSEN), which has trained more than 2200 people in radiological protection in more than 30 years. CSEN is the first center in the country to train people in the area of nuclear energy and radiological protection. It has the best staff of professors with a both a great education and professional experience, as well as

  7. Proceedings of the National Conference on Radiological Protection

    International Nuclear Information System (INIS)

    2014-01-01

    The Radioprotection Argentine Society (SAR) was organized the National Conference on Radiation Protection in 2014, in order to inform to the technical and scientific community about the scopes on radiation protection. The principal treated topics were the following: radiological protection in medical applications, radiology, nuclear medicine, radiotherapy, nuclear fuel cycle, industrial gammagraphy, oil well logging.

  8. Automated radiological monitoring at a Russian Ministry of Defence Naval Site

    International Nuclear Information System (INIS)

    Moskowitz, P.D.; Pomerville, J.; Gavrilov, S.; Kisselev, V.; Daniylan, V.; Belikov, A.; Egorkin, A.; Sokolovski, Y.; Endregard, M.; Krosshavn, M.; Sundling, C.V.; Yokstad, H.

    2001-01-01

    The Arctic Military Environmental Cooperation (AMEC) Program is a cooperative effort between the military establishments of the Kingdom of Norway, the Russian Federation, and the US. This paper discusses joint activities conducted over the past year among Norwegian, Russian, and US technical experts on a project to develop, demonstrate and implement automated radiological monitoring at Russian Navy facilities engaged in the dismantlement of nuclear-powered strategic ballistic missile launching submarines. Radiological monitoring is needed at these facilities to help protect workers engaged in the dismantlement program and the public living within the footprint of routine and accidental radiation exposure areas. By providing remote stand-alone monitoring, the Russian Navy will achieve added protection due to the defense-in-depth strategy afforded by local (at the site), regional (Kola) and national-level (Moscow) oversight. The system being implemented at the Polyaminsky Russian Naval Shipyard was developed from a working model tested at the Russian Institute for Nuclear Safety, Moscow, Russia. It includes Russian manufactured terrestrial and underwater gamma detectors, smart controllers for graded sampling, radio-modems for offsite transmission of the data, and a data fusion/display system: The data fusion/display system is derived from the Norwegian Picasso AMEC Environmental Monitoring software package. This computer package allows monitoring personnel to review the real-time and historical status of monitoring at specific sites and objects and to establish new monitoring protocols as required, for example, in an off-normal accident situation. Plans are being developed to implement the use of this system at most RF Naval sites handling spent nuclear fuel

  9. Philosophy of radiological protection and radiation hazard protection law

    International Nuclear Information System (INIS)

    Kai, Michiaki; Kawano, Takao

    2013-01-01

    The radiation protection and the human safety in radiation facilities are strictly controlled by law. There are rules on the radiation measurement, too. In the present review, philosophy of the radiological protection and the radiation hazard protection law is outlined with reference to ICRP recommendations. (J.P.N.)

  10. Guidelines for selection of radiological protective head covering

    International Nuclear Information System (INIS)

    Galloway, G.R. Jr.

    1995-08-01

    The hood is recognized throughout the nuclear industry as the standard radiological protective head covering for use in radioactively contaminated work environments. As of June 15, 1995, hoods were required for all activities performed in contaminated areas at the Y-12 Plant. The use of hoods had historically been limited to those radiological activities with a high potential for personnel contamination. Due to the large size of many posted contaminated areas at the Y-12 Plant, and compounding safety factors, requirements for the use of hoods are being reevaluated. The purpose of the evaluation is to develop technically sound guidelines for the selection of hoods when prescribing radiological protective head covering. This report presents the guidelines for selection of radiological protective hoods

  11. Board's system of publications. [National Radiological Protection Board

    Energy Technology Data Exchange (ETDEWEB)

    Gaines, M J [National Radiological Protection Board, Harwell (UK)

    1978-07-01

    The purpose of each of the several classes of publication issued by the National Radiological Protection Board is stated. The classes are: advice on standards for protection, emergency reference levels, technical reports, instrument evaluation reports, annual research and development reports, three-yearly reports on the work of the NRPB, miscellaneous specialist booklets, publications for the layman, radiological protection bulletin, information sheets, and brochures.

  12. Some aspects of radiological protection in uranium mines

    International Nuclear Information System (INIS)

    Palacios, E.; Napolitano, C.M.

    1978-01-01

    The basic principles of radiation protection recommended by the International Commission on Radiological Protection - ICRP are presented and the main radiological risks for the uranium mining workers are discussed. Finally some criteria for planning the radioactive waste management in uranium mines are given [pt

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-08-01

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

  14. Protection of staff in interventional radiology

    International Nuclear Information System (INIS)

    Melkamu, M. A.

    2013-04-01

    This project focuses on the interventional radiology. The main objective of this project work was to provide a guidance and advice for occupational exposure and hospital management to optimize radiation protection safety and endorse safety culture. It provides practical information on how to minimize occupational exposure in interventional radiology. In the literature review all considerable parameters to reduce dose to the occupationally exposed are well discussed. These parameters include dose limit, risk estimation, use of dosimeter, personal dose record keeping, analysis of surveillance of occupational dose, investigation levels, and proper use of radiation protection tools and finally about scatter radiation dose rate. In addition the project discusses the ways to reduce occupational exposure in interventional radiology. The methods for dose reduction are minimizing fluoroscopic time, minimizing the number of fluoroscopic image, use of patient dose reduction technologies, use of collimation, planning interventional procedures, positioning in low scattered areas, use of protective shielding, use of appropriate fluoroscopic imaging equipment, giving training for the staff, wearing the dosimeters and know their own dose regularly, and management commitment to quality assurance and quality control system and optimization of radiation protection of safety. (author)

  15. How conservative is routine personal dosimetry monitoring in diagnostic radiology?

    International Nuclear Information System (INIS)

    Boetticher, H. von; Lachmund, J.; Hoffmann, W.

    2007-01-01

    Purpose: Dose values obtained by official personal radiation exposure monitoring are often considered equivalent to the effective dose of a person. This paper provides estimates of the extent of deviation between the two dose concepts under various conditions. Materials and Methods: Doses for patients and personnel were measured using thermoluminescence dosimeters for five different geometries at three work settings in a radiology department. Patients and personnel were simulated with anthropomorphic phantoms. Different types of protective clothing as well as permanent protection shields were considered in the calculations. Results: Dose values obtained by official personal dose monitoring are conservative only for specific radiation protection situations. With state-of-the-art personal protective equipment (wrap-around style lead apron with thyroid shield), the ratio between effective dose and personal dose varies between 0.6 and 1.25. Without thyroid protection the official personal dose systematically underestimates the effective dose: for protective clothing with 0.5 mm lead equivalent without thyroid shielding, the effective dose exceeds the personal dose by factors between 1.7 and 3.1. If protective clothing with lead equivalent 0.35 mm is used, this factor varies between 1.1 and 1.82. (orig.)

  16. New nuclear build and evolving radiological protection challenges

    International Nuclear Information System (INIS)

    Lazo, T.

    2010-01-01

    Many trends and indicators suggest that the use of nuclear power for generating electricity will increase, perhaps significantly, in the coming 10 to 20 years and beyond. Any such expansion will not take place in a static scientific or social context, but rather in the midst of ongoing changes in many relevant fields, radiological protection, radioactive waste management and nuclear safety to name a few. Regarding radiological protection, this evolution can be characterised in many different ways, but can conveniently be described as having scientific and socially driven aspects. These may well pose challenges to radiological protection (RP) policy, regulation and application in the future

  17. Radiologic protection in pediatric radiology: ICRP recommendations

    International Nuclear Information System (INIS)

    Sanchez, Ramon; Khong, Pek-Lan; Ringertz, Hans

    2013-01-01

    ICRP has provided an updated overview of radiation protection principles in pediatric radiology. The authors recommend that staff, radiologists, medical physicists and vendors involved in pediatric radiology read this document. For conventional radiography, the report gives advice on patient positioning, immobilization, shielding and appropriate exposure conditions. It describes extensively the use of pulsed fluoroscopy, the importance of limiting fluoroscopy time, and how shielding and geometry must be used to avoid unnecessary radiation to the patient and operator. Furthermore, the use of fluoroscopy in interventional procedures with emphasis on dose reduction to patients and staff is discussed in light of the increasing frequency, complexity and length ofthe procedures. CT is the main reason that medical imaging in several developed countries is the highest annual per capita effective radiation dose from man-made sources. The ICRP report gives extensive descriptions of how CT protocols can be optimized to minimize radiation exposure in pediatric patients. The importance of balancing image quality with acceptable noise in pediatric imaging and the controversies regarding the use of protective shielding in CT are also discussed.

  18. Evaluation of the effectiveness of gonad protection in diagnostic radiology

    International Nuclear Information System (INIS)

    Kawaura, Chiyo; Aoyama, Takahiko; Koyama, Shuji

    2004-01-01

    In the present study we describes the evaluation of the effectiveness of gonad protection in diagnostic radiology based on the measurement of organ and the effective doses with and without lead clothing to gonads. We devised in-phantom dosimetry system and measured organ and effective doses in x-ray radiography and CT examinations with the new dosimetry system. From the data of organ and the effective doses we assessed the effectiveness of radiological protection by the use of lead clothing to gonads. Although in chest radiography and chest CT examinations, the effectiveness of radiological protection was not found, in the case of hip joint radiography (AP), gonad doses decreased remarkably by using lead clothing. The effectiveness of radiological protection, i.e. the ratio of the decreased dose to the dose value without protection, in testis and ovary were found to be 91.4% and 68.0%, respectively. It was also found that gonad doses observed with and without gonad protection were extremely lower than those of threshold for sterility recommended by the International Commission on Radiological Protection 60 (ICRP Publ. 60). (author)

  19. [Evaluation of the effectiveness of gonad protection in diagnostic radiology].

    Science.gov (United States)

    Kawaura, Chiyo; Aoyama, Takahiko; Koyama, Shuji

    2004-01-01

    In the present study we describe the evaluation of the effectiveness of gonad protection in diagnostic radiology based on the measurement of organ and the effective doses with and without lead clothing to gonads. We devised in-phantom dosimetry system and measured organ and effective doses in x-ray radiography and CT examinations with the new dosimetry system. From the data of organ and the effective doses we assessed the effectiveness of radiological protection by the use of lead clothing to gonads. Although in chest radiography and chest CT examinations, the effectiveness of radiological protection was not found, in the case of hip joint radiography (AP), gonad doses decreased remarkably by using lead clothing. The effectiveness of radiological protection, i.e. the ratio of the decreased dose to the dose value without protection, in testis and ovary were found to be 91.4% and 68.0%, respectively. It was also found that gonad doses observed with and without gonad protection were extremely lower than those of threshold for sterility recommended by the International Commission on Radiological Protection 60 (ICRP Publ. 60).

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1997-12-31

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

  1. Radiological respiratory protection in Angra-1 Nuclear Power Plant

    International Nuclear Information System (INIS)

    Amaral, Marcos A. do

    1996-01-01

    The present paper has the purpose to describe the actual situation of the Radiological respiratory Protection in Angra I Nuclear Power Plant, the difficulties found and the goals to achieve, in order of the radiological protection excellence. (author)

  2. Radiological protection of the environment from the Swedish point of view

    International Nuclear Information System (INIS)

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

    2002-01-01

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

  3. Radiological protection of the patient in the diagnostic X-ray

    International Nuclear Information System (INIS)

    Araujo, A.M.C. de

    1983-01-01

    Measures and procedures are given in relation to the radiological protection of the patient in diagnostic radiology. Technical and physical factors of the patient protection are discussed, as radiation beam properties, size of the irradiation field, shieldings, control of the scattered radiation that reaches the imaging record system, films, ecrans and radiographic film processing. General recommendations about the radiation protection of the patient in diagnostic radiology are given. (M.A.) [pt

  4. National Radiological Protection Board. Account 1991-92

    International Nuclear Information System (INIS)

    1992-01-01

    The Board was constituted as a public authority under the Radiological Protection Act 1970 with the functions of advancing the acquisition of knowledge about the protection of mankind from radiation hazards and providing information and advice to persons, including Government Departments, with responsibilities in the United Kingdom in relation to the protection from radiation hazards either of the community as a whole or particular sections of the community. The Board is also empowered to provide technical services to persons and groups of persons concerned with radiation hazards on a commercial basis. These accounts show that the surplus on ordinary activities amounted to 210k pounds; cash balances increased by 161k pounds to 748k pounds which includes 431k pounds held on behalf of European Partners under the CEC Association Agreement. The Board achieved the principal objectives which had been set out in the Corporate Plan. Demand for the provision of services and advice to industry and other public bodies continued at a constant level. Current major issues are the new Recommendations from the International Commission on Radiological Protection for control of exposure, and subsequent national recommendations on dose limitation; an increasing awareness of non-ionising radiation, and public exposures and aspects of radiation in the environment. In particular there has been a significant demand for radon surveys as part of a sponsored monitoring programme in the south-west which is largely responsible for the increase in income-earning activities. Further studies are being commissioned and it is likely, therefore, that the Board will continue to be involved in large-scale radon work in the immediate future. The financial objectives were attained with minor variances on the planned budget profiles. (UK)

  5. Mission and activities of the International Commission on Radiological Protection

    International Nuclear Information System (INIS)

    Clements, C.H.

    2018-01-01

    The International Commission on Radiological Protection (ICRP), formed in 1928, develops the System of Radiological Protection for the public benefit. The objective of the recommendations is to contribute to an appropriate level of protection for people and the environment against the harmful effects of radiation exposure without unduly limiting the individual or societal benefits of activities involving radiation. In developing its recommendations, ICRP considers advances in scientific knowledge, evolving social values, and practical experience. These recommendations are the basis of radiological protection standards and practice worldwide

  6. SCK CEN'S International School for Radiological Protection (ISRP): communicating the aspects of radiological protection

    International Nuclear Information System (INIS)

    Coeck, M.; Majakowski, I.; Verachtert, C.; Meskens, G.

    2006-01-01

    Full text: Thanks to its thorough experience in the field of peaceful applications of nuclear science and technology, radiological protection and radiobiology, the Belgian nuclear research centre S.C.K. E.N. has garnered a reputation as an outstanding centre of research, training and education. Functioning as a task force within S.C.K. E.N., the international school for Radiological Protection (i.s.R.P.) initiates and manages training and research projects and contributes to related activities on national and international level. I.s.R.P. activities are situated on three axes: Coordination and organisation of training and education programmes on radiological protection The i.s.R.P. training activities deal with all aspects of radiological protection and are directed to the private, medical and industrial nuclear sector, national and international policy organisations, the political and academic world and the general public. Courses are also organised in cooperation with technical high schools, universities and public and private health services. In addition, i.s.R.P. is involved in international research networks and training programmes, such as those of the European Commission and the IAEA. The i.s.R.P. team of lecturers includes technicians, physicists, biologists, medical doctors, engineers and social scientists, who all bring insights and ideas from their specific background into the course programmes. As S.C.K. E.N. staff members, they have a solid knowledge and experience in their field, and can thus directly transfer their theoretical knowledge and practical experience to the various courses. Course programmes are composed together with the customer, drawing from the set of basic and expertise course modules and completed with technical visits. The basic modules textbooks exist in Dutch, French and English. In addition, all course modules and visits can be lectured and guided in Dutch, French or English. Research on trans-disciplinary aspects of education

  7. Federal Radiological Monitoring and Assessment Center Phased Response Operations

    International Nuclear Information System (INIS)

    Riland, C.A.; Bowman, D.R.

    1999-01-01

    A Federal Radiological Monitoring and Assessment Center (FRMAC) is established in response to the Lead Federal Agency (LFA) or state request when a major radiological emergency is anticipated of has occurred. The FRMAC becomes a coalition of federal off-site monitoring and assessment activities to assist the LFA, state(s), local, and tribal authorities. State, local, and tribal authorities are invited to co-locate and prioritize monitoring and assessment efforts in the FRMAC. The Department of Energy is tasked by the Federal Radiological Emergency Response Plan to coordinate the FRMAC

  8. Radiological protection at particle accelerators: An overview

    International Nuclear Information System (INIS)

    Thomas, R.H.

    1991-01-01

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

  9. Operational Radiological Protection and Aspects of Optimisation

    International Nuclear Information System (INIS)

    Lazo, E.; Lindvall, C.G.

    2005-01-01

    Since 1992, the Nuclear Energy Agency (NEA), along with the International Atomic Energy Agency (IAEA), has sponsored the Information System on Occupational Exposure (ISOE). ISOE collects and analyses occupational exposure data and experience from over 400 nuclear power plants around the world and is a forum for radiological protection experts from both nuclear power plants and regulatory authorities to share lessons learned and best practices in the management of worker radiation exposures. In connection to the ongoing work of the International Commission on Radiological Protection (ICRP) to develop new recommendations, the ISOE programme has been interested in how the new recommendations would affect operational radiological protection application at nuclear power plants. Bearing in mind that the ICRP is developing, in addition to new general recommendations, a new recommendation specifically on optimisation, the ISOE programme created a working group to study the operational aspects of optimisation, and to identify the key factors in optimisation that could usefully be reflected in ICRP recommendations. In addition, the Group identified areas where further ICRP clarification and guidance would be of assistance to practitioners, both at the plant and the regulatory authority. The specific objective of this ISOE work was to provide operational radiological protection input, based on practical experience, to the development of new ICRP recommendations, particularly in the area of optimisation. This will help assure that new recommendations will best serve the needs of those implementing radiation protection standards, for the public and for workers, at both national and international levels. (author)

  10. Environmental radioactivity in Canada 1988. Radiological monitoring annual report

    Energy Technology Data Exchange (ETDEWEB)

    1992-12-31

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

  11. Current evaluation of the information about Radiological Protection in Internet

    International Nuclear Information System (INIS)

    Ruiz-Cruces, R.; Marco, M.; Villanueva, I.

    2003-01-01

    To analyze the current situation about the pedagogic information on radiological protection training which could be found in Internet. More than 756 web-pages have been visited in Internet about Radiological Protection in the nuclear and medical fields, providing information mainly focusing on information to the members of the public. In this search were used internet Searching Appliance (as Copernicus, Google and Scirus), using key words related with this subject (as Radiological Protection and Health Safety), getting the internet address of organizations, societies and investigation groups. Only a low percentage (less than 5 per cent) of these addresses content information on Radiological Protection for the members of the public, including information about the regulator Organizations, and which are the objectives for protection of the members of the public against ionization radiation (from the point of view of the use of the ionization radiation in the medical and nuclear field). This work attempts to propose the use of internet as a tool for informing the members of the public in matter of radiological protection, as first link in the chain of the training and education. (Author)

  12. Radiological protection for the dental practice

    International Nuclear Information System (INIS)

    Mora Rodriguez, Patricia; Loria Meneses, Luis Guillermo

    2007-01-01

    This work offers a didactical material, of easy reading and without mathematical complexity, about the fundamentals of the radiological protection in the dental area. It is dedicated to the personnel of the Ministerio de Salud, responsible to realize radiological inspection in dentistry clinics of the country. It is recommended to consult other bibliographical references if it is wished to extend about a particular subject [es

  13. The teaching of Radiological Protection in actual society

    International Nuclear Information System (INIS)

    Lorenzo, Nestor Pedro de

    1996-01-01

    The use more and more frequent of radiations in different areas of the daily life generate a growing necessity of competent professionals and technicians qualified in Health Physics. The teaching of the Radiological Protection does not limit only to the instruction in scientists topics that quality to the professionals in the resolution of problems or the application of techniques, must qualified also the students in the diffusion of the own problems of the radiological protection. The content of different courses of radiological protection given in the Instituto Bailer's ( a join between the National University of Cuyo and the National Commission of Atomic Energy) guided to different groups of students or professionals are also introduced. Finally, some of the examples used in order to clarify practical situations are shown. (author)

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

    International Nuclear Information System (INIS)

    2002-01-01

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

  15. Ethical values in radiological protection

    International Nuclear Information System (INIS)

    Oughton, D.H.

    1996-01-01

    Issues like consent, equity, control and responsibility are important for an ethical evaluation of radiation risks. This paper discusses the incorporation of ethical values in radiological protection policy and compares how ICRP recommendations promote their use in practice and intervention cases. The paper contends that in cases of intervention, where the overall aim is dose reduction, social and ethical factors are often alluded to when evaluating costs of an action. However, possible ethical or social benefits of intervention measures are seldom raised. On the other hand, when assessing a practice, wherein the net effect is an increase in radiation dose, one is more likely to find an appeal to ethical factors on the benefits side of the equation than with the costs. The paper concludes that all decisions concerning radiological protection should consider both positive and negative ethical aspects. (author)

  16. Independent auto evaluation of an operative radiological protection program

    International Nuclear Information System (INIS)

    Medrano L, M.A.; Rodriguez C, C.C.; Linares R, D.; Zarate M, N.; Zempoalteca B, R.

    2006-01-01

    The program of operative radiological protection of a nuclear power plant consists of multiple procedures and associate tasks that have as purpose the radiological protection of the workers of the power station. It is for this reason that the constant evaluation of the one it programs it is an important tool in the identification of their weaknesses (and strengths), so they can be assisted appropriately. In this work the main elements of the program of independent auto evaluation of the program of operative radiological protection of the Laguna Verde Central that has been developed and implemented by the National Institute of Nuclear Research are described. (Author)

  17. Federal Radiological Monitoring and Assessment Center Monitoring Manual Volume 2, Radiation Monitoring and Sampling

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Aerial Measurement Systems

    2012-07-31

    The FRMAC Monitoring and Sampling Manual, Volume 2 provides standard operating procedures (SOPs) for field radiation monitoring and sample collection activities that are performed by the Monitoring group during a FRMAC response to a radiological emergency.

  18. Conditions of radiological protection in the health unities

    International Nuclear Information System (INIS)

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

    1987-01-01

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

  19. Twenty years of Radiology in RP-10 nuclear reactor protection

    International Nuclear Information System (INIS)

    Zapata, Alejandro L.; Ramos, Fernando T.; Arrieta, Rolando W.B.; Vela Mora, Mariano

    2013-01-01

    In this report we present the results about radiation controls during 1990 - 2010, carried out in the Nuclear Reactor RP-10 of the Nuclear Center of Huarangal. These controls and radiological evaluation are of much utility for the radio personnel protection of this one and other reactors, since it allows to compares these variables with respect to the time. From the results obtained in monitoring and radiation controls, we conclude that in no case it has been reached the limits allowed by the Peruvian Regulating Authority. (author)

  20. Recent perspectives on optimisation of radiological protection

    International Nuclear Information System (INIS)

    Robb, J.D.; Croft, J.R.

    1992-01-01

    The ALARA principle as a requirement in radiological protection has evolved from its theoretical roots. Based on several years work, this paper provides a backdrop to practical approaches to ALARA for the 1990s. The key step, developing ALARA thinking so that it becomes an integral part of radiological protection programmes, is discussed using examples from the UK and France, as is the role of tools to help standardise judgements for decision-making. In its latest recommendations, ICRP have suggested that the optimisation of protection should be constrained by restrictions on the doses to individuals. This paper also considers the function of such restrictions for occupational, public and medical exposure, and in the design process. (author)

  1. ICRP Publication 138: Ethical Foundations of the System of Radiological Protection.

    Science.gov (United States)

    Cho, K-W; Cantone, M-C; Kurihara-Saio, C; Le Guen, B; Martinez, N; Oughton, D; Schneider, T; Toohey, R; ZöLzer, F

    2018-02-01

    Despite a longstanding recognition that radiological protection is not only a matter of science, but also ethics, ICRP publications have rarely addressed the ethical foundations of the system of radiological protection explicitly. The purpose of this publication is to describe how the Commission has relied on ethical values, either intentionally or indirectly, in developing the system of radiological protection with the objective of presenting a coherent view of how ethics is part of this system. In so doing, it helps to clarify the inherent value judgements made in achieving the aim of the radiological protection system as underlined by the Commission in Publication 103. Although primarily addressed to the radiological protection community, this publication is also intended to address authorities, operators, workers, medical professionals, patients, the public, and its representatives (e.g. NGOs) acting in the interest of the protection of people and the environment. This publication provides the key steps concerning the scientific, ethical, and practical evolutions of the system of radiological protection since the first ICRP publication in 1928. It then describes the four core ethical values underpinning the present system: beneficence/ non-maleficence, prudence, justice, and dignity. It also discusses how these core ethical values relate to the principles of radiological protection, namely justification, optimisation, and limitation. The publication finally addresses key procedural values that are required for the practical implementation of the system, focusing on accountability, transparency, and inclusiveness. The Commission sees this publication as a founding document to be elaborated further in different situations and circumstances.

  2. Principles of radiological protection: new paradigms

    International Nuclear Information System (INIS)

    Ximenes, Edmir; Guimaraes, Maria Ines Calil Cury

    2009-01-01

    Full text: The relationships of workers, patients and physicians to the basic principles of radiological protection were given in this work an historical introduction that emphasizes their development from their beginnings to the current period. The evolution of scientific knowledge as regards the benefits and injuries resulting from the use of the ionizing radiation in human activities is the main focus of the work. These principles (justification, optimization and limitation) are presented in order to offer a broader view of their application fields. The principle of the optimization receives the contribution of techniques aimed to help the decision used in radiological protection. The principle of the limitation of doses is helped by the concept of limit specifically linked to a given segment of the population or a given human activity. Regarding the current relationship between physicians and patients a change of philosophy is discussed in what concerns the radiation dose supplied that should be the minimum one in relation to the diagnosis or cure objectives. The administration of radiation must follow the recommendations of ICRP - International Commission on Radiological Protection. The radiation can bring benefits if used with rationality, efficacy and care. The radiation should not be feared, but respected. (author)

  3. The basis for a radiological protection program to the health area of the State University of Campinas (UNICAMP)

    International Nuclear Information System (INIS)

    Coelho, Rosangela Franco.

    1994-01-01

    There are some sectors in the Health Area of the State University of Campinas (UNICAMP) that present great potential risks from the viewpoint of radiation protection. The aim of this work is to establish the basis a radiological protection program applicable to these sectors. The Diagnostic Radiology Services and the Laboratory of Cardiac Catheterization of the Hospital de Clinicas have been analyzed, as well as the Radiotherapy Services of the Center for Integral Assistance to the Women Health (CAISM). This work was mainly supported by national and international regulations related to the operative and employment aspects of the equipment and radiation sources used in the health area. Regulations related to area and individual monitoring of workers were also used. Results show that the interior of the rooms where the equipment and radiation sources are located is classified as controlled area, whereas the neighborhoods of the rooms are mostly free areas. In order to improve the radiological protection conditions, only some of the operative and employment aspects need to be modified regarding equipment and radiation sources. In this way, routine personal monitoring would not be further required. Since all the workers have their annual mean equivalent doses below 3/10 of the primary limits of the applicable equivalent dose, routine individual monitoring could be exempted. (author). 23 refs., 51 figs., 83 tabs

  4. Action research regarding the optimisation of radiological protection for nurses during vascular interventional radiology

    International Nuclear Information System (INIS)

    Mori, Hiroshige

    2015-01-01

    The optimisation and decision-making processes for radiological protection have been broadened by the introduction of re-examination or feedback after introducing protective measures. In this study, action research was used to reduce the occupational exposure of vascular interventional radiology (IR) nurses. Four radiological protection improvement measures were continuously performed in cooperation with the researchers, nurses and stakeholders, and the nurses’ annual effective doses were compared before and after the improvements. First, the dosimetry equipment was changed from one electronic personal dosimeter (EPD) to two silver-activated phosphate glass dosimeters (PGDs). Second, the nurses were educated regarding maintaining a safe distance from the sources of scattered and leakage radiation. Third, portable radiation shielding screens were placed in the IR rooms. Fourth, the x-ray units’ pulse rates were reduced by half. On changing the dosimetry method, the two PGDs recorded a 4.4 fold greater dose than the single EPD. Educating nurses regarding radiological protection and reducing the pulse rates by half decreased their effective doses to one-third and two-fifths of the baseline dose, respectively. No significant difference in their doses was detected after the placement of the shielding screens. Therefore, the action research effectively decreased the occupational doses of the vascular IR nurses. (practical matter)

  5. Action research regarding the optimisation of radiological protection for nurses during vascular interventional radiology.

    Science.gov (United States)

    Mori, Hiroshige

    2015-06-01

    The optimisation and decision-making processes for radiological protection have been broadened by the introduction of re-examination or feedback after introducing protective measures. In this study, action research was used to reduce the occupational exposure of vascular interventional radiology (IR) nurses. Four radiological protection improvement measures were continuously performed in cooperation with the researchers, nurses and stakeholders, and the nurses' annual effective doses were compared before and after the improvements. First, the dosimetry equipment was changed from one electronic personal dosimeter (EPD) to two silver-activated phosphate glass dosimeters (PGDs). Second, the nurses were educated regarding maintaining a safe distance from the sources of scattered and leakage radiation. Third, portable radiation shielding screens were placed in the IR rooms. Fourth, the x-ray units' pulse rates were reduced by half. On changing the dosimetry method, the two PGDs recorded a 4.4 fold greater dose than the single EPD. Educating nurses regarding radiological protection and reducing the pulse rates by half decreased their effective doses to one-third and two-fifths of the baseline dose, respectively. No significant difference in their doses was detected after the placement of the shielding screens. Therefore, the action research effectively decreased the occupational doses of the vascular IR nurses.

  6. Radiological protection in nucleus reactor; Perlindungan radiologi di reaktor nukleus

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1988-12-31

    The chapter briefly discussed the following subjects: radiological protection problems of reactor 1. in operation 2. types of reactor i.e. power reactors, research reactors, etc. 3. during maintenance and installation of fuels. 4. nuclear fuels.

  7. Radiological Protection (Amendment) Act, 2002. Number 3 of 2002

    International Nuclear Information System (INIS)

    2002-01-01

    This Act amends the Radiological Protection Acts, 1991 and 1995, and provides for the making of grants out of funds provided by the legislature for remediation works for houses having certain levels of radon gas and for the administration by the Radiological Protection Institute of Ireland of such grants and to provide for related matters

  8. Coincidence of needs in radiological and toxicological protection

    International Nuclear Information System (INIS)

    Osborne, R.V.

    1988-01-01

    Research needs for radiological protection and research programs that have evolved to meet these needs parallel closely those in the chemical toxicology field. The similarity of these needs is described as perceived from the radiological side. Further, the frame work for radiologically-related research, out lines of the research programs, and the development of the facilities at Chalk River Nuclear Labs were presented

  9. Radiological aerial monitoring in a nuclear emergency

    International Nuclear Information System (INIS)

    Shin, Hyeongki; Kim, Juyoul; Jung, Gunhyo

    2008-01-01

    Since North Korea announced the underground nuclear test on last October 9th, 2006, many countries around the world have worried about the atmospheric dispersion and pollution of radioactive materials crossing the border by the clandestine nuclear test. After that time, verifying the existence of nuclear test by detecting radioactive materials such as xenon, I-131, and Cs-134 at the early stage of radiological emergency, locating the position of test site by backward trajectory analysis, and chasing the moving path of airborne radionuclide have been heavily issued. And collection of airborne radioactivity and gamma radiation monitoring technology using an aircraft have been recently examined by an authority concerned in South Korea. Although various techniques of radiological aerial monitoring have been developed and operated around the world, the relevant technical development or research is still required. In order to decide potential measuring location and time within the framework of radiological monitoring system, we use HYSPLIT (Hybrid Single Particle Lagrangian Integrated Trajectory) model developed by National Oceanic and Atmospheric Administration (NOAA) of U.S. Department of Commerce. The model is validated and assessed against North Korea's nuclear test. Calculation results of radionuclide trajectory show a good agreement with measured values. Backward trajectory analysis is useful to track the radiological source term, possible time and place of nuclear accidents and/or activities. Nationwide early warning system using aircraft and atmospheric dispersion model can help a nearly real-time forecasting and warning in preparation for radiological emergencies. (author)

  10. Introduction of new terms and lessons for radiological protection after Fukushima Dai-Ichi accident

    International Nuclear Information System (INIS)

    Singh, Vishwanath P.; Managanvi, S.S.; Bhat, H.R.

    2012-01-01

    , evacuation timing, appropriate evacuation decision, increase in coverage area of EPZ, limit of activity in water, milk and foodstuff during accident. In addition, the training for knowledge of radiation, effects, understanding of the definitions to public, medical staff is also equally important. During the nuclear crises management, radioactivity measurement, personal monitoring, instruments, dose limits, evacuation decision, forecast of the dose/dose rate in public domain, decontamination of the person/land, radioactive waste management are the main concern for radiological protection professionals as an advisor. Conclusion: The Fukushima accident was one of the worst kind for Japan as well as international societies for radiation protection however we have learnt a lot from the accident, The accident has introduced new terms; review of the emergency zoning concept, dose limit, activity limit on food stuff, personnel monitoring equipment, waste management. India is working out the radiological aspect to enhance the safety during emergency. (author)

  11. Radiation protection study of radiology medical workers in radiodiagnosis area

    International Nuclear Information System (INIS)

    Gaona, E.; Canizal, C.; Garcia, M.A.; Orozco, M.; Rincon, A.; Padilla, Y.; Martinez, A.

    1996-01-01

    Aspects related to radiological safety and its organization in radiodiagnosis were evaluated by means of scanning carried out in 18 hospitals of Mexico City, divided in 11 public institutions and 7 private ones. The population being studied was: hospital personnel that works in radiodiagnosis. The survey was made with 31 dichotomic variables, being obtained 132 surveys. The personnel characteristics are 83% works in public institutions, 49% works in radiodiagnosis, 3% has an academic degree, 13% is member of a hospital professional association, 13% has updated information on radiological protection, 36% was trained, 45% works for more than 2 years, 52% uses personal dosemeter, less than the 20% knows about the fundamentals of the radiological protection and 24% states to suffer from biological radiation effects, due to the exposure to x-rays. As result of the study, it was found that the main problems that the radiological protection has, are: lack of training programs in radiological protection and supervision, medical surveillance and the few number of persons that takes part in clinical meetings and professional associations. (authors). 7 refs., 3 tabs

  12. Education and Training in the Field of Radiological Protection

    International Nuclear Information System (INIS)

    Meskens, G.

    2002-01-01

    The International School for Radiological Protection (isRP) was founded within SCK-CEN in 1996 and organises training programmes on radiological protection for nuclear workers and staff. In 2001, isRP organised twelve courses for Belgian and foreign organisations active in the nuclear and non-nuclear field. The report gives an overview of the main activities in 2001

  13. Radiological protection principles concerning the safeguard, use or release of contaminated materials, buildings, areas or dumps from uranium mining. Recommendations of the Commission on Radiological Protection with explanations

    International Nuclear Information System (INIS)

    Mueller-Neumann, M.

    1992-01-01

    The volume presents the full texts of the SSK Recommendations addressing the aspects and problems involved, and which can be separately retrieved from the database: 1) Radiological protection principles concerning the release of scrap from the shut-down of uranium mining plants; 2) Radiological protection principles concerning the release for industrial use of areas contaminated from uranium mining; 3) Radiological protection principles concerning the use for forest and agricultural purposes and as public gardens (parks) and residential areas of areas contaminated from uranium mining; 4) Radiological protection principles concerning the safeguard and use of mine dumps; 5) Radiological protection principles concerning the release for further commercial or industrial use of buildings used for commercial or industrial purposes and the disposal of building debris from uranium mining and milling; 6) Radiological protection principles concerning the release for general use of reusable equipment and installations from uranium mining. The following appendices round up the material: 1) Radiation exposure from mining in Saxony and Thuringia and its evaluation (Summary of the results of consultations during the 1990 closed meeting); 2) Radiological protection principles for the limitation of the radiation exposure of the public to radon and its daughters; 3) Epidemiological studies on the health state of the inhabitants of the mining region and the miners in Saxony and Thuringia. (orig.) [de

  14. Control development of radiation protection and safety on personnel eye lens of interventional radiology

    International Nuclear Information System (INIS)

    Titik Kartika; Ishak

    2013-01-01

    The review on radiation protection and safety to the lens of personnel especially in interventional radiology activities has been carried out. The use of radiation in interventional radiology installations provide significant exposure to the lens of the eye, especially personnel. The results of the latest various surveys and researches on the effects of low dose radiation to the eye lens indicates that the eye lens dose threshold is less than the preconceived values. Based on these facts, recently, ICRP and IAEA provides recommendations regarding the reduction of the value of the eye lens dose limit for personnel. BAPETEN have adopted the value of the eye lens dose limit in the development of new regulations on radiation protection and safety. However, the application of this provision has various challenges that BAPETEN provide 3 (three) years transitional period. These challenges include the problem of monitoring the eye lens dose, the eye lens protective equipment which is not adequate, the lack of understanding of personnel related to the risk of low radiation to the eye lens, as well as the proper procedures to mitigate those risks. BAPETEN as a regulatory agency is expected to provide solutions to the problems faced by the stake holders. Therefore, to answer the challenge, it is necessary to develop better monitoring of radiation protection and safety. (author)

  15. Evaluation of radiological protection aspects in radiodiagnostic rooms in Mexico City

    International Nuclear Information System (INIS)

    Escobar A, L.; Vizuet G, J.; Ruiz, M.A.

    1996-01-01

    The preliminary results of an evaluation of radiological protection carried out in radiology services of different hospitals of Mexico are shown. The evaluated points were: relative aspects of the room, operation parameters of operation of the equipment, work procedures and training about radiological protection for the equipment operators. (authors). 2 refs., 1 fig

  16. Key issues concerning changes in the radiological protection system: some thoughts from the French Society for Radiation Protection (SFRP)

    International Nuclear Information System (INIS)

    Schieber, C.; Cordoliani, Y.S.

    2002-01-01

    In 1999, the International Radiological Protection Association (IRPA) asked for contributions to the debate on future changes to the radiological protection system proposed by the International Commission on Radiological Protection (ICRP). In response, the Board of the French Society for Radiation Protection (SFRP) created a working group to deal specifically with this issue. It met on several occasions between April and July and its findings were presented at the IRPA Congress in May 2000. They were also published in the French journal Radioprotection and in the British Journal of Radiological Protection. To further its discussions, the Board of the SFRP decided to create a second working group which became operational in September 2001. It has around 20 members representing the major players in the radiological protection field in France: authorities, experts and professionals from the nuclear, medical and research fields as well as one association representative (the list of members can be found at the end of this document). The working group was set up to produce proposals relating to the key issues likely to be raised, particularly by the ICRP, concerning the development of new radiological protection recommendations. The members of the working group analysed the ICRP memorandum published in the June 2001 edition of the Journal of Radiological Protection and used their own experience to determine what these key issues would be. The following issues were discussed: General thoughts on the new radiological protection system proposed by the ICRP, Individual and collective approaches to the radiological risk, Comparison with chemical risk management, Radiological protection of the environment, Changes in exposure levels and units of measurement. This paper, which has been approved by the Board of the SFRP, gives the main conclusions of the working group on the key issues in these areas. It is intended to reflect the various opinions expressed during the groups

  17. Services of radiological protection: as sizing the human and material resources

    International Nuclear Information System (INIS)

    Rueda Guerrero, M. D.; Sierra Perler, I.; Lorenzo Perez, P.

    2014-01-01

    Discussion of radiological protection in the Middle Health has formed a task force to develop a technical document recommendatory to help plan and evaluate resources radiological protection services. (Author)

  18. The mandate and work of ICRP Committee 3 on radiological protection in medicine.

    Science.gov (United States)

    Miller, D L; Martin, C J; Rehani, M M

    2018-01-01

    The mandate of Committee 3 of the International Commission on Radiological Protection (ICRP) is concerned with the protection of persons and unborn children when ionising radiation is used in medical diagnosis, therapy, and biomedical research. Protection in veterinary medicine has been newly added to the mandate. Committee 3 develops recommendations and guidance in these areas. The most recent documents published by ICRP that relate to radiological protection in medicine are 'Radiological protection in cone beam computed tomography' (ICRP Publication 129) and 'Radiological protection in ion beam radiotherapy' (ICRP Publication 127). A report in cooperation with ICRP Committee 2 entitled 'Radiation dose to patients from radiopharmaceuticals: a compendium of current information related to frequently used substances' (ICRP Publication 128) has also been published. 'Diagnostic reference levels in medical imaging' (ICRP Publication 135), published in 2017, provides specific advice on the setting and use of diagnostic reference levels for diagnostic and interventional radiology, digital imaging, computed tomography, nuclear medicine, paediatrics, and multi-modality procedures. 'Occupational radiological protection in interventional procedures' was published in March 2018 as ICRP Publication 139. A document on radiological protection in therapy with radiopharmaceuticals is likely to be published in 2018. Work is in progress on several other topics, including appropriate use of effective dose in collaboration with the other ICRP committees, guidance for occupational radiological protection in brachytherapy, justification in medical imaging, and radiation doses to patients from radiopharmaceuticals (an update to ICRP Publication 128). Committee 3 is also considering the development of guidance on radiological protection in medicine related to individual radiosusceptibility, in collaboration with ICRP Committee 1.

  19. Environmental aspects at radiological protection in ArcelorMittal Monlevade

    International Nuclear Information System (INIS)

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

    2010-01-01

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

  20. The role of radiologic technologist in radiation protection and quality assurance programs

    International Nuclear Information System (INIS)

    Djurovic, B.; Spasci -Jokic, V.; Misovic, M.

    2001-01-01

    The most important sources of ionizing radiation for general public are medical sources. Good working protocols and radiological protections measurements provided significant reduction of patients and professional doses. Medical users of ionizing radiation are radiological technologists. The purpose of this paper is to point out to several facts and errors in radiation protection educational programs for radiological technologists. Medical College educational program covers main specific topics in radiation protection, but there are some omissions in training process. Radiological technologists must be actively involved in radiation protection. Following ethical standards they will reach higher standards than the law requires

  1. Radiological protection report 2007; Strahlenschutzbericht 2007

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-01

    This annual report issued by the Swiss Federal Nuclear Inspectorate (HSK) reports on the work carried out by the Inspectorate in 2007. It provides comprehensive data on radiation protection activities in Switzerland during 2007. This is the fourth annual summary report on the radiological protection issues regulated by the Inspectorate. It provides comprehensive data on doses for the staff and for individual jobs. It also includes year-to-year comparisons and comments on the continuing decline in collective and average doses for persons exposed to radiation in the course of their work. Radiation doses are commented on. Radiation in the four Swiss nuclear power stations and in four further nuclear installations in various Swiss research facilities is commented on. The Swiss radiation measurement network is commented on and the results obtained are discussed. The Inspectorate concludes that radiological protection in Swiss nuclear facilities is carried out consistently and in compliance with existing legislation.

  2. Bi-annual report 1994-1995. Research and operational activities of Central Laboratory for Radiological Protection

    International Nuclear Information System (INIS)

    1996-01-01

    BI-annual report of Central Laboratory for Radiological Protection, Warsaw, shows its activities in 1994-1995. The general information and organization of CLOR have been performed in the opening part of the report. The second part contains extended abstracts of scientific activities especially in: environmental radioactivity monitoring, supervision and control of the users of radioactive sources, dosimetry problems, calibration and standardization of dosimetric equipment, radiobiology and radiological hazard assessment. The report also includes the full list of publications of CLOR scientific staff issued in the period of 1994-1995

  3. Bi-annual report 1994-1995. Research and operational activities of Central Laboratory for Radiological Protection

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-12-31

    BI-annual report of Central Laboratory for Radiological Protection, Warsaw, shows its activities in 1994-1995. The general information and organization of CLOR have been performed in the opening part of the report. The second part contains extended abstracts of scientific activities especially in: environmental radioactivity monitoring, supervision and control of the users of radioactive sources, dosimetry problems, calibration and standardization of dosimetric equipment, radiobiology and radiological hazard assessment. The report also includes the full list of publications of CLOR scientific staff issued in the period of 1994-1995.

  4. Bi-annual report 1992-1993. Operational and research activities of Central Laboratory for Radiological Protection

    International Nuclear Information System (INIS)

    1994-06-01

    Bi-annual report of Central Laboratory for Radiological Protection, Warsaw shows its activities in 1992-1993. The general information and organization of CLOR have been shown in the first part of the report. The second part contains extended abstracts of scientific activity, especially in: environmental radioactivity monitoring, supervision and control of the users of radioactive sources, personal dosimetry, calibration and periodical control of dosimetric equipment, radiobiology and radiological hazard assessment. The report also includes the full list of publications of scientists of CLOR issued in the period of 1992-1993

  5. Bi-annual report 1992-1993. Operational and research activities of Central Laboratory for Radiological Protection

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-06-01

    Bi-annual report of Central Laboratory for Radiological Protection, Warsaw shows its activities in 1992-1993. The general information and organization of CLOR have been shown in the first part of the report. The second part contains extended abstracts of scientific activity, especially in: environmental radioactivity monitoring, supervision and control of the users of radioactive sources, personal dosimetry, calibration and periodical control of dosimetric equipment, radiobiology and radiological hazard assessment. The report also includes the full list of publications of scientists of CLOR issued in the period of 1992-1993.

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

    International Nuclear Information System (INIS)

    Mueller, P.G.

    2000-01-01

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

  7. Monitoring in radiological protection scheme; Pemonitoran dalam skim perlindungan radiologi

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1988-12-31

    The chapter briefly discussed the following subjects: function and responsibility of the monitoring, planning of monitoring programme i.e working area for external radiation, monitoring of workers for external radiation, monitoring of working area for surface contamination, monitoring of working area for air contamination, monitoring of workers for internal contamination, and the evaluation of monitoring results.

  8. A new approach to authorization in the field of radiological protection

    International Nuclear Information System (INIS)

    2003-01-01

    Approaches to radiological protection have been evolving, particularly over the past several years. This has been driven by the emergence of modern concepts of and approaches to risk governance, and by calls from within the radiological protection community for the simplification and clarification of the existing system of protection, as based on the Recommendations of the International Commission on Radiological Protection (ICRP). The NEA Committee on Radiation Protection and Public Health (CRPPH) has been very active in developing its own suggestions as to how the system of radiological protection should evolve to better meet the needs of policy makers, regulators and practitioners. One of those suggestions is that a generic concept of 'regulatory authorization' of certain levels and types of exposure to radiation should replace the current and somewhat complicated concepts of exclusion, exemption and clearance. It has also been suggested that by characterising emerging sources and exposures in a screening process leading into the authorization process, regulatory authorities could develop a better feeling for the type and scale of stakeholder involvement that would be necessary to reach a widely accepted approach to radiological protection. In order to verify that these suggestions would make the system of radiological protection more understandable, easy to apply, and acceptable, independent consultants have 'road tested' the CRPPH concepts of authorization and characterisation. Their findings, which show that applying these concepts would represent significant improvement, are reproduced herein. Specific approaches for the application of the new CRPPH ideas are also illustrated in this report. (author)

  9. Basic principles of radiological protection

    International Nuclear Information System (INIS)

    Pina, Jorge Luiz Soares de; Fajardo, Patricia Wieland.

    1984-07-01

    The fundamentals of radiological protection are presented. The interaction of radiation with matter and with living systems as well as radioprotection procedures and units are described. 6 refs., 7 figs., 9 tabs of radioactive wastes from nuclear medicine in Brazil are presented. 7 refs., 3 figs., 2 tabs

  10. Federal Radiological Monitoring and Assessment Center Monitoring Manual Volume 1, Operations

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Aerial Measurement Systems

    2012-07-31

    The Monitoring division is primarily responsible for the coordination and direction of: Aerial measurements to delineate the footprint of radioactive contaminants that have been released into the environment. Monitoring of radiation levels in the environment; Sampling to determine the extent of contaminant deposition in soil, water, air and on vegetation; Preliminary field analyses to quantify soil concentrations or depositions; and Environmental and personal dosimetry for FRMAC field personnel, during a Consequence Management Response Team (CMRT) and Federal Radiological Monitoring and Assessment Center (FRMAC) response. Monitoring and sampling techniques used during CM/FRMAC operations are specifically selected for use during radiological emergencies where large numbers of measurements and samples must be acquired, analyzed, and interpreted in the shortest amount of time possible. In addition, techniques and procedures are flexible so that they can be used during a variety of different scenarios; e.g., accidents involving releases from nuclear reactors, contamination by nuclear waste, nuclear weapon accidents, space vehicle reentries, or contamination from a radiological dispersal device. The Monitoring division also provides technicians to support specific Health and Safety Division activities including: The operation of the Hotline; FRMAC facility surveys; Assistance with Health and Safety at Check Points; and Assistance at population assembly areas which require support from the FRMAC. This volume covers deployment activities, initial FRMAC activities, development and implementation of the monitoring and assessment plan, the briefing of field teams, and the transfer of FRMAC to the EPA.

  11. International Commission On Radiological Protection: recommendations relevant to the uranium industry

    International Nuclear Information System (INIS)

    Clement, C.H.

    2010-01-01

    The International Commission on Radiological Protection (ICRP) is an independent, international organization that advances for the public benefit the science of radiological protection, in particular by providing recommendations and guidance on all aspects of protection against ionizing radiation. This presentation touches on aspects of The 2007 Recommendations of the ICRP, a fundamental document that lays out the system of radiological protection for all exposure situations and types, and focuses on other recent publications relevant to the uranium industry. Of particular relevance are the 2009 ICRP Statement on Radon and the accompanying report on lung cancer risk from radon. (author)

  12. Identification and monitoring of non-radiological carcinogens

    Energy Technology Data Exchange (ETDEWEB)

    Chuaqui, C A; Petkau, A; Greenstock, C L; Brown, C P [Atomic Energy of Canada Ltd., Pinawa, MB (Canada). Whiteshell Labs.

    1995-09-01

    This study examines the feasibility of identifying and monitoring occupational exposures to non-radiological carcinogens in the workplace at Canadian nuclear establishments (Whiteshell Laboratories, Pickering Nuclear Generating Station, Cameco Limited and Canadian General Electric Company Limited). Recent epidemiological studies recommended that potential confounding factors of a non-radiological nature be identified and analyzed, particularly non-radiological carcinogens that may be present in the workplace at nuclear facilities. The feasibility of identifying and measuring occupational exposures to non-radiological carcinogens in Canadian nuclear facilities is examined. Also, the report describes the problem of chemical carcinogens and the mechanisms involved in chemical carcinogenesis; the epidemiology related to the problem, followed by a description of the analytical aspects of detection, monitoring and analysis of carcinogens, as well as a discussion on the regulatory aspects and the regulations in place; and the findings, recommendations and concluding remarks of this study. Several problem areas became apparent as the study proceeded. For example, the classification of a chemical as a human carcinogen is a difficult problem, as is its adequate monitoring and analysis. This situation reflects, in turn, the regulatory aspects in the workplace. A list of chemical carcinogens used industrially at the four Canadian nuclear facilities has been identified. The list includes arsenic, asbestos, benzene, cadmium, beryllium, nickel, polychlorinated biphenyls, lead and trichloroethylene. Several recommendations are made in relation to the need for practical and efficient monitoring methods for chemical carcinogens, the definition of radiation and chemical dose equivalencies, and the classification of human chemical carcinogens, as well as their disposal. (author). 122 refs., 8 tabs., 6 figs.

  13. Identification and monitoring of non-radiological carcinogens

    International Nuclear Information System (INIS)

    Chuaqui, C.A.; Petkau, A.; Greenstock, C.L.; Brown, C.P.

    1995-09-01

    This study examines the feasibility of identifying and monitoring occupational exposures to non-radiological carcinogens in the workplace at Canadian nuclear establishments (Whiteshell Laboratories, Pickering Nuclear Generating Station, Cameco Limited and Canadian General Electric Company Limited). Recent epidemiological studies recommended that potential confounding factors of a non-radiological nature be identified and analyzed, particularly non-radiological carcinogens that may be present in the workplace at nuclear facilities. The feasibility of identifying and measuring occupational exposures to non-radiological carcinogens in Canadian nuclear facilities is examined. Also, the report describes the problem of chemical carcinogens and the mechanisms involved in chemical carcinogenesis; the epidemiology related to the problem, followed by a description of the analytical aspects of detection, monitoring and analysis of carcinogens, as well as a discussion on the regulatory aspects and the regulations in place; and the findings, recommendations and concluding remarks of this study. Several problem areas became apparent as the study proceeded. For example, the classification of a chemical as a human carcinogen is a difficult problem, as is its adequate monitoring and analysis. This situation reflects, in turn, the regulatory aspects in the workplace. A list of chemical carcinogens used industrially at the four Canadian nuclear facilities has been identified. The list includes arsenic, asbestos, benzene, cadmium, beryllium, nickel, polychlorinated biphenyls, lead and trichloroethylene. Several recommendations are made in relation to the need for practical and efficient monitoring methods for chemical carcinogens, the definition of radiation and chemical dose equivalencies, and the classification of human chemical carcinogens, as well as their disposal. (author). 122 refs., 8 tabs., 6 figs

  14. Radiological protection aspects of geological disposal of high-level radioactive waste

    International Nuclear Information System (INIS)

    Matsuzuru, Hideo; Kimura, Hideo

    1992-01-01

    A high-level radioactive waste, generated at a nuclear fuel reprocessing plant, will be disposed of deep, i.e., several hundred meters, within geological formations, to isolate it from the human environment. Since the waste contains significant amounts of long-lived radionuclides, such as Tc-99, I-129, Cs-135 and transuranic elements, the safety of its disposal, particularly as regards the requirement for the radiological protection of human and his environment even in the far future, is one of the essential subjects of all countries engaged in nuclear power production. The radiological protection system has long been established and applied to regulate radiation exposures to the public associated with a relatively short-term release of radioactive materials, during normal and accidental conditions, from nuclear installations such as a power plant and reprocessing plant. Radioactive waste disposal, which potentially offers a long-term radiological consequence on the public, inevitably produces a specific requirement, from the standpoint of radiological protection, that individuals and populations in the future should be accorded at least a current level of the protection. This requirement has caused a serious debate, among the community of radiological protection, on how to establish radiological protection standards and criteria, and how to establish safety assessment methodologies to demonstrate compliance with them. We have discussed in this paper on specific items such as numerical guides to indicate radiological consequences, time frames over which calculations of the consequences are to be carried out, uncertainties to be involved in the calculations, and safety assessment methodologies. (author)

  15. Fundamentals of radiological protection

    International Nuclear Information System (INIS)

    Mill, A.J.; Charles, M.W.; Wells, J.

    1978-04-01

    A review is presented of basic radiation physics with particular relevance to radiological protection. The processes leading to the production and absorption of ionising radiation are outlined, and the important dosimetric quantities and their units of measurements. The review is the first of a series of reports presenting the fundamentals necessary for an understanding of the basis of regulatory criteria such as those recommended by the ICRP. (author)

  16. Education and Training in the Field of Radiological Protection

    International Nuclear Information System (INIS)

    Meskens, G.

    2001-01-01

    The International School for Radiological Protection (isRP) was founded within SCK-CEN in 1996 and organises training programmes on radiological protection for nuclear workers and staff. In 2000, isRP organised eleven courses for Belgian and foreign organisations active in the nuclear and non-nuclear field. The report summarises major achievements in 2000 and outlines a number of recent initiates, in particular the development of a distance learning programme

  17. Changes in radiological protection and quality control in Spanish dental installations: 1996-2003.

    Science.gov (United States)

    Alcaraz-Baños, Miguel; Parra-Pérez, María del Carmen; Armero-Barranco, David; Velasco-Hidalgo, Francisco; Velasco-Hidalgo, Esteban

    2009-10-01

    The European Union has established specific directives concerning radiological protection which are obligatory for member States. In addition, all Spanish dental clinics with radiological equipment are required to have an annual quality control check. To analyze the effect of new European legislation on dental radiological practice in Spain and to determine whether it has resulted in lower doses being administered to patients. A total of 10,171 official radiological quality control reports on Spanish dental clinics, covering 16 autonomous regions, were studied following the passing of Royal Decree 2071/1995 on quality criteria in radiodiagnostic installations. The reports, compiled by U.T.P.R Asigma S.A., a company authorised by the Nuclear Safety Council, cover the years 1996 to 2003, which has enabled us to monitor the evolution of radiological procedures in dental clinics over a seven year period. According to the reports for 2003, 77.3 % of clinics complied with EU requirements, using equipment of 70 kVp, 8 mA, 1.5 mm Al filters, with a collimator length of 20 cm. However, non-compliance was detected in approximately a third (30.8%) of the equipment inspected: alterations in the kilovoltage used, exposure time, performance of the tubing, dosage, linearity/intensity of current and acoustic-luminous signal 6.86%. The mean skin dose reached 3.11 mGy for patients who received an x-ray of an upper molar, representing a decrease of 18% over the seven years studied. there has obviously been a general improvement in the parameters studied, but only 77.3% of the installations complied fully with official EU regulations concerning dental radiological protection.

  18. Survey of radiological protection in the A.E.A.: 1979

    International Nuclear Information System (INIS)

    Lomer, W.M.

    1979-10-01

    The practices and achievements of the radiological protection systems of the U.K.A.E.A. have been critically examined in the light of the report made by Sir Edward Pochin on Aldermaston practices. Aspects examined include the responsibilities and organisation for health and safety, sources of potential exposure, working procedures and monitoring, and health physics staffing and training. It is found that many of the criticisms made in Pochin's report do not apply to the existing conditions in the U.K.A.E.A. Several points are identified where procedures should be re-examined by managements and where improvements might be sought. The U.K.A.E.A. standards of monitoring and procedures meet all regulatory limits. Finally, a list of detailed recommendations is given. (U.K.)

  19. Radiological protection objectives for the disposal of solid radioactive wastes

    International Nuclear Information System (INIS)

    1983-10-01

    Guidance is given on the standards to be used in the UK in decisions on the radiological acceptability of disposal methods for solid radioactive wastes. The radiological protection objectives given in the report are intended to be applied to all types of solid radioactive waste, and to all the disposal methods which are in use or under consideration. This guidance complements and extends previous Board advice on radiological protection objectives which apply to the control of routine discharges of gaseous and liquid effluents. (author)

  20. e-Learning applications for radiological protection training

    International Nuclear Information System (INIS)

    Gonzalez, F.; Gomez-Arguello, B.; Callejo, J. L.

    2003-01-01

    The unattended training, through e-learning platforms, offers advantages in comparison with the traditional attended training, such as, freedom to study when, where and how the trance desires, the student is learning customization, a continuous self evaluation of the learning process and the rhythm of study, etc. To explore the possibilities of the radiological protection training in a WEB site, a first application for External Workers has been developed. The high number of students, their geographical dispersion and their different level of knowledge and experience arise attended training limitations in this area. In this article, the WEB course Basic Radiological Protection is presented and the results, preliminarily conclusions and lesson learnt are analysed. (Author) 7 refs

  1. Transition in occupational radiation exposure monitoring methods in diagnostic and interventional radiology

    International Nuclear Information System (INIS)

    Loennroth, N.; Hirvonen-Kari, M.; Timonen, M.; Savolainen, S.; Kortesniemi, M.

    2008-01-01

    Radiation exposure monitoring is a traditional keystone of occupational radiation safety measures in medical imaging. The aim of this study was to review the data on occupational exposures in a large central university hospital radiology organisation and propose changes in the radiation worker categories and methods of exposure monitoring. An additional objective was to evaluate the development of electronic personal dosimeters and their potential in the digitised radiology environment. The personal equivalent dose of 267 radiation workers (116 radiologists and 151 radiographers) was monitored using personal dosimeters during the years 2006-2010. Accumulated exposure monitoring results exceeding the registration threshold were observed in the personal dosimeters of 73 workers (59 radiologists' doses ranged from 0.1 to 45.1 mSv; 14 radiographers' doses ranged from 0.1 to 1.3 mSv). The accumulated personal equivalent doses are generally very small, only a few angiography radiologists have doses >10 mSv per 5 y. The typical effective doses are -1 and the highest value was 0.3 mSv (single interventional radiologist). A revised categorisation of radiation workers based on the working profile of the radiologist and observed accumulated doses is justified. Occupational monitoring can be implemented mostly with group dosimeters. An active real-time dosimetry system is warranted to support radiation protection strategy where optimisation aspects, including improving working methods, are essential. (authors)

  2. Training in Radiation Protection for Interventional Radiology

    Energy Technology Data Exchange (ETDEWEB)

    Vano, E.; Guibelalde, E.

    2002-07-01

    Several potential problems have been detected in the safety aspects for the practice of interventional radiology procedures: a) An important increase in the number cases and their complexity and the corresponding increase of installations and specialists involved; b) New X ray systems more sophisticated, with advanced operational possibilities, requiring special skills in the operators to obtain the expected benefits;c) New medical specialists arriving to the interventional arena to profit the benefits of the interventional techniques without previous experience in radiation protection. For that reason, education and training is one of the basic areas in any optimisation programme in radiation protection (RP). the medical field and especially interventional radiology requires actions to promote and to profit the benefit of the new emerging technologies for training (Internet, electronic books, etc). The EC has recently sponsored the MARTIR programme (Multimedia and Audio-visual Radiation Protection Training in Interventional Radiology) with the production of two videos on basic aspects of RP and quality control and one interactive CD-ROM to allow tailored individual training programmes. those educational tools are being distributed cost free in the main European languages. To go ahead with these actions, the EC has decided to promote during 2002, a forum with the main Medical European Societies involved in these interventional procedures. (Author)

  3. Training in Radiation Protection for Interventional Radiology

    International Nuclear Information System (INIS)

    Vano, E.; Guibelalde, E.

    2002-01-01

    Several potential problems have been detected in the safety aspects for the practice of interventional radiology procedures: a) An important increase in the number cases and their complexity and the corresponding increase of installations and specialists involved; b) New X ray systems more sophisticated, with advanced operational possibilities, requiring special skills in the operators to obtain the expected benefits;c) New medical specialists arriving to the interventional arena to profit the benefits of the interventional techniques without previous experience in radiation protection. For that reason, education and training is one of the basic areas in any optimisation programme in radiation protection (RP). the medical field and especially interventional radiology requires actions to promote and to profit the benefit of the new emerging technologies for training (Internet, electronic books, etc). The EC has recently sponsored the MARTIR programme (Multimedia and Audio-visual Radiation Protection Training in Interventional Radiology) with the production of two videos on basic aspects of RP and quality control and one interactive CD-ROM to allow tailored individual training programmes. those educational tools are being distributed cost free in the main European languages. To go ahead with these actions, the EC has decided to promote during 2002, a forum with the main Medical European Societies involved in these interventional procedures. (Author)

  4. Guideline concerning specialist knowledge of radiological protection

    International Nuclear Information System (INIS)

    1991-09-01

    The regulation is to be applied to licenses according to paragraphs 3, 15, 16, 20, 20a of the Radiation Protection Law, paragraphs 6, 7, 9 of the Atomic Law, to notices according to paragraphs 4, 17 of the Radiation Protection Law as well as in the prospecting, mining and processing of radioactive minerals. It regulates the extent and evidence of the special knowledge required for radiation protection of radiological safety officers and personnel responsible for radiation protection. (UK)

  5. Radiological protection in computed tomography and cone beam computed tomography.

    Science.gov (United States)

    Rehani, M M

    2015-06-01

    The International Commission on Radiological Protection (ICRP) has sustained interest in radiological protection in computed tomography (CT), and ICRP Publications 87 and 102 focused on the management of patient doses in CT and multi-detector CT (MDCT) respectively. ICRP forecasted and 'sounded the alarm' on increasing patient doses in CT, and recommended actions for manufacturers and users. One of the approaches was that safety is best achieved when it is built into the machine, rather than left as a matter of choice for users. In view of upcoming challenges posed by newer systems that use cone beam geometry for CT (CBCT), and their widened usage, often by untrained users, a new ICRP task group has been working on radiological protection issues in CBCT. Some of the issues identified by the task group are: lack of standardisation of dosimetry in CBCT; the false belief within the medical and dental community that CBCT is a 'light', low-dose CT whereas mobile CBCT units and newer applications, particularly C-arm CT in interventional procedures, involve higher doses; lack of training in radiological protection among clinical users; and lack of dose information and tracking in many applications. This paper provides a summary of approaches used in CT and MDCT, and preliminary information regarding work just published for radiological protection in CBCT. © The International Society for Prosthetics and Orthotics Reprints and permissions: sagepub.co.uk/journalsPermissions.nav.

  6. Use of the analytical tree technique to develop a radiological protection program

    International Nuclear Information System (INIS)

    Domenech N, H.; Jova S, L.

    1996-01-01

    The results obtained by the Cuban Center for Radiological Protection and Hygiene by using an analytical tree technique to develop its general operational radiation protection program are presented. By the application of this method, some factors such as the organization of the radiation protection services, the provision of administrative requirements, the existing general laboratories requirements, the viability of resources and the current documentation was evaluated. Main components were considered such as: complete normative and regulatory documentation; automatic radiological protection data management; scope of 'on the-job'and radiological protection training for the personnel; previous radiological appraisal for the safety performance of the works and application of dose constrains for the personnel and the public. The detailed development of the program allowed to identify the basic aims to be achieved in its maintenance and improvement. (authors). 3 refs

  7. Radiological protection of the environment from an NGO perspective

    International Nuclear Information System (INIS)

    Carroll, S.

    2008-01-01

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

  8. Federal Radiological Monitoring and Assessment Center Analytical Response

    International Nuclear Information System (INIS)

    Nielsen, E.C.

    2003-01-01

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

  9. Radiological protection criteria risk assessments for waste disposal options

    International Nuclear Information System (INIS)

    Hill, M.D.

    1982-01-01

    Radiological protection criteria for waste disposal options are currently being developed at the National Radiological Protection Board (NRPB), and, in parallel, methodologies to be used in assessing the radiological impact of these options are being evolved. The criteria and methodologies under development are intended to apply to all solid radioactive wastes, including the high-level waste arising from reprocessing of spent nuclear fuel (because this waste will be solidified prior to disposal) and gaseous or liquid wastes which have been converted to solid form. It is envisaged that the same criteria will be applied to all solid waste disposal options, including shallow land burial, emplacement on the ocean bed (sea dumping), geological disposal on land and sub-seabed disposal

  10. Environmental and Radiological Protection Department - DEPRA

    International Nuclear Information System (INIS)

    1989-01-01

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

  11. Evaluation of the conditions and practices of radiological protection technicians in radiology, according to Ordinance 453; Avaliacao das condicoes e das praticas de protecao radiologica dos tecnicos em radiologia, segundo a portaria 453

    Energy Technology Data Exchange (ETDEWEB)

    Costa, Rogerio Ferreira da

    2013-10-01

    Professionals in radiology suffer whole body exposure to low doses for long periods . The system of radiological protection should keep exposures below recommended thresholds, thus avoiding the stochastic effects that can be triggered with any dose level value, and there is not a threshold for induction of the same. Therefore it is important to use personal dosimeter for monitoring doses and protective equipment. The increase in procedures using ionizing radiation in recent years has been noted with concern, since many companies are not complying with the standards of protection. This is because some procedures may be performed without the need of surgery, which presents a greater risk to the patient. Furthermore, Brazilians are being exposed to radiation without necessity. The reasons range from radiological equipment miscalibrated to poorly trained staff. Thus we evaluate the conditions and practices of radiation protection technicians in radiology according to Ordinance 453 in Goiania, GO, Brazil. Through a descriptive survey with a quantitative approach, we used the technique of gathering information based on a questionnaire. From this survey, we identified the procedures used by radiation protection professionals and concluded that there are failures in the procedures for protecting patients and accompanying and in the training of the professionals. (author)

  12. Optimization in radiological protection

    International Nuclear Information System (INIS)

    Acosta Perez, Clarice de Freitas

    1996-01-01

    The optimization concept in radiation protection is, in its essence, practical. In each aspect that we deal with the man, it is necessary to take frequent decisions such as: what is the protection level to be pursued, since the protection levels under consideration provide doses lower than the appropriate annual limits. The optimization gives a basic framework of the minding that is appropriate to conduct to a balance kind of the resources available for the protection and protection level obtained against a multitude of factors and constrains in a manner to obtain the best result. In this work, was performed the optimization, from the radiation protection point of view, of a facility project who enclose two shielded hot cells where will be handled UO 2 small plate with 50% of U-235 burn-up, irradiated in the research swimming pool reactor, IEA-R1. To obtain this goal were specified the relevant factors and criteria, were applied the main techniques used in a decision-making in radiological protection, presently adopted and was performed a sensibility study of the factors and criteria used in this work. In order to obtain a greater agility in applying the techniques for decision-making was developed a micro computer program. (author)

  13. Radiological protection challenges at B.N.G. Sellafield

    International Nuclear Information System (INIS)

    Hallard, R.; Anderson, B.; Hutton, E.

    2006-01-01

    The UK Nuclear Industry is in the midst of a period of intense change with the formation of a national body to manage the clean up of Nuclear facilities. Previous owners of nuclear sites have become contractors and the emphasis has switched from production facilities for power or reprocessing to decommissioning and clean up. Many of the older facilities were not designed for decommissioning and now require attention to reduce risks. Sellafield represents a microcosm of the industry with operating and production facilities, waste storage facilities and plants awaiting or undergoing decommissioning. The experience already gained in decommissioning of redundant facilities over the last decade is being used to develop an accelerated response to clean up of the past. The major challenge is to accommodate the changes whilst monitoring and improving Radiological standards and performance. This paper describes a number of issues to which the site must be managed to ensure that the current Radiological performance is maintained and improved. The dose control arrangements for some 6000 radiation workers on the site requires a change in approach as we move towards localised project based systems with an increasingly mobile workforce. Work is proceeding to introduce a new generation of short term dose control equipment with an emphasis on safety culture and management responsibilities for dose control. The achievement and demonstration of ALARP in these circumstances, is being reviewed in situations where timescale, overall risk to public and workforce and exposure to non radiological hazards are factors. Clean up requires more attention to clearance of materials and this aspect has an increasing profile to recognize the need to balance risk and expenditure. The paper will review the current Radiological Protection challenges to the changing Nuclear Industry using the Sellafield site as the prime example and will discuss achievements and areas where further work is necessary

  14. Enhancement of the radiological protection in the Nuclear Medicine Centres in Peru

    International Nuclear Information System (INIS)

    Lopez, Edith; Gonzales, Susana; Zapata, Luis

    2008-01-01

    Full text: The Laboratory of Internal Dosimetry (LDI) of the Nuclear Energy Peruvian Institute (IPEN) is the laboratory which offers the service of internal dosimetry to the IPEN personnel who works handling non sealed radioactive sources. The Laboratory has participated in several intercomparison exercises featuring in vivo measurements, in vitro methods and dose calculations with acceptable results, which are indicators that the laboratory results are reliable. The National Program of Radiological Protection for occupational exposed workers, who handles non sealed radioactive sources, allows involving the IPEN occupational exposed workers and the Nuclear Medicine Centres Personnel. In Peru, there are 5000 occupational exposed workers, 3500 of them are controlled through external dosimetry. There are approximately 230 occupational exposed workers to non sealed radioactive sources, 67 of them are registered in the National Regulatory Authority and 20 are controlled radiologically. The aim of this study is the enhancement of the radiological safety of the personnel who works in the Nuclear Medicine Centres and handles non sealed radioactive sources. As part of this work, activities addressed to improve the radiological safety of the occupational exposed workers were taken place such as: supply of technical documents about radiological safety, performance of surveys and polls and the organization of a workshop involving the participation of several health professionals working in this field. The situation of the control measures in the radiation protection of the patients and occupational exposed workers, based in updated regulatory documents, have been assessed and it allowed knowing and learning that the occupational exposed workers of the Nuclear Medicine Centres could perform their own monitoring program since they have potential capabilities like Iodine Uptake Systems and calibrated Gamma cameras. This study involves 15 public and private institutions. (author)

  15. Environmental Radiological Impact of Nuclear Power. Monitoring and Control Programs

    International Nuclear Information System (INIS)

    Ramos, L. M.

    2000-01-01

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

  16. A Low-Cost, Real-Time Network for Radiological Monitoring Around Nuclear Facilities

    International Nuclear Information System (INIS)

    Bertoldo, N A

    2004-01-01

    A low-cost, real-time radiological sensor network for emergency response has been developed and deployed at the Lawrence Livermore National Laboratory (LLNL). The Real-Time Radiological Area Monitoring (RTRAM) network is comprised of 16 Geiger-Mueller (GM) sensors positioned on the site perimeter to continuously monitor radiological conditions as part of LLNL's comprehensive environment/safety/health protection program. The RTRAM network sensor locations coincide with wind sector directions to provide thorough coverage of the one square mile site. These low-power sensors transmit measurement data back to a central command center (CCC) computer through the LLNL telecommunications infrastructure. Alarm conditions are identified by comparing current data to predetermined threshold parameters and are validated by comparison with plausible dispersion modeling scenarios and prevailing meteorological conditions. Emergency response personnel are notified of alarm conditions by automatic radio- and computer- based notifications. A secure intranet provides emergency response personnel with current condition assessment data that enable them to direct field response efforts remotely. This system provides a low-cost real-time radiation monitoring solution that is easily converted to incorporate both a hard-wired interior perimeter with strategically positioned wireless secondary and tertiary concentric remote locations. These wireless stations would be configured with solar voltaic panels that provide current to recharge batteries and power the sensors and radio transceivers. These platforms would supply data transmission at a range of up to 95 km from a single transceiver location. As necessary, using radio transceivers in repeater mode can extend the transmission range. The RTRAM network as it is presently configured at LLNL has proven to be a reliable system since initial deployment in August 2001 and maintains stability during inclement weather conditions. With the proposed

  17. Good practices in radiological protection at Narora Atomic Power Station

    International Nuclear Information System (INIS)

    Singh, V.P.; Kumar, Sanjeev; Agrawal, Mitesh; Tiwari, S.K.; Kulhari, Praveen; Gupta, Ashok

    2016-01-01

    Radiological protection performance of nuclear power plant is assessed by collective exposure, individual average exposure, external/external exposure, personnel/surface contamination and reduction of radioactive wastes. Collective exposure is reduced by integrated comprehensive ALARA program in all aspects of nuclear plant operation and maintenance has reduced collective dose many folds. In the present paper, implementation of new good practices in Radiological Protection is presented

  18. Radiologic science for technologists: physics, biology, and protection

    International Nuclear Information System (INIS)

    Bushong, S.C.

    1980-01-01

    The second edition of a textbook primarily for students in radiologic technology is presented. Separate chapters discuss mammography, computed tomography, diagnostic ultrasound, and design of radiologic physics. Radiation protection is specifically presented in two chapters as well as being integrated throughout the text. The fundamentals of radiobiology, molecular and cellular effects of irradiation, and early and late radiation effects comprise four chapters

  19. Development of a real-time extremity dose monitor for personnel in interventional radiology

    International Nuclear Information System (INIS)

    Ban, Nobuhiko; Kusama, Tomoko; Adachi, Akiko

    2000-01-01

    Protection of personnel in interventional radiology is one of the most important issues of radiological protection in medicine. Fluoroscopically guided interventional procedures require the operation near X-ray beam, which brings a considerable hand exposure to the operators. For the purpose of effectual control of their extremity doses, we have developed a real-time extremity dose monitor which is worn on a strap around the wrist. The monitor consists of a silicon semiconductor detector, thin lithium battery and a waterproof frame with a four-digit LED display. Experiment was carried out to examine a response of the monitor to diagnostic X-rays. A practical test was also performed to evaluate usability in the actual interventional procedures. In the experiment, the extremity dose monitor was placed on an arm phantom and exposed to diagnostic X-rays. Readings of the monitor were compared to those of Capintec PS-033 shallow chamber. The monitor was highly sensitive to diagnostic X-rays. It showed a linear response down to doses of a few tens of microsieverts. For high dose-rate exposure, however, a slight decrease in the response was observed, about 10% of counting loss for 80 kV, 40 mA X-ray at one meter from the focus. With regard to energy dependence, variation was within 20% for 60 to 100 kV X-rays. The monitor showed a good angular response in general, except lateral geometry facing the far side from a detector center. In the practical test, hand exposures of medical staff were measured with the extremity dose monitor. They were also asked to fill in a questionnaire regarding size and weight of the monitor, clarity of the display and usefulness. The subjects consisted of physicians, technicians and nurses who engaged in angiography, PTCD, CT-biopsy, barium enema and so on. The readings of the monitor were less than 1 mSv in most cases while 93 mSv was recorded in an extreme case due to direct-beam exposure. In some cases, TLD rings were used together with the

  20. Development of a real-time extremity dose monitor for personnel in interventional radiology

    Energy Technology Data Exchange (ETDEWEB)

    Ban, Nobuhiko; Kusama, Tomoko [Oita University of Nursing and Health Sciences, Oita (Japan); Adachi, Akiko [Oita Medical University, Oita (JP)] [and others

    2000-05-01

    Protection of personnel in interventional radiology is one of the most important issues of radiological protection in medicine. Fluoroscopically guided interventional procedures require the operation near X-ray beam, which brings a considerable hand exposure to the operators. For the purpose of effectual control of their extremity doses, we have developed a real-time extremity dose monitor which is worn on a strap around the wrist. The monitor consists of a silicon semiconductor detector, thin lithium battery and a waterproof frame with a four-digit LED display. Experiment was carried out to examine a response of the monitor to diagnostic X-rays. A practical test was also performed to evaluate usability in the actual interventional procedures. In the experiment, the extremity dose monitor was placed on an arm phantom and exposed to diagnostic X-rays. Readings of the monitor were compared to those of Capintec PS-033 shallow chamber. The monitor was highly sensitive to diagnostic X-rays. It showed a linear response down to doses of a few tens of microsieverts. For high dose-rate exposure, however, a slight decrease in the response was observed, about 10% of counting loss for 80 kV, 40 mA X-ray at one meter from the focus. With regard to energy dependence, variation was within 20% for 60 to 100 kV X-rays. The monitor showed a good angular response in general, except lateral geometry facing the far side from a detector center. In the practical test, hand exposures of medical staff were measured with the extremity dose monitor. They were also asked to fill in a questionnaire regarding size and weight of the monitor, clarity of the display and usefulness. The subjects consisted of physicians, technicians and nurses who engaged in angiography, PTCD, CT-biopsy, barium enema and so on. The readings of the monitor were less than 1 mSv in most cases while 93 mSv was recorded in an extreme case due to direct-beam exposure. In some cases, TLD rings were used together with the

  1. Radiological protection and public health: crossbreeding

    International Nuclear Information System (INIS)

    Smeesters, Patrick; Pinak, Miroslav

    2008-01-01

    Full text: This paper summarizes the scope of activities, ongoing experience and current results of the Expert Group on the Public Health Perspective in Radiological Protection (EGPH) of the Committee of Radiological Protection and Public Health, OECD Nuclear Energy Agency. While the prime and general task of the EGPH group is looking at how the public health and radiation protection can better take an advantage of their respective perspectives, the following four areas have been explored in detail: a) Exposure to radon; b) Justification of medical exposures; c) Public health judgement and decision making based on new scientific evidence; and d) Management of individual differences. In most of these areas, a targeted telephone survey on public policies in selected countries was used for collecting information from stake holders (public, consumers groups, public health and radiation protection regulators, governmental bodies, medical practitioners, patients, scientific communities, NGOs, etc.). The presented paper also highlights key issues of collected information and summarises existing approaches and policies. The case study on exposure to radon collects national information on approaches to the management of domestic radon risks, focusing on the integration of radiation protection and public health aspects (quality of dwellings, overall quality of indoor air, perception of radon levels, position of radon risk in the pool of other risks). In the case of justification of medical exposures, the Group studies the applications of the justification principle in opportunistic screenings (responsibilities, management of the situation, risk assessment). The precautionary principle and its impact on policy judgement in the light of significant scientific uncertainties can have a large influence on radiological-protection decision making. The case study on public health judgement and decision making based on new scientific evidence is exploring how these uncertainties and

  2. Radiological protection and environmental management

    International Nuclear Information System (INIS)

    Perez Fonseca, A.

    2010-01-01

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

  3. Fundamentals of radiological protection

    International Nuclear Information System (INIS)

    Wells, J.; Mill, A.J.; Charles, M.W.

    1978-05-01

    The basic processes of living cells which are relevant to an understanding of the interaction of ionizing radiation with man are described. Particular reference is made to cell death, cancer induction and genetic effects. This is the second of a series of reports which present the fundamentals necessary for an understanding of the bases of regulatory criteria such as those recommended by the International Commision on Radiological Protection (ICRP). Others consider basic radiation physics and the biological effects of ionizing radiation. (author)

  4. Optimal layout of radiological environment monitoring based on TOPSIS method

    International Nuclear Information System (INIS)

    Li Sufen; Zhou Chunlin

    2006-01-01

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

  5. Radiological protection in veterinary practice

    International Nuclear Information System (INIS)

    Konishi, Emiko; Tabara, Takashi; Kusama, Tomoko.

    1990-01-01

    To propose measures for radiological protection of veterinary workers in Japan, X-ray exposure of workers in typical conditions in veterinary clinics was assessed. Dose rates of useful beam and scattered radiation, worker exposure doses at different stations, and effectiveness of protective clothing were determined using TLD and ion chambers. As precausions against radiation, the following practices are important: (1) use of suitable and properly maintained X-ray equipment, (2) proper selection of safe working stations, (3) use of protective clothing. Regulations are necessary to restrict the use of X-rays in the veterinary field. Because the use of X-rays in the veterinary field is not currently controlled by law, the above precautions are essential for minimizing exposure of veterinary staff. (author)

  6. Work management to optimise occupational radiological protection

    International Nuclear Information System (INIS)

    Ahier, B.

    2009-01-01

    Although work management is no longer a new concept, continued efforts are still needed to ensure that good performance, outcomes and trends are maintained in the face of current and future challenges. The ISOE programme thus created an Expert Group on Work Management in 2007 to develop an updated report reflecting the current state of knowledge, technology and experience in the occupational radiological protection of workers at nuclear power plants. Published in 2009, the new ISOE report on Work Management to Optimise Occupational Radiological Protection in the Nuclear Power Industry provides up-to-date practical guidance on the application of work management principles. Work management measures aim at optimising occupational radiological protection in the context of the economic viability of the installation. Important factors in this respect are measures and techniques influencing i) dose and dose rate, including source- term reduction; ii) exposure, including amount of time spent in controlled areas for operations; and iii) efficiency in short- and long-term planning, worker involvement, coordination and training. Equally important due to their broad, cross-cutting nature are the motivational and organisational arrangements adopted. The responsibility for these aspects may reside in various parts of an installation's organisational structure, and thus, a multi-disciplinary approach must be recognised, accounted for and well-integrated in any work. Based on the operational experience within the ISOE programme, the following key areas of work management have been identified: - regulatory aspects; - ALARA management policy; - worker involvement and performance; - work planning and scheduling; - work preparation; - work implementation; - work assessment and feedback; - ensuring continuous improvement. The details of each of these areas are elaborated and illustrated in the report through examples and case studies arising from ISOE experience. They are intended to

  7. Federal Radiological Monitoring and Assessment Center. The analytical response

    International Nuclear Information System (INIS)

    Nielsen, E.C.

    2005-01-01

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

  8. Radiological monitoring of northern slopes of Mogoltau

    International Nuclear Information System (INIS)

    Murtazaev, Kh.; Boboev, B.D.; Bolibekov, Sh.; Akhmedov, M.Z.

    2010-01-01

    Present article is devoted to radiological monitoring of northern slopes of Mogoltau. The physicochemical properties of water of northern slopes of Mogoltau were studied. The radiation monitoring of northern slopes of Mogoltau was carried out during several years under various weather conditions. The exposure rate of human settlements of northern part of Mogoltau was defined.

  9. Protecting people against radiation exposure in the event of a radiological attack

    International Nuclear Information System (INIS)

    Valentin, J.

    2005-01-01

    This report responds to a widely perceived need for professional advice on radiological protection measures to be undertaken in the event of a radiological attack. The report, which is mainly concerned with possible attacks involving 'radioactive dispersion devices', re-affirms the applicability of existing ICRP recommendations to such situations, should they ever occur. Many aspects of the emergency scenarios expected to arise in the event of a radiological attack may be similar to those that experience has shown can arise from radiological accidents, but there may also be important differences. For instance, a radiological attack would probably be targeted at a public area, possibly in an urban environment, where the presence of radiation is not anticipated and the dispersion conditions commonly assumed for a nuclear or radiological emergency, such as at a nuclear installation, may not be applicable. First responders to a radiological attack and other rescuers need to be adequately trained and to have the proper equipment for identifying radiation and radioactive contamination, and specialists in radiological protection must be available to provide advice. It may be prudent to assume that radiological, chemical, and/or biological agents are involved in an attack until it is proven otherwise. This calls for an 'all-hazard' approach to the response. In the aftermath of an attack, the main aim of radiological protection must be to prevent the occurrence of acute health effects attributable to radiation exposure (termed 'deterministic' effects) and to restrict the likelihood of late health effects (termed 'stochastic' effects) such as cancers and some hereditable diseases. A supplementary aim is to minimise environmental contamination from radioactive residues and the subsequent general disruption of daily life. The report notes that action taken to avert exposures is a much more effective protective measure than protective measure the provision of medical treatment

  10. Recommendations of the AIRP-SEFP-SFPR working group individual radiological monitoring document-dosimetric data base

    International Nuclear Information System (INIS)

    Litido, M.; Busuoli, G.; Pelliccioni, M.; Iniiguez Saez, J.; Dollo, R.

    1996-01-01

    On the initiative of the chairmen of the three radiation protection societies (Italian, French, Spanish), it has been decided to extend the study carried out at TAORMINA (Sicily, Italy) joint conference on the harmonization of radiation protection practices. In order to formulate proposals on this topic, a working group was created at the end of 1993 made up of representatives of each society, with the objective of harmonizing the individual radiological monitoring documents and methods of recording and managing dosimetric information in data banks. (author)

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

    International Nuclear Information System (INIS)

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

    1983-01-01

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

  12. Scientific issues and emerging challenges for radiological protection

    International Nuclear Information System (INIS)

    2007-01-01

    Scientific knowledge is constantly evolving as more advanced technologies become available and more in-depth research is carried out. Given the potential implications that new findings could have on policy decisions, in 1998 the NEA Committee on Radiation Protection and Public Health (CRPPH) performed a survey of state-of-the-art research in radiological protection science. This study suggested that, while the current system of radiological protection was well under-pinned by scientific understanding, growing knowledge in several areas could seriously impact policy and regulation. Ten years later, the CRPPH has again performed a survey of state-of-the-art research which reiterates and clarifies its earlier conclusions. This report summarises the results of this latest CRPPH assessment of radiological protection science. Specifically, it explains that knowledge of non-targeted and delayed effects, as well as of individual sensitivity, have been significantly refined over the past ten years. Although at this point there is still no scientific certainty in these areas, based on the most recent studies and results, the report strongly suggests that policy makers and regulatory authorities should consider possible impacts that could arise from research in the next few years. Further, the report identifies research areas that should be supported to more definitively answer scientific questions having the most direct impacts on policy choices. (author)

  13. Radiation protection in the intervenmtional radiology

    International Nuclear Information System (INIS)

    Becker, Benjamin V.; Lissek, Friedrich; Waldeck, Stephan

    2017-01-01

    Interventional radiology and neuroradiology covers a variety of diagnostic and therapeutic methods. A minimal invasive percutaneous access under imaging guidance is common for all these methods. The legal regulations for quality assurance are reviewed, technical possibilities for dose reduction and the importance of modern radiation protection procedures are discussed.

  14. Radiological monitoring of food on the French territory

    Energy Technology Data Exchange (ETDEWEB)

    Boissieux, T.; Leprieur, F.; Pierrard, O. [Institute for Radiological Protection and Nuclear Safety (France)

    2014-07-01

    Drink the milk of cows grazing near French nuclear power plants is it really safe in normal times? In case of a nuclear accident leading to release in the environment, what kind of foodstuff can we still eat? In his regulatory mission of environmental monitoring, the French Institute for Radiological Protection and Nuclear Safety (IRSN) tends to answer these questions by acquiring radioactivity data in the food chain. Food radiological monitoring program by IRSN is implemented with a three scale strategy. Locally, i.e. within the range 0 to 10 kilometers of nuclear installations, foodstuff locally produced and thus potentially exposed to radioactive sources are frequently sampled and analyzed. At the regional level, specific studies are carried out to establish an updated levels baseline of radioactivity in the environment, especially in agricultural productions characteristic of the area concerned. At the national level, monitoring food aims to map the average contamination observed all around the French territory. This work of vigilance is organized in partnerships with other French actors involved in food monitoring. In the event of a nuclear accident or small-scale incidents, it would allow having an efficient support network of samplers and measurers located on the whole French territory and quickly mobilized in short or medium terms. Since 2008, IRSN has developed a food monitoring program with the Directorate general for food (DGAL) and the Directorate general for competition policy, consumer affairs and fraud control (DGCCRF). These directions have a general mission of food safety control (animal and plant products) and animal feed-stuff, which requires the search for chemical, physical, biological and radioactive substances. Likewise, a sampling program of grain products is efficient since 1969 with the support of France Agrimer. In 2013, the food monitoring is based on multi-radionuclides analysis (cesium, iodine, tritium, alpha emitters...) in about 650

  15. Role and responsibilities of medical physicists in radiological protection of patients

    International Nuclear Information System (INIS)

    Niroomand-Rad, A.

    2001-01-01

    The paper provides a brief history of the International Organization for Medical Physics (IOMP), followed by some general comments on the radiological protection of patients. The importance of establishing scientific guidelines and professional standards is emphasized, as is the need to ensure the protection of patients undergoing radiation therapy. The responsibility of qualified medical physicists in the protection of patients in nuclear medicine and in diagnostic and interventional radiology is also discussed. (author)

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

    International Nuclear Information System (INIS)

    1992-10-01

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

  17. Radiological protection worker: occupational medical aspects

    International Nuclear Information System (INIS)

    Mora Ramirez, Erick

    2008-01-01

    International Organizations involved with radiation protection are presented in the first part. Also some documents related to the radiation that have been published by these organizations. Among the analyzed contents are the radiation and their patients, how to avoid the damage of radiation, pregnancy and exposure to medical radiation, effects of radiation, recommendations for the protection and safety standards. Occupational exposure is defined as the exposure received and understood by a worker during a period of work. In addition, it shows the types of occupational exposure, the protection that workers must have with the radiation, regulations, laws and the regulatory authority that protects the medical personnel in the uses of radiology [es

  18. Radiological Emergency Response Data

    Data.gov (United States)

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

  19. Radiological protection program in x-ray diagnostic facilities

    International Nuclear Information System (INIS)

    Melara F, N.E.

    1996-01-01

    This paper presents a basic document to initiate a discussion which will originate a Unified Protocol in Latin America and the Caribbean for radiological protection in the installations of medical radiology. The following principal elements are considered an inherent part of radiology protection: 1. Quality control of equipment. 2. Conditions in the dark room which coincide in the quality of the image. Levels of patient exposure and the processes for the quality control of the processors are not discussed, and it is limited to the installation of radiographic medical x-ray equipment, stationary and mobile. Each point to be put into effect is presented in a diagram, frequency and criteria for acceptance. A detailed explanation of each point along with a clear explanation of the recommended method for each follows in the same order in which they are presented in the diagram. Finally adequate forms for easily acquiring data are presented. (author)

  20. The R+D radiological protection program in the European Communities

    International Nuclear Information System (INIS)

    Mingot Buades, F.

    1993-01-01

    The R+D program a radiological protection for the year 1992 has lied basically on three areas: I .- Radiological exposure of man II .- Radiation effects on man (evaluation, prevention and treatment) III.- Risks and management of radiation exposure

  1. Radiological Protection in Medicine

    International Nuclear Information System (INIS)

    Valetin, J.

    2011-01-01

    This report was prepared to underpin the Commission's 2007 Recommendations with regard to the medical exposure of patients, including their comforters and carers, and volunteers in biomedical research. It addresses the proper application of the fundamental principles (justification, optimisation of protection, and application of dose limits) of the Commission's 2007 Recommendations to these individuals. With regard to medical exposure of patients, it is not appropriate to apply dose limits or dose constraints, because such limits would often do more harm than good. Often, there are concurrent chronic, severe, or even life-threatening medical conditions that are more critical than the radiation exposure. The emphasis is then on justification of the medical procedures and on the optimisation of radiological protection. In diagnostic and interventional procedures, justification of procedures (for a defined purpose and for an individual patient), and management of the patient dose commensurate with the medical task, are the appropriate mechanisms to avoid unnecessary or unproductive radiation exposure. Equipment features that facilitate patient dose management, and diagnostic reference levels derived at the appropriate national, regional, or local level, are likely to be the most effective approaches. In radiation therapy, the avoidance of accidents is a predominant issue. With regard to comforters and carers, and volunteers in biomedical research, dose constraints are appropriate. Over the last decade, the Commission has published a number of documents that provided detailed advice related to radiological protection and safety in the medical applications of ionising radiation. Each of the publications addressed a specific topic defined by the type of radiation source and the medical discipline in which the source is applied, and was written with the intent of communicating directly with the relevant medical practitioners and supporting medical staff. This report

  2. Contribution to the optimization of worker's radiological protection in a uranium mine

    International Nuclear Information System (INIS)

    Lombard, J.; Oudiz, A.; Zettwoog, P.

    1984-04-01

    This report presents the results of an optimization study dealing with radiological protection in a uranium mine. The modelization of alpha contamination associated with short-lived radon daughter in a mine branch allows the comparison of various protection strategies by a cost-effectiveness analysis in view of determining the ''optimal'' protection strategy. The study points out the interest of the optimization procedure as a decision-aiding tool within the framework of radiological protection [fr

  3. Radiologic protection in intensive therapy units; Protecao radiologica em unidades de terapia intensiva

    Energy Technology Data Exchange (ETDEWEB)

    Andrea, H.; Juliana, C.; Gerusa, R.; Laurete, M.B.; Suelen, S., E-mail: andrea.huhn@ifsc.edu.br, E-mail: juliana@ifsc.edu.br, E-mail: gerusa@ifsc.edu.br, E-mail: laurete@ifsc.edu.br, E-mail: suelen.saraiva@ifsc.edu.br [Instituto Federal de Santa Catarina (IFSC), Florianopolis, SC (Brazil); Derech, Rodrigo D.A., E-mail: dagostiniderech@gmail.com [Policlinica Municipal Sul, Florianopolis, SC (Brazil)

    2013-11-01

    The discovery of X-ray was a great achievement for humanity, especially for the medical community. In Intensive Care Units (ICUs), the RX tests, performed with mobile devices, add immense value to the diagnosis of inpatients who do not have the option to carry them out of bed. Following the technology and its improvements, fatalities arose from misuse of ionizing radiation, which mostly gave up for lack of knowledge of the biological effects caused by them, which leads to fear among professionals and often prevents a quick job and effectively by professionals of radiological techniques. The research it is a systematic review of the literature and justified by the scarcity of materials that reflect on the radiological protection in ICUs. For this study we found the Virtual Health Library (VHL) and Pubmed were indexed terms radiological protection and intensive care units, the search in Portuguese and English terms were used radiological protection and intensive care unit. The study aims to inform professionals of ICUs on the main aspects that refer to X-rays in hospital beds, the standards of radiological protection and personal protective equipment, thus avoiding possible damage to the biological health of workers, addressing subjects in rules and laws about the X radiation, emphasizing the protection of professionals in intensive care. It is clear, finally, that little research is conducted in the context of radiological protection of workers ICU's and this is a place that receives daily RX equipment, deserving more attention to protect the worker. (author)

  4. Main radiation protection actions for medical personnel as primary responders front of an event with radiological dispersive device

    International Nuclear Information System (INIS)

    Duque, Hildanielle Ramos

    2015-01-01

    After the terrorist attack in New York, USA, in 2001, there was a worldwide concern about possible attacks using radioactive material in conventional detonators, called as Radiological Dispersal Device (RDD) or 'dirty bomb'. Several studies have been and are being made to form a global knowledge about this type of event. As until now, fortunately, there has not been an event with RDD, the Goiania Radiological Accident in Brazil, 1987, is used as a reference for decision-making. Several teams with technical experts should act in an event with RDD, but the medical staffs who respond quickly to the event must be properly protected from the harmful effects of radiation. Based on the radiological protection experts performance during the Goiania accident and the knowledge from lessons learned of many radiological accidents worldwide, this work presents an adaptation of the radiation protection actions for an event with RDD that helps a medical team as primary responders. The following aspects are presented: the problem of radioactive contamination from the explosion of the device in underground environment, the actions of the first responders and evaluation of health radiation effects. This work was based on specialized articles and papers about radiological accidents and RDD; as well as personal communication and academic information of the Institute of Radiation Protection and Dosimetry. The radiation protection actions, adapted to a terrorist attack event with RDD, have as a scenario a subway station in the capital. The main results are: the use of the basic radiation protection principle of time because there is no condition to take care of a patient keeping distance or using a shielding; the use of full appropriate protection cloths for contaminating materials ensuring the physical safety of professionals, and the medical team monitoring at the end of a medical procedure, checking for surface contamination. The main conclusion is that all medical actions

  5. Radiological safety and control

    Energy Technology Data Exchange (ETDEWEB)

    Chang, Sea Young; Yoo, Y S; Lee, J C; Lee, T Y; Lee, J L; Kim, B W; Lee, B J; Chung, K K; Chung, R I; Kim, J S; Lee, H S; Han, Y D; Lee, J I; Lee, K C; Yoon, J H; Sul, C W; Kim, C K; Yoon, K S; Seo, K W; Yoon, Y C [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1996-01-01

    This report describes the annual results of radiological safety and control program of 1995. This program consists of working area monitoring including HANARO, personnel radiation monitoring, education for radiation protection. As a result, the objectives of radiation protection have been achieved satisfactorily through the activities mentioned above. Also, the calibration services were provided to insure accurate radiation measurement in the radiation working places. 21 figs., 39 tabs., 5 refs. (Author) .new.

  6. Training in radiological protection - a pool of practical exercises

    International Nuclear Information System (INIS)

    Croft, J.R.; Hudson, A.P.

    1981-01-01

    Courses in Radiological Protection have been organised at Leeds by the NRPB since its formation, and prior to that by the Leeds Centre of the Radiological Protection Service. From the outset it seemed essential that such courses should contain a practical element, and accordingly a number of exercises were drawn up. Since that time further exercises have been added, often in response to a specific requirement from a customer or group of customers. Most of the exercises have involved the design and construction of 'one-off' items of equipment, a number of which can be considered to represent interesting approaches towards radiological protection teaching. The construction of a 'second generation' of hardware has focused attention on the objectives and design features of the exercises, which in turn has prompted a desire to publish a series of short papers describing the pool of exercises that is currently available for inclusion in the various courses run by the NRPB Centres. The first of these papers puts the series into context and provides a background to the descriptions of specific exercises. (author)

  7. Fundamentals of radiological protection

    International Nuclear Information System (INIS)

    Charles, M.W.; Wells, J.; Mill, A.J.

    1978-04-01

    A brief review is presented of the early and late effects of ionising radiation on man, with particular emphasis on those aspects of importance in radiological protection. The terminology and dose response curves, are explained. Early effects on cells, tissues and whole organs are discussed. Late somatic effects considered include cancer and life-span shortening. Genetic effects are examined. The review is the third of a series of reports which present the fundamentals necessary for an understanding of the basis of regulatory criteria, such as those of the ICRP. (u.K.)

  8. STRAPIR, an European initiative for optimizing radiation protection in interventional radiology

    International Nuclear Information System (INIS)

    Vano, E.; Gonzalez, L.; Loon, R. van; Padovani, R.; Maccia, C.; Eggermont, G.

    1997-01-01

    In 1995, a European initiative for optimizing radiation protection in interventional radiology was proposed by 8 research groups. The project acronym was STPAPIR (Staff Radiation Protection in Interventional Radiology). Interventional Radiology involves an important number of specialists and their risk level is not well known, since dosimetric records exhibit important discrepancies. Many professionals using these techniques are not radiologists and the basic rules of radiation protection, known by radiologists, are not always correctly and completely followed, hence the use of protection devices is not as regular as desirable. Additionally, x-ray systems not specifically designed for interventional procedures are still used in many hospitals, what entails a significant occupational risk increase to the specialists. Some relevant questions for regulatory bodies are presented, namely, reliability of the actual data banks for occupational dosimetry, use of two personal dosimeters for assessing effective dose, actions to strengthen the systematic use of personal dosimeters and protection tools, proposals for specific training in radiation protection and use of x-ray systems specifically designed for interventional procedures, publication of reports about accidents and incidents, are also discussed. (author)

  9. Public competitive examination for radiology technologist: knowledge in radiation protection required in Brazil

    International Nuclear Information System (INIS)

    Oliveira, J.S.; Silva, K.R.; Gomes, A.S.

    2017-01-01

    Ionizing radiations are used in areas such as health, industry and safety, not only in the private sector, but also in the public. Thus, it is necessary the radiological protection, a set of studies and practices that increases the safety in these applications, where the professional involved is the technologist in radiology. The objective was to analyze the contents effectively required by the Brazilian public agencies in their competitions for radiology technologist, regarding the area of radiological protection, identifying their profile of requirement. It consisted of three stages: first, a survey of all the public competitions already carried out in the country up to the end of 2016, that requested a diploma of graduation in Technology in Radiology; second, all the specific questions were collected and grouped in an electronic text file; third, issues involving radiological protection were segregated, using as reference the 2017 edition of the National Nuclear Energy Commission's General Proof of Radioprotection Supervision. The results showed that almost 40% of the competition questions were about radiation protection. From this sampling, the topics most covered were: radiological safety (36%), fundamentals of atomic and nuclear physics (24%) and biological effects of radiation (16%). It is concluded that the competitions for radiologist technologist have the profile of concentration of exigency in radiological safety, fundamentals of atomic and nuclear physics and biological effects of the radiations

  10. History of the radiological protection in Mexico

    International Nuclear Information System (INIS)

    Ortiz M, J. R.

    2008-12-01

    The beginning in the use of the ionizing radiations goes back towards end of 19 century, when Wilhelm Roentgen discovers x-rays in 1985, finding that quickly founds also the new technology, which spreads to tabs of multiple applications anywhere in the world, some of very beneficial them of use like the radio diagnosis, but others of frivolous and commercial kind. As much in the beneficial uses as in the banal ones, the world also is begun to be aware that the ionizing radiations are a physical element that must be handled with precaution then also can induce injuries in the involved people, which is documented already in 1912. This characteristic is confirmed with the use of Radio-226 as source of ionizing radiation, in whose applications were observed some deleterious effects, which forces to take some measures of protection an intuitive and rather incipient way. The first attempt of limit was denominated erythema dose, that it was a concept of qualitative-subjective character when it is observed a reddening of the skin of the radiated zone. Just a short time later, with the invention of the detector Geiger and the possibility of measuring the radiation quantity received by the people, the limits are transformed into quantitative. lt is as well as it is born the radiological protection like scientific and technological discipline, and essential ally of the nuclear energy pacific applications , event in which the international organizations related to the subject play a very important role, in the middle of the 1920 decade. Since then radiological protection (RP) is in permanent evolution, keeping a balance between the people protection, the sources security and the benefits of the ionizing radiations applications. In Mexico, the nuclear energy taking height from the second half of 1950, when the National Commission of Nuclear Energy was created, it spent in his first years to functions that mainly were of investigation, but in which already appeared the RP like

  11. Radiological monitoring plan for the Oak Ridge Y-12 Plant: Surface water

    International Nuclear Information System (INIS)

    1995-01-01

    National Pollutant Discharge Elimination System (NPDES) Permit TN0002968, issued April 28, 1995, requires that the Y-12 Plant Radiological Monitoring Plan for surface water be modified (Part 111-H). These modifications shall consist of expanding the plan to include storm water monitoring and an assessment of alpha, beta, and gamma emitters. In addition, a meeting was held with personnel from the Tennessee Department of Environment and Conservation (TDEC) on May 4, 1995. In this meeting, TDEC personnel provided guidance to Y-12 Plant personnel in regard to the contents of the modified plan. This report contains a revised plan incorporating the permit requirements and guidance provided by TDEC personnel. In addition, modifications were made to address future requirements of the new regulation for radiation protection of the public and the environment in regards to surface water monitoring

  12. The protection of on-site personnel in the event of a radiological accident

    International Nuclear Information System (INIS)

    Morrey, M.; Simister, D.N.

    2003-01-01

    The National Radiological Protection Board (NPRB) is responsible in the UK for advising Government and other responsible bodies on the principles for responding to radiological emergencies. NRPB has published appropriate advice on the off-site protection of the public and on the protection of workers involved in taking mitigating actions to reduce the exposure of others. This paper puts forward a suggested framework for the protection of on-site personnel in the event of a radiological emergency which might include a criticality accident. This framework both dovetails with existing planning for the protection of members of the public off-site, and also takes account of specific differences between the situations on and off-site. (author)

  13. The provision of radiological protection services

    International Nuclear Information System (INIS)

    1965-01-01

    This publication is a code of practice for the provision or radiological protection services for establishments in which, or in part of which, work is primarily with radiation sources. It was prepared with the help of an international panel of experts and representatives of international organizations which have an interest in this field and was promulgated by the Director General of the Agency under the authority of the Board of Governors of the Agency as a code of practice in the framework of the Agency's Safety Standards. The Board of Governors also authorized the Director General to recommend to Member States that the code of practice be taken into account in the formulation of national regulations or recommendations. The Appendix to the code contains a number of examples of the organization of radiological protection services that have been provided by the members of the panel of experts. These examples do not form a part of the code of practice, but are intended to illustrate the methods of organization which have been adopted in different countries.

  14. Implications of tissue reactions for radiological protection

    International Nuclear Information System (INIS)

    Miyazaki, S.

    2013-01-01

    Cancer effects and risks at low doses from ionising radiation have been main issues within the field of radiological protection. In contrast, non-cancer effects and risks at low doses from ionising radiation are controversial topics within the field of radiation protection. These issues are discussed in ICRP Publication 118, 'ICRP Statement on Tissue Reactions.' Both non-cancer effects and risks are expected to become increasingly important to the system of radiation protection. Before this can happen, several factors must be considered: thorough characterization of the relationship between dose and risk; verification of the biological mechanisms for any noted excess risk; and adjustment of noted excess risks through the use of a detriment factor. It is difficult to differentiate the relatively small risks associated with radiation from other risk factors in the low-dose region of the dose response curve. Several recent papers also indicate the possibility of a non-linear dose response relationship for non-cancer effects. In addition, there are still many uncertainties associated with the biological mechanisms for non-cancer effects. Finally, it is essential to consider the incorporation of detriment into a well-defined system of radiological protection. Given the recent interest in non-cancer effects, it is essential to facilitate discussions in order to more clearly define dose limits within the existing system of radiation protection for both cancer and non-cancer effects. (author)

  15. Radiological protection and safety in medicine

    International Nuclear Information System (INIS)

    Anon.

    1998-01-01

    Here is presented a book published by ICRP ( International Commission Radiological Protection) that exposes the base principles of radiation protection, especially in medical sector. The exposure to ionizing radiations in medicine concerns the persons that profit by a diagnosis or a treatment but also the medical personnel, the patients family and the public. This publication 'CIPR 73' is more particularly adapted to the physicists and physicians implied in radiotherapy, medical imaging, in nuclear medicine and dentistry. It is also useful for the hospital establishments managers and to concerned national authorities. (N.C.)

  16. Development of a Data acquisition node for the environmental radiological monitoring network

    International Nuclear Information System (INIS)

    Benitez S, R.

    2000-01-01

    This work consists in the development of a data acquisition system related to the radiation levels of each one of the laboratories or installations of the ININ, setting up an interconnection of the existing radiological monitoring system (RMS-II), with a personal computer through the use and programming of a data acquisition card (PC-LPM-16). This system works in real time, presenting on the PC screen the measurement of each one of the connected detectors, the alarm signals that are being had been when the allowed levels have been exceeded and the registry of these alarm levels; for their later processing in rapidity graphs of exposure against time. Also aspects such as : brief history of the ionizing radiations and their nature, their interaction with matter and the method which were discovered are treated as well as how it is possible to detect and to measure them. The radiological protection and the standards on which that is based. The RMSII radiation monitoring system and its calibration as well as the obtention of performance curves are treated too. Finally, it is described the performance of the Data acquisition circuit, the based programming in virtual instrumentation and its importance. (Author)

  17. Legal provisions governing liquid effluents radiological monitoring

    International Nuclear Information System (INIS)

    Gans, I.; Ruehle, H.

    1985-01-01

    The KTA rule 1504 for radiological monitoring of liquid effluents from nuclear installations is explained. As there are no such rules published to date for establishments handling isotopes, some criteria are discussed which in the future ought to form part of a practical guide for liquid effluents monitoring in isotope handling installations. Monitoring measures described refer to liquid effluents from transfer containers, auxiliary cooling equipment, turbine buildings, main cooling installations, and waste air discharges from closed-circuit cooling systems. (DG) [de

  18. Radiological protection and nuclear power plants

    International Nuclear Information System (INIS)

    Delpla, M.

    Dosimetric results obtained inside and outside nuclear power plants are examined with a review to proposing revision of the radiological protection standards. Dose limits are considered with regard to leukemia and genetic effects. Other topics discussed are: observed collective damage and mean risk; lethal exposure; healing and sign change of additional risk; and genetic effects of radiation on mice

  19. Radiological protection and radioactive waste management aspects of the decommissioning of redundant nuclear facilities at the Rosyth Dockyard, UK

    International Nuclear Information System (INIS)

    Kerr, Robert W.; Murdo Murray; Hunter Common

    2008-01-01

    The Rosyth Dockyard is located near the city of Edinburgh in Scotland. The dockyard's nuclear activities centred around the refuelling and refitting of submarines, as well as some submarine decommissioning. In 1993, submarine refitting work was transferred to Devonport in Southern England. This meant that there were a number of facilities at the Rosyth Dockyard that were now redundant. In accordance with UK government policy a programme of works was instigated to allow for the decommissioning of these nuclear liabilities. This paper provides a brief overview of work activities performed to allow physical decommissioning to take place. Topics covered include radiological characterisation activities, development of monitoring protocols for decommissioning, obtaining relevant environmental authorisations, developing a decommissioning safety case, gaining the UK's Nuclear Installations Inspectorate approval to proceed with decommissioning and an overview of some of the post operative clean out (POCO) activities performed. Edmund Nuttall Ltd were contracted to perform the physical decommissioning of the redundant nuclear facilities, that have been subject to POCO, and this work commenced in February 2006. As part of this contract they were to provide a radiological protection infrastructure including dosimetry and health physics monitoring. This paper discusses the radiological protection infrastructure established by the decommissioning contractor, the radiological protection aspects of the decommissioning work, some of the tools and techniques utilised to date during the nuclear decommissioning, and the radioactive waste management processes established for the project. All activities are referenced to relevant aspects of UK nuclear industry best practice and to the Scottish, UK and European regulatory framework. The progress to date is discussed and lessons that have been learnt are highlighted. (author)

  20. Guidelines for training and qualification of radiological protection technicians

    International Nuclear Information System (INIS)

    1987-08-01

    These guidelines, used in combination with plant-specific job analysis, provide the framework for a training and qualification program for radiological protection technicians at nuclear power plants. Radiological protection technicians are defined as those individuals, both plant and contractor, who will be engaged in the evaluation of radiological conditions in the nuclear plant and the implementation of the necessary radiological safety measures as they apply to nuclear plant workers and members of the general public. An important aspect of this work is recognizing and handling unusual situations involving radioactivity, including incidents related to degraded core conditions. These guidelines incorporate the results of an industry-wide job analysis and task analysis (JTA) combined with industry operating experience review. However, the industry-wide analyses did not identify all important academic and fundamental knowledge and skills. Further in-depth analysis by subject matter experts produced additional knowledge and skills that were added to these guidelines. All utilities should use these guidelines in conjunction with plant-specific and industry-wide JTA results to develop or validate their radiological protection technician training program. Plant-specific information should be used to establish appropriate training program content. This plant-specific information should reflect unique job duties, equipment, operating experience, and trainee entry-level qualifications. Revisions to these guidelines should be reviewed for applicability and incorporated into the training program using each utility's training system development (TSD) procedures. Plant-specific job analysis and task analysis data is essential to the development of performance-based training programs. These analyses are particularly useful in selecting tasks for training and in developing on-the-job training (OJT), laboratory training, and mock-up training. Qualification programs based on these

  1. Radiological protection of patients

    International Nuclear Information System (INIS)

    Niroomand-Rad, A.

    2003-01-01

    The benefits of ionizing radiation in the diagnosis and treatment of cancer, as well as other conditions such as cardiac ablation, are well established. However determination, monitoring, and evaluation of patient doses is not as easy task. Furthermore, radiation doses for individual patients may vary greatly from one radiological procedure to another. Attention is needed to reduce unnecessary radiation exposure to patients from All types of radiation producing machines and equipment. The patient risk from radiation injury-stochastic and/or deterministic must be weighted against the benefits of a proper medical examination or treatment as well as the risk of depriving the patient from the necessary medical care. Arbitrary reduction of radiological patient doses without regard to final outcome is determined to proper medical care provided to the patient. Sacrificing image quality in order to reduce patient dose is potentially harmful to the patient as well. Furthermore, the role of radiation exposure incurred from screening procedures such as mammography, needs to be properly considered and differentiated from medically indicated procedures. A known radiation induced risk needs to be balanced against diagnostic efficacy of a screening procedure. In these cases, regulations on standards and guidelines for determination, monitoring, and evaluation of patient doses may be appropriate. In this paper, the technical data collected in the United States have been compared with the corresponding data in Canada. However, even here, it has been recognized that we can not assume that one dose limit fits all. It is advisable to consider individual patient specifics if it means the difference between detection and miss

  2. Intervention levels for protective action in the radiological emergency

    International Nuclear Information System (INIS)

    Lee, G.Y.; Khang, B.O.; Lee, M.; Lee, J.T.

    1998-09-01

    In the event of nuclear accident or radiological emergency, the protective action based on intervention levels prepared in advance should be implemented in order to minimize the public hazard. There are several protective measures such as sheltering, evacuation, iodine prophylaxis, foodstuff restrictions, temporary relocation, permanent resettlement, etc. for protecting the public. The protective measures should be implemented on the basis of operational intervention level of action level. This report describes the basic principles of intervention and the methodology for deriving intervention levels, and also recommendations for the intervention levels suggested from IAEA, ICRP, WHO and EU are summarized to apply to the domestic radiological emergency. This report also contains a revision procedure of operational intervention levels to meet a difference accident condition. Therefore, it can be usefully applied to establish revised operational intervention levels considering or the regional characteristics of our country. (author). 20 refs

  3. Protecting people in Ireland from the harmful effects of radiation 2014 to 2015 - The Strategic Plan of the Radiological Protection Institute of Ireland

    International Nuclear Information System (INIS)

    McGarry, A.; McMahon, C.; Pollard, D.; Rafferty, B.; Ryan, T.

    2014-02-01

    This strategic plan has been written in the context of the merger with the Environmental Protection Agency. It addresses the delivery of radiological protection during the period spanning the transition from RPII to the Office of Radiological Protection in the EPA. The plan is focused on priorities for radiological protection and does not deal directly with corporate or support functions

  4. Study of the radiation protection in the radiology services of the Town of Ouagadougou. Actual realities and perspectives

    International Nuclear Information System (INIS)

    Cisse, R.; Lougue, L.C.; Bamouni, Y.A.; Ouedraogo, V.; Siko, A.; Diallo, O.; Ouedraogo, N.; Napon, M.; Zoungrana, R.; Kambou, S.; Tapsoba, T.L.; Sondo, B.

    2005-01-01

    This study has shown numerous factors of risks able to favour occupational irradiations to x radiations in the radiological services. The factors of risks are in relation with the following categories: medical surveillance of the personnel, collective and individual protection, monitoring of occupational exposure to X radiations and the periodic checking of installations. (N.C.)

  5. Research and development in radiological protection; Investigacion y desarrollo en proteccion radiologica

    Energy Technology Data Exchange (ETDEWEB)

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

    2004-07-01

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

  6. The evolution of the system of radiological protection: the programme of the Nea committee on radiation protection and public health

    International Nuclear Information System (INIS)

    Mundigl, S.

    2004-01-01

    The primary aim of radiological protection has always been to provide an appropriate standard of protection for the public and workers without unduly limiting the beneficial practices giving rise to radiation exposure. Over the past few decades, many studies concerning the effects of ionising radiation have been conducted, ranging from those that examine the effects of radiation on individual cells, to epidemiological studies that examine the effects on large populations exposed to different radiation sources. Using information gained from these studies to estimate the consequences of radiation exposure, together with the necessary social and economic judgements, the International Commission on Radiological Protection (ICRP) has put forward a series of recommendations to structure an appropriate system for radiological protection, and to ensure a high standard of protection for the public and for occupational exposed workers. The ICRP system of radiological protection that has evolved over the years now covers many diverse radiological protection issues. Emerging issues have been dealt with more or less on an individual basis resulting in an overall system, which while very comprehensive, is also complex. With such a complex system it is not surprising that some perceived inconsistencies or incoherence may lead to concerns that radiation protection issues are not being adequately addressed. Different stakeholders in decisions involving radiological protection aspects tend to focus on different elements of this perceived incoherence. To advance solutions to these issues, the OECD Nuclear Energy Agency (NEA) has been working for some time to contribute to the evolution of a new radiological protection system, through its Committee on Radiation Protection and Public Health (CRPPH). This group of senior regulators and expert practitioners has, throughout its existence, been interested in the development of recommendations by the ICRP. Recently, this interest has

  7. Radiological protection and environmental monitoring in the area of the Asse mine

    International Nuclear Information System (INIS)

    Meyer, H.; Mueller-Lyda, I.

    1993-01-01

    The personnel at the site has been monitored in accordance with the provisions of the Radiation Protection Ordinance. In addition, ambient dose, ambient dose rate, and radioactivity levels of the air in the mine have been meassured pursuant to the health physics provisions of the Radiation Protection Ordinance. None of the measured results indicated any dose received by the persons, or ambient radioactivity levels, exceeding the maximum permissible values determined for occupational exposure. Continuous monitoring of the mine off-gas has shown a minor accumulation of the nuclides. H-3, C-14, Pb-210 and of the short-lived daughter products of Rn-222 and Rn-220. The average annual emission values serving as input data, the concentration levels computed for the environment of the mine for some part have been below the levels of the naturally occurring concentrations of these nuclides. The emission-induced radiation dose measured at the least favourable place in the plant's vicinity has been far below the maximum permissible dose defined in the Radiation Protection Ordinance. All activities carried out in the Asse salt mine for the purpose of research work and storage of radioactive waste in the period under review have been contributing only a negligible amount to the radiation exposure of the population or personnel, as compared to the natural or other man-made radioactivity levels in that area. (orig.) [de

  8. Training in radiological protection; Capacitacion en proteccion radiologica

    Energy Technology Data Exchange (ETDEWEB)

    Medina G, E., E-mail: medina@ipen.gob.pe [Instituto Peruano de Energia Nuclear, Av. Canada 1470, San Borja, Lima 41 (Peru)

    2014-08-15

    In the Peru, according to the current regulations, people that work with ionizing radiations should have an authorization (individual license), which is granted by the Technical Office of the National Authority that is the technical body of the Instituto Peruano de Energia Nuclear (IPEN) manager of the control of ionizing radiations in the country. The individual license is obtained after the applicant fulfills the requested requirements, as having safety knowledge and radiological protection. Since its founding in 1972, the Centro Superior de Estudios Nucleares (CSEN) of the IPEN has carried out diverse training courses in order to that people can work in a safe way with ionizing radiations in medicine, industry and research, until the year 2013 have been organized 2231 courses that have allowed the training of 26213 people. The courses are organized according to the specific work that is carried out with radiations (medical radio-diagnostic, dental radiology, nuclear medicine, radiotherapy, industrial radiography, nuclear meters, logging while drilling, etc.). In their majority the courses are directed to people that will make use of radiations for first time, but refresher courses are also granted in the topic. The CSEN also carries out the Master degree programs highlighting the Second Professional Specialization in Radiological Protection carried out from the year 2004 with the support of the National University of Engineering. To the present has been carried out 2 programs and there is other being developed. In this work is shown the historical evolution of the radiological protection courses as well as the important thing that they are to work in a safe way in the country. (Author)

  9. Focal role of tolerability and reasonableness in the radiological protection system.

    Science.gov (United States)

    Schneider, T; Lochard, J; Vaillant, L

    2016-06-01

    The concepts of tolerability and reasonableness are at the core of the International Commission on Radiological Protection (ICRP) system of radiological protection. Tolerability allows the definition of boundaries for implementing ICRP principles, while reasonableness contributes to decisions regarding adequate levels of protection, taking into account the prevailing circumstances. In the 1970s and 1980s, attempts to find theoretical foundations in risk comparisons for tolerability and cost-benefit analysis for reasonableness failed. In practice, the search for a rational basis for these concepts will never end. Making a wise decision will always remain a matter of judgement and will depend on the circumstances as well as the current knowledge and past experience. This paper discusses the constituents of tolerability and reasonableness at the heart of the radiological protection system. It also emphasises the increasing role of stakeholder engagement in the quest for tolerability and reasonableness since Publication 103. © The International Society for Prosthetics and Orthotics.

  10. Science and Values in Radiological Protection - Helsinki, Finland, 15-17 January 2008. Workshop proceedings

    International Nuclear Information System (INIS)

    2008-01-01

    Key scientific challenges arising from ongoing radiobiological research have been identified recently. From this scientific base, the possible implications for radiological protection science are expected to be further elaborated. Through discussions among members of various NEA committees, it is clear that there is a need for radiological protection policy makers, regulators and practitioners to better understand possible developments coming from radiological protection science. At the same time, there is also a need for radiological protection scientists to better understand the broad processes of radiological protection decision making and to better interact with these processes in terms of furnishing input coming from their research. Participants in this workshop will attempt to identify elements of a framework that are better suited for the integration of new scientific and technological developments and socio-political considerations into radiological protection. This workshop initiated a process of reflection and dialogue among researchers, policy makers and other stakeholders that will, in the longer term: - improve understanding in both the research and policy communities of what is at stake in the system of radiological protection as scientific knowledge and social values evolve; - contribute to the development of a more shared view of emerging scientific and societal challenges to radiological protection, taking into account existing differences; - identify research that will better inform decision makers' judgments on emerging issues; - be the first step in the identification of elements of a framework that is better suited for the integration of new scientific and technological developments and socio-political considerations into radiological protection; and - identify the most appropriate next steps in this process. To achieve the above objectives, selected examples of emerging radiological protection issues were addressed during the workshop. The

  11. Radiological protection standards in the United Kingdom

    International Nuclear Information System (INIS)

    Pochin, E.; McLean, A.S.; Richings, L.D.G.

    1976-09-01

    In view of the interest now being expressed in the means by which radiological protection standards are derived and applied, this report briefly outlines the roles of the international organisations involved, summarises the UK arrangements, and indicates the principal sources of relevant biological information. (author)

  12. Comparison between radiological protection against ionizing radiation and non ionizing radiation

    International Nuclear Information System (INIS)

    Jammet, H.P.

    1992-01-01

    Protection against IR and NIR developed in completely different ways because of the very different evolution of the techniques they involve. While as soon as 1928, the International Society of Radiology created the International Commission of Radiological Protection, we had to wait until 1977 to see the creation of the International Committee for NIR (INIRC) by IRPA. To compare protection against Ionizing Radiations and Non Ionizing Radiations we will first carry out a general analysis of its components and then we will draw the general conclusions leading to a quite comparable evolution. (author)

  13. Radiological Protection Criteria for the Safety of LILW Repository in Croatia

    International Nuclear Information System (INIS)

    Levanat, I.; Lokner, V.; Subasic, D.

    2000-01-01

    Preparations for a LILW repository development in Croatia, conducted by APO Hazardous Waste Management Agency, have reached a point where the first safety assessment of the prospective facility is being attempted. For evaluation of the calculated radiological impact in the assessed option of repository development, a set of radiological protection criteria should be included in the definition of the assessment context. The Croatian regulations do not explicitly require that the repository development be supported by such safety assessment process, and do not provide a specific set of radiological criteria intended for the repository assessment which would be suitable for the constrained optimization of protection. For the initial safety assessment iterations of the prospective repository, which will address long term performance of the facility for various design and other safety options, we propose to use relatively simple radiological protection criteria, consisting only of individual dose and risk constraints for the general population. The numerical values for these constraints are established in accordance with the recognized international recommendations and in compliance with all possibly relevant Croatian safety requirements. (author)

  14. Radiation protection of workers in radiological emergency situation. Proceedings of the technical day

    International Nuclear Information System (INIS)

    Rannou, Alain; Gosset, Eric; Lahaye, Thierry; Foucher, Laurent; Couasnon, Olivier; Bouchery, Pascal; Gaillard-Lecanu, Emmanuelle; Pectorin, Xavier; Fusil, Laurence; Boudergui, Karim; Adhemar, Bruno; Devin, Patrick; Mace, Jean-Reynald; Chevallier, Michel; Leautaud, Jean-Marc; LANCE, Benoit

    2015-03-01

    Following the Fukushima-Daichi accident, several actions have been taken in France from the lessons learnt from the accident: the elaboration of a national plan for the management of a major nuclear or radiological accident, and the safety complementary evaluations to be carried out by nuclear operators. As a complement to the measures to be implemented for the protection of the overall population in emergency radiological situation, the protection of workers mobilized for the management of the crisis has also to be taken into account in the framework of these measures. The French Society of Radiation Protection (SFRP) has organized a technical day to take stock of this question. The program comprises 4 topical sessions dealing with: the main actions taken at the national scale after the Fukushima-Daichi accident, the strategies and intervention means of nuclear operators in case of radiological emergency, the radiation protection R and D for the protection of intervenors in case of radiological emergency, and the main actions implemented at the international scale and their perspectives. This document brings together the abstracts and the presentations (slides) of the different talks given at the meeting: 1 - Health status and lessons learnt from the Fukushima accident - workers (Alain RANNOU, IRSN); 2 - National response plan to a major nuclear or radiologic accident (Eric GOSSET, SGDSN); 3 - Legal framework applicable to intervenors (Thierry LAHAYE, DGT); 4 - Prescriptions linked with complementary safety and liability studies (Laurent FOUCHER, ASN); 5 - EDF: radiological risk management in emergency situation (Pascal BOUCHERY, EDF); 6 - CEA: intervention strategy, means and radiation protection (Xavier PECTORIN, Laurence FUSIL - CEA); 7 - AREVA: FINA's Intervention and workers' radiation protection (Bruno ADHEMAR, Patrick DEVIN - AREVA); 8 - Intervention in radiological emergency situation: the INTRA (Robots intervention on accidents) economic

  15. 1993 Radiation Protection Workshop: Proceedings

    Energy Technology Data Exchange (ETDEWEB)

    1993-12-31

    The 1993 DOE Radiation Protection Workshop was conducted from April 13 through 15, 1993 in Las Vegas, Nevada. Over 400 Department of Energy Headquarters and Field personnel and contractors from the DOE radiological protection community attended the Workshop. Forty-nine papers were presented in eleven separate sessions: Radiological Control Manual Implementation, New Approaches to Instrumentation and Calibration, Radiological Training Programs and Initiatives, External Dosimetry, Internal Dosimetry, Radiation Exposure Reporting and Recordkeeping, Air Sampling and Monitoring Issues, Decontamination and Decommissioning of Sites, Contamination Monitoring and Control, ALARA/Radiological Engineering, and Current and Future Health Physics Research. Individual papers are indexed separately on the database.

  16. 1993 Radiation Protection Workshop: Proceedings

    International Nuclear Information System (INIS)

    1993-01-01

    The 1993 DOE Radiation Protection Workshop was conducted from April 13 through 15, 1993 in Las Vegas, Nevada. Over 400 Department of Energy Headquarters and Field personnel and contractors from the DOE radiological protection community attended the Workshop. Forty-nine papers were presented in eleven separate sessions: Radiological Control Manual Implementation, New Approaches to Instrumentation and Calibration, Radiological Training Programs and Initiatives, External Dosimetry, Internal Dosimetry, Radiation Exposure Reporting and Recordkeeping, Air Sampling and Monitoring Issues, Decontamination and Decommissioning of Sites, Contamination Monitoring and Control, ALARA/Radiological Engineering, and Current and Future Health Physics Research. Individual papers are indexed separately on the database

  17. Recommended radiological controls for tritium operations

    International Nuclear Information System (INIS)

    Mansfield, G.

    1992-01-01

    This informal report presents recommendations for an adequate radiological protection program for tritium operations. Topics include hazards analysis, facility design, personnel protection equipment, training, operational procedures, radiation monitoring, to include surface and airborne tritium contamination, and program management

  18. The work of ICRP on the ethical foundations of the system of radiological protection

    International Nuclear Information System (INIS)

    Cho, Kun-Woo

    2017-01-01

    The International Commission on Radiological Protection (ICRP) has established Task Group 94 (TG 94) to develop a publication on the ethical foundations of the system of radiological protection aiming to consolidate the basis of ICRP's recommendations, to improve the understanding of the system and to provide a basis for communication on radiation risk and its perception. Through the review of the publications of the Commission and the conduct of a series of workshops, TG 94 has identified the key components of the ethical theories and principles relevant to the system of radiological protection. The purpose of eliciting the ethical values underpinning the system of radiological protection is not only to clarify the rationale of the recommendations made by the Commission, but also to assist in discussions related to its practical implementation. The report nearing completion by TG 94 will present the key steps concerning the scientific, ethical and practical evolutions of the system of radiological protection since the first ICRP publication in 1928, describe the core ethical values underpinning the present system and address the key procedural aspects for its implementation. (authors)

  19. New recommendations from the International Commission on Radiological Protection-a review

    International Nuclear Information System (INIS)

    Wrixon, A D

    2008-01-01

    For almost half a century, the International Commission on Radiological Protection (ICRP) has revised its recommendations on radiological protection with an average frequency of about 10 years, building on the experience gained in their implementation. This has ensured that the recommendations remain up to date and fit for purpose and it is this that has led in turn to their wide acceptance internationally. Indeed, the 1990 version of the recommendations forms the basis of the international radiological protection standards and the systems of control of exposure to ionizing radiation in many countries throughout the world. This version introduced new concepts and a more holistic approach to radiological protection but marrying the different exposure situations into one coherent framework has proved not to be straightforward and further reflection seemed necessary in order to satisfy both those who are responsible for the development of the control systems as well as a broader audience. Review of the 1990 recommendations started around 1998 and, since then, many ideas have been explored and avenues followed. Eventually, new recommendations were agreed by the Commission at its meeting in Essen in March 2007. This paper provides a review of these new recommendations and their possible implications. (topical review)

  20. Radiological protection aspects regarding to assistance of the cesium-137 radiation accident victims in Goiania; Aspectos de protecao radiologica no atendimento as vitimas do acidente radiologico com cesio-137 em Goiania

    Energy Technology Data Exchange (ETDEWEB)

    Hunt, John Graham; Oliveira Filho, Denizart Silveira de; Rabelo, Paulo Ney Pamplona [Instituto de Radioprotecao e Dosimetria (IRD), Rio de Janeiro, RJ (Brazil)

    1997-12-31

    The radiological protection measures taken in the general hospital of Goiania (HGG/INAMPS) and in the FEBEM institution, due to the accident involving Cesium-137 are described, as well as the work of the IRD personnel in the areas of: radiological protection of the medical and auxiliary staff, contamination control of the ward, radiological monitoring of the patients, waste management, personnel and area decontamination and patient transportation. (author) 4 refs., 11 figs.; e-mail: marcos at omega.lncc.br

  1. Radiological protection and the Fukushima Daiichi accident. Responses of the key international organisations

    Energy Technology Data Exchange (ETDEWEB)

    Clement, Christopher

    2017-10-01

    The Fukushima Daiichi nuclear power plant accident in March 2011 shook the radiological protection world. All major organisations in the radiological protection field turned their eyes to Japan. Their actions, driven by their mandates, are reflected in their respective landmark reports on the accident. Reports of the International Commission on Radiological Protection, World Health Organisation, United Nations Scientific Committee on the Effects of Atomic Radiation, and International Atomic Energy Agency are summarised. Collaboration between key international organisations is strong, based in part on informal interactions which need to be backed up with formal relations to ensure solid long-term collaboration.

  2. ICRP and radiological protection in medicine

    International Nuclear Information System (INIS)

    Cousins, Claire

    2017-01-01

    Standards in relation to radiological protection in medicine are well-documented, particularly with the recent update of the Basic Safety Standards. The principles of justification and optimisation remain key, as dose limitation is not applicable in medical practice. Appropriate justification relies on the knowledge, experience and discretion of the relevant medical practitioners and this may be overlooked in the race for diagnosis and treatment. One argument would be further regulation of medical exposures, although it is difficult to see how this could be imposed without denying patients essential investigations and treatments. Another contentious issue is individual patient dose management with the possible creation of a 'radiation passport'. Individual radiation susceptibility is a topic that has attracted much attention, but how to manage such persons, if identified, raises further questions. Communicating radiation risks and benefits to patients appropriately needs to be addressed, including who should be responsible for this, given accurate knowledge is a prerequisite. Ethics in radiological protection is also being widely discussed and this in relation to medical practice, which already involves numerous ethical issues, is likely to be open to debate in the near future. (authors)

  3. Issues around radiological protection of the environment and its integration with protection of humans: promoting debate on the way forward

    International Nuclear Information System (INIS)

    Brownless, G P

    2007-01-01

    This paper explores issues to consider around integrating direct, explicit protection of the environment into the current system of radiological protection, which is focused on the protection of humans. Many issues around environmental radiological protection have been discussed, and ready-to-use toolboxes have been constructed for assessing harm to non-human biota, but it is not clear how (or even if) these should be fitted into the current system of protection. Starting from the position that the current approach to protecting the environment (namely that it follows from adequately protecting humans) is generally effective, this paper considers how explicit radiological protection of the environment can be integrated with the current system, through developing a 'worked example' of how this could be done and highlighting issues peculiar to protection of the environment. The aim of the paper is to promote debate on this topic, with the ultimate aim of ensuring that any changes to the system are consensual and robust

  4. The regulation of the radiological protection in Mexico; La reglamentacion de la proteccion radiologica en Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Eibenschutz H, J. [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Jose Ma. Barragan No. 779, Col. Narvarte, 03020 Mexico D. F. (Mexico)

    2008-12-15

    The regulation antecedents in nuclear question in Mexico are placed in 1950, with the promulgation of {sup L}aw that declares national mining reserves the uranium deposits, thorium and the other substances of which obtains fissionable isotopes that can produce nuclear energy{sup ,} instrument that stipulated the control of uranium, thorium, as to its it indicated it name, and other fissionable substances, on the part of the state, although they were without a doubt the respective institutions, the National Commission of Nuclear Energy in 1955, and the one of the National Commission of Nuclear Safety and Safeguards (CNSNS) in 1979, those that allowed the development of a prescribed frame in the nuclear and radiological areas. One characteristic of the regulation in radiological protection is the variety in the authorities type that have incidence in the regulation, as a result of the different approaches with which it can be approached. For example, in Mexico normative instruments with content in radiological protection exist and are watched over the Health Secretary, who is oriented to the protection of the patient, their relatives and the medical body; Work and Social Welfare Secretary, with a labor approach; Communications and Transport Secretary, which regulates the transport of nuclear and radioactive materials; Finance and Public Credit Secretary, who regulates the import and export of radioactive materials; Environment and Natural Resources Secretary, which regulates the environment protection; Energy Secretary who has responsibilities inside of the {sup p}rescribed law of article 27 constitutional in nuclear matter{sup ;} and within the energy sector, the CNSNS that expedite and watch the fulfillment of normative in radiological protection and nuclear safety. In order to resist effects of on regulation; frequently inter institutional agreements are carried out in which the areas of monitoring are agreed by each authority. The regulation in radiological

  5. The current status of radiological protection infraestructures in Tanzania

    International Nuclear Information System (INIS)

    Ngalie, J.E.; Mompome, W.K.; Meza, L.H.

    2008-01-01

    Without adequate and sustainable radiation protection infrastructure, the benefits associated with safe use of nuclear technology and atomic energy might be jeopardized. In the United Republic of Tanzania, the Atomic Energy Act No. 7 of 2003 established the Tanzania Atomic Energy Commission as sole regulatory body responsible for regulating and controlling the safe and peaceful utilization of nuclear technology in the country. The Atomic Energy (Protection from ionizing radiation) Regulations, 2004 further specifies practices designed to ensure that unnecessary exposure of persons to ionizing radiation is avoided, that all exposures are kept as low as reasonably achievable and that all the dose limits specified in the radiation protection standards are not exceeded. This is achieved through the systems of notification, authorizations through registration and licensing, safety and security of radiation sources as well as regulatory inspections and enforcements. These activities are performed by the Commission with operational funds allocated by the Government of Tanzania. The Commission further provides other services namely individual monitoring; calibration services; education and training to radiation workers, public as well as law enforcers; and safe management of radioactive waste. Despite such achievement, still there are a lot to be done in order to strengthen the radiation protection infrastructure in Tanzania. These include issues such as gaps in our legislations, regulations and guidance, security of sources, enforcement of laws, etc. This paper describes and discusses the current status of the regulatory control activities and radiation protection services provided by the Commission and suggestions for further improvement of radiological protection infrastructure in Tanzania. (author)

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

    International Nuclear Information System (INIS)

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

    1996-01-01

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

  7. Principles of Radiation Protection Concepts

    International Nuclear Information System (INIS)

    Abd Aziz Mhd Ramli

    2004-01-01

    The contents of this chapter are follows - Radiation Protection Concepts: justification, dose limitation, optimisation, potential exposures, situation requiring intervention; Special Considerations. Protection from Radiation Hazards, Remove the Hazard, Prevent the Hazard, Guard the Worker, Implementation of Radiation Protection and Safety Measures, Distance, Shielding, Time, Monitoring Programme, Safety System. Radiation Protection in Radiological Service: Specific Requirement in Diagnostic Radiological Service

  8. Evaluation of the integrity of radiological protection clothing used in veterinary radiology

    Energy Technology Data Exchange (ETDEWEB)

    Rosa, Paola da Costa; Barros, Frieda Saicla; Costa, Douglas Siqueira da, E-mail: paah_dacosta@hotmail.com [Universidade Tecnologica Federal do Parana (UTFPR), Curitiba, PR (Brazil). Curso Superior de Tecnologia em Radiologia e Programa de Pos-Graduacao em Engenharia Biomedica

    2017-11-01

    This study aimed to evaluate the integrity of radiological protection clothing used by veterinarians in veterinary radiology facilities, and whether they are available in an adequate quantity for the team. Inspection was performed by palpation, followed by X-ray scanning in 189 clothing from 29 veterinary facilities. The results indicate that 5% of the clothes evaluated in this study were considered inadequate due to the failure of the integrity of the lead, being most lead aprons. All facilities have at least two lead aprons and one Thyroid protectors. 24% of the facilities have lead glasses, pointing to a risk to veterinarians by radiosensitivity of the eyes. Also, 24% of the facilities do not have lead gloves, which also presents a risk due to the hand's exposure to the primary beam. Most lead clothing has shield equivalence of 0.5mmPb. The method used in the study was effective in attesting the adequacy of lead clothing. It is recommended to periodically evaluate clothing to ensure that users are always protected. (author)

  9. Evaluation of the integrity of radiological protection clothing used in veterinary radiology

    International Nuclear Information System (INIS)

    Rosa, Paola da Costa; Barros, Frieda Saicla; Costa, Douglas Siqueira da

    2017-01-01

    This study aimed to evaluate the integrity of radiological protection clothing used by veterinarians in veterinary radiology facilities, and whether they are available in an adequate quantity for the team. Inspection was performed by palpation, followed by X-ray scanning in 189 clothing from 29 veterinary facilities. The results indicate that 5% of the clothes evaluated in this study were considered inadequate due to the failure of the integrity of the lead, being most lead aprons. All facilities have at least two lead aprons and one Thyroid protectors. 24% of the facilities have lead glasses, pointing to a risk to veterinarians by radiosensitivity of the eyes. Also, 24% of the facilities do not have lead gloves, which also presents a risk due to the hand's exposure to the primary beam. Most lead clothing has shield equivalence of 0.5mmPb. The method used in the study was effective in attesting the adequacy of lead clothing. It is recommended to periodically evaluate clothing to ensure that users are always protected. (author)

  10. Radiological safety system based on real-time tritium-in-air monitoring in room and effluents

    Energy Technology Data Exchange (ETDEWEB)

    Bidica, N.; Sofalca, N.; Balteanu, O.; Stefan, I. [National Institute of Cryogenics and Isotopes Technologies, Ramnicu Valcea (Romania)

    2006-07-01

    The conceptual design of the radiological safety system based on real time-in-air monitoring in room and effluents is intended to provide the maximum achievable safety level, basing no the ALARA concept. the capabilities of this system are not only to inform any time personnel about tritium in air concentration level, but it will be able to: initiate the shut down procedure and drain off the plant, as well to start the Air cleaning System when the tritium-in-air concentration exceed pre-established threshold; estimate tritium effective dose rate before starting an activity into the monitored area, or during this activity, or soon as the activity was finished; estimate tritium effective dose and instantly record and update individual effective doses, using a special computer application called 'dose record'; lock access into the radiological area for individuals when tritium dose rate in the monitoring area will exceed the pre-established thresholds, or when any individual dose data provided by 'dose records' application ask for, or for other protection consideration; calculate the total tritium activity released to the environment (per day, week, or month). (N.C.)

  11. Radiological safety system based on real-time tritium-in-air monitoring in room and effluents

    International Nuclear Information System (INIS)

    Bidica, N.; Sofalca, N.; Balteanu, O.; Stefan, I.

    2006-01-01

    The conceptual design of the radiological safety system based on real time-in-air monitoring in room and effluents is intended to provide the maximum achievable safety level, basing no the ALARA concept. the capabilities of this system are not only to inform any time personnel about tritium in air concentration level, but it will be able to: initiate the shut down procedure and drain off the plant, as well to start the Air cleaning System when the tritium-in-air concentration exceed pre-established threshold; estimate tritium effective dose rate before starting an activity into the monitored area, or during this activity, or soon as the activity was finished; estimate tritium effective dose and instantly record and update individual effective doses, using a special computer application called 'dose record'; lock access into the radiological area for individuals when tritium dose rate in the monitoring area will exceed the pre-established thresholds, or when any individual dose data provided by 'dose records' application ask for, or for other protection consideration; calculate the total tritium activity released to the environment (per day, week, or month). (N.C.)

  12. Airborne systems for emergency radiological monitoring

    International Nuclear Information System (INIS)

    Jupiter, C.; Boyns, P.

    1976-01-01

    A variety of aerial radiological monitoring systems are available to respond to a radiological accident or incident affecting large areas. These are operated by EG and G, Inc. for ERDA's Division of Operational Safety. A survey system can be airborne within approximately two hours after notification. Both airborne and terrestrial radioactivity can be measured and mapped. Special analysis procedures allow discrimination between radioactivity from most man-made radioelements and naturally occurring radioelements. A position accuracy of +-54 feet can be maintained over a large area survey. Detection sensitivity for gamma sources employing NaI detector arrays on board an airplane flying at 500 feet altitude is better than 2 μR/hr for surface planar contaminants and approximately 10 mCi for a point gamma source

  13. Studies on optimization of radiation protection for patients in diagnostic radiology

    International Nuclear Information System (INIS)

    Wei, Z.; Zhang, Q.; Li, W.; Li, K.; Wei, L.; Zong, X.; Qiang, Z.; Wu, Y.

    1994-01-01

    For the exposure of patients in diagnostic radiology, individual dose limit does not apply, but optimization of radiological protection may play a major role. This project has been carried out with the purpose of improving the protection of patients in medical diagnostic radiology in China utilizing the principles of optimization. Taking Sichuan, Shandong and Beijing as surveyed areas, we investigated the present situation of the protection of patients. In the survey, the patient doses were classified into practical dose, justified dose and optimized dose to evaluate the influences of managerial and equipment factors separately. The results show that there are some urgent protection problems in X-ray protection to be solved in the surveyed regions. This paper, however, points out that the prospects of reducing patient doses are encouraging provided that appropriate measures are adopted. For instance, taking proper managerial measures without radical change of existing equipments may reduce patient doses in chest fluoroscopy and radiography by 40% and 18% respectively; refitting some equipment may reduce the doses by 82.4% in chest fluoroscopy, 66% in chest radiography, and 80% in barium meal examination of the gastrointestinal (GI) tract. Using chest radiography instead of fluoroscopy supplemented by other protection measures may reduce the doses by 91.7%. Optimization analysis shows that adoption of the above measures conforms to the principle of optimization of radiation protection. (authors). 5 refs., 7 tabs

  14. Statutory Instrument No 48 of 1992. Radiological Protection Act, 1991 (Establishment day) Order, 1992

    International Nuclear Information System (INIS)

    1992-03-01

    This order appoints 1st April 1992 as the day on which the Radiological Protection Institute of Ireland is established. From that day the Radiological Protection Institute of Ireland will take over the functions of An Bord Fuinnimh Nuicleigh

  15. Radiological Protection Plan an ethic responsibility; Plano de protecao radiologica e responsabilidade etica

    Energy Technology Data Exchange (ETDEWEB)

    Huhn, Andrea, E-mail: andrea.huhn@ifsc.edu.br [Instituto Federal de Santa Catarina (IFSC), Florianopolis, SC (Brazil); Vargas, Mara Ambrosina de Oliveira, E-mail: mara@ccs.ufs.br [Universidade Federal de Santa Catarina (UFSC), Florianopolis, SC (Brazil)

    2014-07-01

    The Radiological Protection Plan - PPR, quoted by the Regulatory Standard 32, requires to be maintained at the workplace and at the disposal of the worker's inspection the PPR, for it to be aware of their work environment and the damage that can be caused by misuse of ionizing radiation. Objective: to discuss the interface between PPR and ethical reflection. Method: this is a reflective study. Discussion and results: regulatory norm 32 points out that the worker who conducts activities in areas where there are sources of ionizing radiation should know the risks associated with their work. However, it is considered that the sectors of hospital radiology the multidisciplinary health team is exposed to ionizing radiation and has not always aware of the harm caused by it, so end up unprotected conduct their activities. Concomitantly, recent studies emphasize the radiological protection and concern for the dangers of radiation on humans, but rather refer to the legislation about the radiological protection. In this context an ethical reflection is necessary, seeking to combine work ethics liability to care in protecting themselves and the other with the institutional conditions for this protection becomes effective.

  16. Objectives of radiological environment protection in nuclear facilities

    International Nuclear Information System (INIS)

    Oberhausen, E.

    1976-01-01

    The aim of the radiological environment protection is to avoid risks to the health of the population. But the risks from radiation can only be considered in connection with spontaneously occuring malignancies. The comparison shows that according to the maximum permissible doses in the German Ordinance of Radiation Protection the risks of radiation injury are so low that they cannot be detected relative to the spontaneous malignancies. (orig.) [de

  17. Evolution of the radiological protection policy. Applications in developing countries. IPEN a case of study

    International Nuclear Information System (INIS)

    Gordon, A.M.P.L.; Sordi, G.M.A. A.

    2006-01-01

    This paper aims to show the radiological protection development in Brazil from the beginning, when President Joao Cafe Filho signed an agreement with the U.S.A. In this agreement, Brazil joined the 'Atoms for Peace' program established on August 3., 1955. Yet in 1955, Brazil participated as a foundation member in the International Atomic Energy Agency (IAEA). As a result, the Iea - 'Instituto de Energia Atomica'- was created on August 31., 1956 and a research reactor type swimming pool was installed to produce radioisotopes and prepare experts in the field of nuclear activities. This reactor is maintained in operation at the Instituto de Pesquisas Energeticas e Nucleares (IPEN), former Iea. Having the Iea as a case of study, we analyze the radiological protection evolution during the fifty years of its life. We correlate this development with the Brazilian National Nuclear Energy Commission (CNEN) Regulations. CNEN was also created in 1956. The first safety standard in Brazil was delivered in 1973. Therefore, this paper will focus the radiological protection development at national level. Both institutions followed the international radiological protection recommendations, under the difficulties imposed by the historical conditions of a developing country. In order to have an outline of the radiological protection development, we inform that it was started as a section of the Radiological Division at the Iea. At that time, the Iea had four divisions. The radiological protection was performed by four people, being two physicists and two technicians that accomplished all the duties. On that occasion, approximately 30 people operated the Iea. The work staff at IPEN increased, arriving to 1600 people in 1998, including 150 persons in the radiological protection activities. Nowadays, 1200 people, including 100 persons in the health physics duties operate the IPEN. (authors)

  18. Evolution of the radiological protection policy. Applications in developing countries. IPEN a case of study

    Energy Technology Data Exchange (ETDEWEB)

    Gordon, A.M.P.L.; Sordi, G.M.A. A. [Instituto de Pesquisas Energeticas e Nucleares - IPEN, Sao Paulo (Brazil)

    2006-07-01

    This paper aims to show the radiological protection development in Brazil from the beginning, when President Joao Cafe Filho signed an agreement with the U.S.A. In this agreement, Brazil joined the 'Atoms for Peace' program established on August 3., 1955. Yet in 1955, Brazil participated as a foundation member in the International Atomic Energy Agency (IAEA). As a result, the Iea - 'Instituto de Energia Atomica'- was created on August 31., 1956 and a research reactor type swimming pool was installed to produce radioisotopes and prepare experts in the field of nuclear activities. This reactor is maintained in operation at the Instituto de Pesquisas Energeticas e Nucleares (IPEN), former Iea. Having the Iea as a case of study, we analyze the radiological protection evolution during the fifty years of its life. We correlate this development with the Brazilian National Nuclear Energy Commission (CNEN) Regulations. CNEN was also created in 1956. The first safety standard in Brazil was delivered in 1973. Therefore, this paper will focus the radiological protection development at national level. Both institutions followed the international radiological protection recommendations, under the difficulties imposed by the historical conditions of a developing country. In order to have an outline of the radiological protection development, we inform that it was started as a section of the Radiological Division at the Iea. At that time, the Iea had four divisions. The radiological protection was performed by four people, being two physicists and two technicians that accomplished all the duties. On that occasion, approximately 30 people operated the Iea. The work staff at IPEN increased, arriving to 1600 people in 1998, including 150 persons in the radiological protection activities. Nowadays, 1200 people, including 100 persons in the health physics duties operate the IPEN. (authors)

  19. Global view on the radiological protection of patients: PAHO position paper

    International Nuclear Information System (INIS)

    Borras, C.

    2001-01-01

    The Pan American Health Organization/World Health Organization (PAHO/WHO), founded in 1902, initiated a radiological health programme in the 1950s. Within this programme, there are currently three lines of work: (a) radiology services; (b) radiation safety; and (c) radiological emergencies. Radiology services deals with health services for diagnostic and interventional imaging, and for radiation therapy. Radiation safety studies the three types of exposures to both ionizing and non-ionizing radiation: occupational; medical; and public. Radiological emergencies involve radioactive waste management programmes and emergency plans. The radiological protection of patients is addressed in each of these areas: (a) when analysing the infrastructure of radiology services; and (b) when determining medical exposures; and (c) when investigating overexposures in interventional or therapeutic procedures or under-doses in radiation therapy. (author)

  20. Accreditation of professionals for radiological protection in medical and dental radiology at Minas Gerais, Brazil

    International Nuclear Information System (INIS)

    Silva, Teogenes A. da; Pereira, Elton G.; Alonso, Thessa C.; Guedes, Elton C.; Goncalves, Elaine C.; Nogueira, Maria Angela A.

    2000-01-01

    The role of the CDTN/CNEN as far as the radiological protection services in the medical and dental radiology has changed a lot due to the new Regulatory Directives. The CDTN/CNEN was recognized as the regional reference center for providing not only radiological survey services, but to coordinate an accreditation procedure for professional persons to be accepted by the State Regulatory Authorities to work at Minas Gerais. All the new activities were formalized in a Cooperation Agreement between the CDTN/CNEN and the Regulatory Authority. This paper describes the accreditation procedure for candidates, the adopted requirements, the intercomparison results among measuring instruments and the main achievements during the first year of the Agreement. (author)

  1. Evaluation of the radiological protection in several departments of nuclear medicine

    International Nuclear Information System (INIS)

    Lopez Bejerano, G.; Jova Sed, L.

    2001-01-01

    For the evaluation of radiation protection, in several departments of nuclear medicine a survey was elaborated and applied that includes mainly: aspects of the licence and compliance with the requirements settled down in this, the program of individual radiological surveillance and their evaluation, functions that it completes the service of radiation protection, training program and the personnel's training, equipment and means of radiation protection, radiological surveillance program of the work areas, characteristics of the installation, radioactive waste management, quality assurance program, relative aspects to radiation protection in the procedures of diagnoses, as well as to pregnant patients and those related with the investigation of accidental medical exposures. The work makes a systematization and discussion of the state of compliance of the radiation protection requirements reflected in the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources (BSS) and the main recommendations are exposed to achieve in these departments the optimization of the radiation protection. (author)

  2. Evolution of the system of radiological protection

    International Nuclear Information System (INIS)

    2007-01-01

    The OECD Nuclear Energy Agency (NEA) has actively participated in discussions with the International Commission on Radiological Protection (ICRP) regarding the development of new recommendations that will replace those in ICRP Publication 60, which has long served as the international standard in this field. Part of this development process has involved the organisation of seven international workshops, including the First and Second Asian Regional Conferences on the Evolution of the System of Radiological Protection which took place in Tokyo, Japan in October 2002 and July 2004. The Third Asian Regional Conference was held on 5-6 July 2006, also in Tokyo. The main objective of these conferences was to ensure that the views and concerns of relevant Asian stakeholders, such as regulatory authorities, industry, professional societies and NGO, could be expressed and discussed with the ICRP. The three conferences provided the ICRP with specific views on how new recommendations could best be developed to address regulatory and implementation needs in the Asian context. These proceedings summarize the results and key discussions of the Third Asian Regional Conference. (author)

  3. Radiological protection of paediatric patients: An overview

    International Nuclear Information System (INIS)

    Ringertz, H.G.; Bremmer, S.

    2001-01-01

    Paediatric patients require special attention with respect to radiation protection, for various reasons. The difference between a 1 kg premature baby and a 100 kg teenager puts special demands on the radiographic techniques used, and the increased radiosensitivity of growing tissue and the patients' longer life expectancy put greater demands on the justification of the procedures to be carried out. The optimization procedure involves practical aspects such as immobilization, body build specific exposure parameters and body build specific anatomical knowledge. These and other aspects of paediatric radiological protection are discussed in this overview. (author)

  4. Dose monitoring in radiology departments. Status quo and future perspectives

    International Nuclear Information System (INIS)

    Boos, J.; Bethge, O.T.; Antoch, G.; Kroepil, P.

    2016-01-01

    The number of computed tomography examinations has continuously increased over the last decades and accounts for a major part of the collective radiation dose from medical investigations. For purposes of quality assurance in modern radiology a systematic monitoring and analysis of dose related data from radiological examinations is mandatory. Various ways of collecting dose data are available today, for example the Digital Imaging and Communication in Medicine - Structured Report (DICOM-SR), optical character recognition and DICOM-modality performed procedure steps (MPPS). The DICOM-SR is part of the DICOM-standard and provides the DICOM-Radiation Dose Structured Report, which is an easily applicable and comprehensive solution to collect radiation dose parameters. This standard simplifies the process of data collection and enables comprehensive dose monitoring. Various commercial dose monitoring software devices with varying characteristics are available today. In this article, we discuss legal obligations, various ways to monitor dose data, current dose monitoring software solutions and future perspectives in regard to the EU Council Directive 2013/59/EURATOM.

  5. Environmental protection: Researches in National Inst. of Radiological Sciences

    International Nuclear Information System (INIS)

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

    2011-01-01

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

  6. How can interventions for inhabitants be justified after a nuclear accident? An approach based on the radiological protection system of the international commission on radiological protection

    International Nuclear Information System (INIS)

    Takahara, Shogo; Homma, Toshimitsu; Yoneda, Minoru; Shimada, Yoko

    2016-01-01

    Management of radiation-induced risks in areas contaminated by a nuclear accident is characterized by three ethical issues: (1) risk trade-off, (2) paternalistic intervention and (3) individualization of responsibilities. To deal with these issues and to clarify requirements of justification of interventions for the purpose of reduction in radiation-induced risks, we explored the ethical basis of the radiological protection system of the International Commission on Radiological Protection (ICRP). The ICRP's radiological protection system is established based on three normative ethics, i.e. utilitarianism, deontology and virtue ethics. The three ethical issues can be resolved based on the decision-making framework which is constructed in combination with these ethical theories. In addition, the interventions for inhabitants have the possibility to be justified in accordance with two ways. Firstly, when the dangers are severe and far-reaching, interventions could be justified with a sufficient explanation about the nature of harmful effects (or beneficial consequences). Secondly, if autonomy of intervened-individuals can be promoted, those interventions could be justified. (author)

  7. Use of certification programs in the radiological protection of the patient

    International Nuclear Information System (INIS)

    Lucino, Sergio; Touzet, Rodolfo

    2008-01-01

    Full text: One of the main recommendations of the Congress of Malaga on Radiological Protection of the Patient is 'the qualification and training of the staff'. This goal cannot be reached in a country, in complete and systematic form, without the help of existing national programs who allow designing a program of continuous development of the professional capacities. This program must be able to adapt in permanent form to the needs of the Program of Radiological Protection of the Patient that change and evolve in constant form. In case of the Argentina it was adapted to these needs the 'National Program of Certification and Re-certification of medical professionals in Radiology and Radio-Diagnosis'. On the base of the existing program, general requirements were established for the radiological protection of the patient and in addition, special requirements for four specialties: a) General and pediatrics radiology; b) Computed tomography; c) Interventional radiology; d) Radiotherapy. The National Program of Certification was established in 1997 with a 'Top Permanent Council' formed by the National Minister of Health advised by a scientific council. It was also creates the 'National Council of Certification and professional Re-certification' integrated by the Minister of Education, the National Academy of Medicine, the Faculties of Medicine of the whole country, the medical Federations, the trade-union Associations and the Argentine Medical Association. The process of certification can be delegated to academic or university entities, medical colleges and medical chambers that have been recognized path and ethical conduct. The certification is voluntary but it becomes obligatory to be recognized as a specialist. The certification has duration of 5 years and is renewable on the basis of a system of credits that considers different elements of the developed activities and the written theoretical and practical evaluations. It is a transparent process where the ethical

  8. Importance of establishing radiation protection culture in Radiology Department.

    Science.gov (United States)

    Ploussi, Agapi; Efstathopoulos, Efstathios P

    2016-02-28

    The increased use of ionization radiation for diagnostic and therapeutic purposes, the rapid advances in computed tomography as well as the high radiation doses delivered by interventional procedures have raised serious safety and health concerns for both patients and medical staff and have necessitated the establishment of a radiation protection culture (RPC) in every Radiology Department. RPC is a newly introduced concept. The term culture describes the combination of attitudes, beliefs, practices and rules among the professionals, staff and patients regarding to radiation protection. Most of the time, the challenge is to improve rather than to build a RPC. The establishment of a RPC requires continuing education of the staff and professional, effective communication among stakeholders of all levels and implementation of quality assurance programs. The RPC creation is being driven from the highest level. Leadership, professionals and associate societies are recognized to play a vital role in the embedding and promotion of RPC in a Medical Unit. The establishment of a RPC enables the reduction of the radiation dose, enhances radiation risk awareness, minimizes unsafe practices, and improves the quality of a radiation protection program. The purpose of this review paper is to describe the role and highlight the importance of establishing a strong RPC in Radiology Departments with an emphasis on promoting RPC in the Interventional Radiology environment.

  9. Legal provisions governing gaseous effluents radiological monitoring

    International Nuclear Information System (INIS)

    Winkelmann, I.

    1985-01-01

    This contribution explains the main provisions governing radiological monitoring of gaseous effluents from LWR type nuclear power plants. KTA rule 1503.1 defines the measuring methods and tasks to be fulfilled by reactor operators in order to safeguard due monitoring and accounting of radioactive substances in the plants' gaseous effluents. The routine measurements are checked by a supervisory programme by an independent expert. The routine controls include analysis of filter samples, comparative measurement of radioactive noble gases, interlaboratory comparisons, and comparative evaluation of measured values. (DG) [de

  10. Eye lens monitoring for interventional radiology personnel: dosemeters, calibration and practical aspects of Hp(3) monitoring. A 2015 review

    International Nuclear Information System (INIS)

    Carinou, Eleftheria; Ferrari, Paolo; Bjelac, Olivera Ciraj; Gingaume, Merce; Merce, Marta Sans; O’Connor, Una

    2015-01-01

    A thorough literature review about the current situation on the implementation of eye lens monitoring has been performed in order to provide recommendations regarding dosemeter types, calibration procedures and practical aspects of eye lens monitoring for interventional radiology personnel. Most relevant data and recommendations from about 100 papers have been analysed and classified in the following topics: challenges of today in eye lens monitoring; conversion coefficients, phantoms and calibration procedures for eye lens dose evaluation; correction factors and dosemeters for eye lens dose measurements; dosemeter position and influence of protective devices. The major findings of the review can be summarised as follows: the recommended operational quantity for the eye lens monitoring is H p (3). At present, several dosemeters are available for eye lens monitoring and calibration procedures are being developed. However, in practice, very often, alternative methods are used to assess the dose to the eye lens. A summary of correction factors found in the literature for the assessment of the eye lens dose is provided. These factors can give an estimation of the eye lens dose when alternative methods, such as the use of a whole body dosemeter, are used. A wide range of values is found, thus indicating the large uncertainty associated with these simplified methods. Reduction factors from most common protective devices obtained experimentally and using Monte Carlo calculations are presented. The paper concludes that the use of a dosemeter placed at collar level outside the lead apron can provide a useful first estimate of the eye lens exposure. However, for workplaces with estimated annual equivalent dose to the eye lens close to the dose limit, specific eye lens monitoring should be performed. Finally, training of the involved medical staff on the risks of ionising radiation for the eye lens and on the correct use of protective systems is strongly recommended. (review)

  11. From a regulatory to a cultural approach in the field of radiological protection

    International Nuclear Information System (INIS)

    Boehler, M.-C.

    1995-01-01

    A radiological protection culture, which is seen to be a 'management' approach to individual and collective doses, based on the principle of optimisation is described with particular reference to the nuclear industry. The article discusses the fundamental role of the principle of optimisation, the legal nature of the principle of optimisation and the implementation of a radiological protection culture. (UK)

  12. Radiation monitoring systems and methodologies for radiological impact assessment

    International Nuclear Information System (INIS)

    Chaudhury, Probal

    2016-01-01

    Radioactive sources of various strengths are used in large number of applications in industry, healthcare, agriculture and research. Though all the sources are transported and used under regulatory control, there is always a possibility of some of the sources getting into the hands of committed antisocial non state actors. In addition to this, there is a possible threat of radioactive material being illegally brought into a country. These gives rise to an increase in the global radiological threat and security experts world over are concerned about the possibility of malicious use of radiation in the public domain. Radiation detection systems are installed at various entry and exit ports of some of the countries to detect illicit trafficking of radioactive materials. IAEA has recommended that all States should have a national response plan for nuclear security events to provide for an appropriate and coordinated response. Considering the requirement of radiological emergency preparedness, various radiation monitoring systems and methodologies have been developed. A few aerial radiation monitoring systems developed at Bhabha Atomic Research Centre (BARC) for radiological impact assessment are described here

  13. Practical aspects of radiation protection in interventional radiology

    International Nuclear Information System (INIS)

    Faulkner, K.; Vano, E.; Ortiz, P.; Ruiz, R.

    2000-01-01

    to the patient, c) making selective use of high dose rate mode, by prior identification situations in which this use is really necessary, d) changing the projection possible, and d) performing simple constancy checks to detect malfunctions in the automatic control systems. In addition to these straightforward measures derived from the lessons learned, a more comprehensive approach should include review and optimization of technical factors used in protocols, such as the use of high-dose-rate modes, of magnification, of high image frequency, of extremely extended fluoroscopy time and exploratory research of the potential for dose reference levels as a tool for optimization. The IAEA, together with the European Commission, the World Health Organization and the Pan American Health Organization has prepared a report which provides practical measures of radiation protection in interventional radiology. This report reviews the use of interventional radiology, the observed deterministic effects, the methods for dose monitoring to patients and staff and the parameters influencing image quality and radiation dose. Finally, the document provides recommendations on syllabus for training programmes of the different professionals involved. (author)

  14. Individual monitoring of medical staff working in interventional radiology in Switzerland using double dosimetry

    International Nuclear Information System (INIS)

    Damet, J.; Bailat, C.; Bize, P.; Buchillier, Th.; Tosic, M.; Verdun, F.R.; Baechler, S.

    2011-01-01

    Physicians who frequently perform fluoroscopic examinations are exposed to high intensity radiation fields. The exposure monitoring is performed with a regular personal dosimeter under the apron in order to estimate the effective dose. However, large parts of the body are not protected by the apron (e.g. arms, head). Therefore, it is recommended to wear a supplemental dosimeter over the apron to obtain a better representative estimate of the effective dose. The over-apron dosimeter can also be used to estimate the eye lens dose. The goal of this study was to investigate the relevance of double dosimetry in interventional radiology. First the calibration procedure of the dosimeters placed over the apron was tested. Then, results of double dosimetry during the last five years were analyzed. We found that the personal dose equivalent measured over a lead apron was underestimated by ∼20% to ∼40% for X-ray beam qualities used in radiology. Measurements made over five-year period confirm that the use of a single under-apron dosimeter is inadequate for personnel monitoring. Relatively high skin dose (>10 mSv/month) would have remained undetected without a second dosimeter placed on the apron.

  15. International Commission on Radiological Protection. History, policies, procedures

    International Nuclear Information System (INIS)

    Lindell, Bo; Dunster, H.J.; Valentin, Jack; )

    2000-01-01

    This report briefly reviews the history, mode of operation, concepts, and current policies of the International Commission on Radiological Protection (ICRP). It touches upon the objectives of the Commission's recommendations, the quantities used, the biological basis of the Commission's policy, the quantitative basis for its risk estimates, the structure of the system of protection, some problems of interpretation and application in that system, and the need for stability, consistency, and clarity in the Commission's recommendations. (author)

  16. An Evolved System of Radiological Protection

    International Nuclear Information System (INIS)

    Kaneko, M.

    2004-01-01

    The current system of radiological protection based on the Linear No-Threshold (LNT) hypothesis has greatly contributed to the minimization of doses received by workers and members of the public. However, it has brought about r adiophobia a mong people and waste of resources due to over-regulation, because the LNT implies that radiation is harmful no matter how small the dose is. The author reviewed the results of research on health effects of radiation including major epidemiological studies on radiation workers and found no clear evidence of deleterious health effects from radiation exposures below the current maximum dose limits (50 mSv/y for workers and 5 mSv/y for members of the public), which have been adopted worldwide in the second half of the 20th century. Now that the existence of bio-defensive mechanisms such as DNA repair, apoptosis and adaptive response are well recognized, the linearity assumption cannot be said to be s cientific . Evidences increasingly imply that there are threshold effects in risk of radiation. A concept of practical thresholds or virtually safe doses will have to be introduced into the new system of radiological protection in order to resolve the low dose issues. Practical thresholds may be defined as dose levels below which induction of detectable radiogenic cancers or hereditary effects are not expected. If any workers and members of the public do not gain benefits from being exposed, excepting intentional irradiation for medical purposes, their radiation exposures should be kept below practical thresholds. On the assumption that the current dose limits are below practical thresholds and with no radiation detriments, there is no need of justification and optimization (ALARA) principles for occupational and public exposures. Then the ethical issue of justification to allow benefit to society to offset radiation detriments to individuals can be resolved. And also the ethical issue of optimization to exchange health or safety for

  17. Evaluation of radiation protection conditions in intraoral radiology

    Energy Technology Data Exchange (ETDEWEB)

    Miguel, Cristiano; Barros, Frieda Saicla; Rocha, Anna Silvia Penteado Setti da, E-mail: miguel_cristianoch@yahoo.com.br [Universidade Tecnologica Federal do Parana (PPGEB/UTFPR), Curitiba, PR (Brazil). Programa de Pos-graduacao em Engenharia Biomedica; Tilly Junior, Joao Gilberto [Universidade Federal do Parana (UNIR/UFPR), Curitiba, PR (Brazil). Hospital de Clinicas. Unidade de Imagem e Radioterapia; Almeida, Claudio Domingues de [Instituto de Radioprotecao e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil). Dept. de Fisica Medica

    2016-04-15

    Introduction: The dental radiology represents about 20% of human exposure to radiation in radio diagnostic. Although the doses practiced in intraoral dentistry are considered low, they should not be ignored due to the volume of the performed procedures. This study presents the radiation protection conditions for intraoral radiology in Curitiba - PR. Methods: Data was collected through a quantitative field research of a descriptive nature during the period between September of 2013 and December of 2014. The survey sample consisted of 97 dentists and 130 intraoral equipment. The data related to the equipment was collected using structured questions and quality control evaluations. The evaluations of the entrance skin dose, the size of the radiation field and the total filtration were performed with dosimetry kits provided and evaluated by IRD/CNEN. The exposure time and voltage were measured using noninvasive detectors. The occupational dose was verified by thermoluminescent dosimeters. The existence of personal protection equipment, the type of image processing and knowledge of dentists about radiation protection were verified through the application of a questionnaire. Results: Among the survey's results, it is important to emphasize that 90% of the evaluated equipment do not meet all the requirements of the Brazilian radiation protection standards. Conclusion: The lack of knowledge about radiation protection, the poor operating conditions of the equipment, and the image processing through visual method are mainly responsible for the unnecessary exposure of patients to ionizing radiation. (author)

  18. Radiation and man. From radiology to radiation protection

    International Nuclear Information System (INIS)

    2005-04-01

    Man first became aware of the invisible radiation surrounding him in 1895, when Wilhelm Roentgen showed that a photographic plate could be affected by an invisible radiation capable of passing through matter. He called this radiation 'X-rays' from X, the unknown. Doctors immediately saw the usefulness of this type of radiation and began to use it in medical research. This was the birth of radiology. 'Mankind has been exposed to radiation since his first appearance on Earth. We first became aware of this at the end of the 19. century'. However, it was not long before some of the doctors and radiologists treating their patients with X-rays began to fall ill. It began to be understood that exposure to high doses of radiation was dangerous and protective measures were necessary. From the 1920's onwards, international commissions were established to specify regulations for the use of radiation and for the radiological protection of personnel. (authors)

  19. Radiological protection in equine radiography and radiotherapy

    Energy Technology Data Exchange (ETDEWEB)

    Yoxall, A.T.

    1977-10-01

    The principles of radiological protection are summarised and consideration is then given to problems, which may confront the equine practitioner, in the fulfillment of these principles during diagnostic radiography of the limbs, head, and spine of the horse. The place of anaesthesia in such procedures is discussed and the special problems associated with therapeutic radiography of the horse are considered.

  20. General aspects of radiological protection to consider for the licensing a hospital cyclotron

    International Nuclear Information System (INIS)

    Andrada Contardi, F.A.; Fruttero, N.H.; Bozzo, R.H.; Moschella, E.G.

    2010-01-01

    The use of PET/PET-CT studies for a variety of diagnoses has increased significantly on a global scale. Modern medical cyclotrons must be placed in or near hospitals on account of the short radioactive half-life of the pharmaceuticals used in such studies. Many countries in Latin America are now licensing cyclotrons and laboratories for the production of radio-pharmaceuticals for the first time, and most are expected to have installations within the near future. This report outlines the general aspects of radiological protection important to consideration during the licensing of these facilities, and includes the following: general operation of the cyclotron and laboratory for the production of radiopharmaceuticals, safety systems (shielding, interlocks, ventilation, manual safety systems, alarms and monitors), and general aspects for licensing an installation (monitoring, accidental and incidental events, activation of components, etc.) and personnel. (authors) [es

  1. Radiological protection criteria for waste management

    International Nuclear Information System (INIS)

    Hill, M.D.; Webb, G.A.M.

    1985-01-01

    In this paper the progress being made by international organisations towards the development of a consensus on the radiological protection criteria to be applied to waste management, and in particular waste disposal, is reviewed. Against this background, work on the development of criteria for use in the UK is described. It is concluded that an international consensus is emerging and that the criteria being recommended for use in the UK are consistent with current international views. (author)

  2. Radiological protection criteria for waste management

    International Nuclear Information System (INIS)

    Hill, M.D.; Webb, G.A.M.

    1985-01-01

    In this Paper the progress being made by international organizations towards the development of a consensus on the radiological protection criteria to be applied to waste management, and in particular waste disposal, is reviewed. Against this background, work on the development of criteria for use in the UK is described. It is concluded that an international consensus is emerging and that the criteria being recommended for use in the UK are consistent with current international views. (author)

  3. Networking as an efficient, modern way of favouring stakeholders' involvement in implementing good radiological protection

    International Nuclear Information System (INIS)

    Lefaure, Ch.; Janssens, A.; Mrabit, K.; Ahier, B.

    2006-01-01

    Since the publication of ICRP 22 and ICRP 26 in 1973 and 1977 respectively, the understanding and practical implementation of the concept of Optimisation of Radiation Protection known as ALARA ('as low as reasonably achievable') has developed considerably globally and particularly in Europe. In the 1990 ICRP 60 publication, ALARA was re-emphasised as the cornerstone of the radiological protection system. This is also an explicit requirement of the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources (International BSS) and EC Directive laying down the Basic Safety Standards for radiological protection (EURATOM Directive 96/29), as well as of most of the national regulations. Throughout the 1980's and early 1990's ALARA was integrated into many organisations' radiation protection programmes, particularly in the nuclear industry and mainly for managing occupational exposure. One of the main lessons identified from that period was that it was not possible to implement good radiological protection by relying only on technical rules and procedures summarised in the three words: 'Time-Distance-Shielding'. A fourth word, 'Commitment', was to be added as no radiological protection programme would be successful without the commitment of all concerned stakeholders: regulatory bodies, managers, workers, etc. The scope of this presentation is, through different international feedback experiences, to demonstrate how networking is an efficient, modern way of fostering stakeholders involvement in implementing good radiological protection. (authors)

  4. Training project on Radiological Protection in medicine. Use of new technologies

    International Nuclear Information System (INIS)

    Ruis-Cruces, R.; Perez-Martinez, M.; Pastor Vega, J. M.; Diez de los Rios Delgado, A.

    2003-01-01

    Radiological protection training addressed to physicians should start during the teaching graduate and postgraduate studies, and a third phase only for those physicians using X rays and radioactive sources in diagnosis and treatment of diseases. To show a training project addressed to the teaching graduate students based on the new technologies, such as web online and interactive CD-ROM. Development of a web-online including information in.pdf (adobe acrobat) format and additional tools (as data bases, videos, news and class meetings, FAQ, tutorials). Moreover, we propose to development an interactive CD-ROM which will be used as a practical tool to complete the obligatory subject on radiological protection in the University of Malaga (Spain). We show the preliminary phase of the project. The web-online is being developed with the Microsoft FrontPage software. The first version of the CR-ROM is being developed in html format. These tools based on new technologies will be a very important support for radiological protection training, which is recommended by International Organizations (EC Report R116 and IAE Action Plan 2002-2006). (Author) 4 refs

  5. Offsite emergency radiological monitoring system and technology

    International Nuclear Information System (INIS)

    Mao Yongze

    1994-01-01

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

  6. ICRP-26, the recommendations on radiological protection

    International Nuclear Information System (INIS)

    Jun, J.S.

    1983-01-01

    Since the last ICRP recommendations on radiological protection was pubished in 1966 as it's publication 9, the revised edition of the recommendations had first been published in 1977, accommodating up-to-date knowledge of radiobiology and operational experiences of radiation protection built up for over a decade. In this article, the new version of the recommendations is reviewed in comparison with those of the publication 9, while the corrections and modifications made afterward are introduced together with the recent trends and responses of the experts in various countries for the pracical adoption or legislation of the recommendations. (Author)

  7. 6. Regional Congress on Radiation Protection and Safety; 3. Iberian and Latin American Congress on Radiological Protection Societies; Regional IRPA Congress. Book of abstracts

    International Nuclear Information System (INIS)

    2003-11-01

    The 6th Regional Congress on Radiation Protection and Safety was organized by the Peruvian Radiation Protection Society and the Peruvian Institute of Nuclear Energy, held in Lima, Peru, between 9 and 13 of november of 2003. In this event, were presented 227 papers that were articulated in the following sessions: radiation natural exposure, biological effects of ionizing radiation, instruments and dosimetry, radiological emergency and accidents, occupational radiation protection, radiological protection in medical exposure, radiological environmental protection, legal aspects, standards and regulations, training, education and communication, radioactive waste management, radioactive material transport, nuclear safety and biological effects of non-ionizing radiation. (APC)

  8. Hanford Radiological Protection Support Services Annual Report for 1998

    Energy Technology Data Exchange (ETDEWEB)

    DE Bihl; JA MacLellan; ML Johnson; RK Piper; TP Lynch

    1999-05-14

    During calendar year (CY) 1998, the Pacific Northwest National Laboratory (PNNL) performed its customary radiological protection support services in support of the U.S. Department of Energy (DOE) Richland Operations OffIce (RL) and the Hanford contractors. These services included: 1) external dosimetry, 2) internal dosimetry, 3) in vivo measurements, 4) radiological records, 5) instrument calibra- tion and evaluation, and 6) calibration of radiation sources traceable to the National Institute of Standards and Technology (MST). The services were provided under a number of projects as summarized here.

  9. Sampling on radiological protection training in diagnostic radiology

    International Nuclear Information System (INIS)

    Gaona, E.

    2001-01-01

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

  10. L-035: EPR-First Responders: Basic Risk and Protection for First Responders to a Radiological Emergency

    International Nuclear Information System (INIS)

    2011-01-01

    There are some basic actions and self-protective actions to take in an radiological emergency. Radiation is detected with appropriate instrumentation and measuring the rate of exposure (Sv per hour) in contact with radioactive materials involved. Is important to note: Responsive to a radiological emergency, tool to identify radiological risks, radiation protection, radioactive symbol and instrumentation

  11. Enhancement of radiological protection through an internal quality assessment cycle

    International Nuclear Information System (INIS)

    Figueiredo, Filipe Morais de; Gama, Zenewton Andre da Silva

    2012-01-01

    Objective: To determine the level of quality in radiation protection of patients during radiological examination, evaluating the effectiveness of an intervention aimed at enhancing the quality of such a protection. Materials and Methods: A quality improvement cycle was implemented in a radiology service of the Regional Health Administration, in Algarve, Portugal. Based on six quality criteria, an initial evaluation was performed and followed by an intervention focused on the most problematic points (over an eight-month period) and a subsequent quality reassessment. A random sampling (n = 60) has allowed the authors to infer the point estimates and confidence intervals for each criterion, as well as calculating the statistical significance of the results by means of the Z-test. Results: Initially, deficiencies were observed in relation to all the quality criteria. After the intervention, a minimum relative improvement of 33% was observed in five of the six criteria, with statistical significance (p < 0.05) in two of them. The absolute frequency of noncompliance decreased from 38 (first evaluation) to 21 (second evaluation), corresponding to a 44.7% improvement. Conclusion: The first institutional evaluation cycle showed a seemingly incipient improvement margin. However, the implemented intervention was effective in stimulating good practices and improving the level of radiological protection of patients. (author)

  12. A multimedia - virtual reality based- tool for training in radiological protection

    International Nuclear Information System (INIS)

    Salve, R.; Castro, A.; Javier, Castelo; Francisco, Diaz; Francisco, Massana; Antonio, A. de; Herrero, P.

    2001-01-01

    This paper presents the work that has been carried out under the frame of the project PRVIR, promoted by DTN in co-operation with the UPM and Vandellos II NPP, as the pilot plant. The aim of the project is to make use of computer-based training in nuclear plants, taking advantage of multimedia resources and advanced computer graphics. The area that has been selected for this first training program is radiological protection fundamentals, and the end users of the program will be professionally exposed workers. The software can also be used for radiological protection concepts dissemination purposes. (author)

  13. A multimedia - virtual reality based- tool for training in radiological protection

    Energy Technology Data Exchange (ETDEWEB)

    Salve, R.; Castro, A. [DTN, Madrid (Spain); Antonio, A. de; Herrero, P. [UPM Facultad de Informatica, Madrid (Spain); Diaz, F.; Massana, F [Central Nuclear Vandellos 2, Tarragona (Spain)

    2001-07-01

    This paper presents the work that has been carried out under the frame of the project PRVIR, promoted by DTN in co-operation with the UPM and Vandellos II NPP, as the pilot plant. The aim of the project is to make use of computer-based training in nuclear plants, taking advantage of multimedia resources and advanced computer graphics. The area that has been selected for this first training program is radiological protection fundamentals, and the end users of the program will be professionally exposed workers. The software can also be used for radiological protection concepts dissemination purposes. (author)

  14. Statutory Instrument no. 1230, The National Radiological Protection Board (Extension of Functions) Order 1974

    International Nuclear Information System (INIS)

    1974-01-01

    This Order, which came into operation of 1st August 1974, extends the functions and powers of the National Radiological Protection Board, which was established by the Radiological Protection Act 1970 so as to cover research and the giving of advice on the dangers of radiation which is electromagnetic but not ionizing. (NEA) [fr

  15. Foundations in radiological protection and radiotherapy

    International Nuclear Information System (INIS)

    Morales M, F.

    2002-01-01

    The work is divided in three parts. The part 1 are a brief abstrac of some important concepts related with the cells. The part 2 speak in general of the biological effects of the ionizing radiations according to the recommendations of the international commission of radiological protection. The part 3 refer to radiobiological calculations applying the quadratic lineal pattern to the radiotherapy. These calculations are important in view of the fact that they are applied for the introduction of new outlines of treatments

  16. Manual for environmental radiological surveillance

    International Nuclear Information System (INIS)

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

    2010-03-01

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

  17. Radiological protection procedures for industrial applications of computed radiography

    International Nuclear Information System (INIS)

    Aquino, Josilto Oliveira de

    2009-03-01

    Due to its very particular characteristics, industrial radiography is responsible for roughly half of the relevant accidents in nuclear industry, in developed as well as in developing countries, according to the International Atomic Energy Agency (IAEA). Thus, safety and radiological protection in industrial gamma radiography have been receiving especial treatment by regulatory authorities of most Member States. The main objective of the present work was to evaluate, from the radioprotection point of view, the main advantages of computed radiography (CR) for filmless industrial radiography. In order to accomplish this, both techniques, i.e. conventional and filmless computed radiography were evaluated and compared through practical studies. After the studies performed at the present work it was concluded that computed radiography significantly reduces the inherent doses, reflecting in smaller restricted areas and costs, with consequent improvement in radiological protection and safety. (author)

  18. Contribution of the french society of radiological protection to the current reflections on the possible improvement of the radiological risk management system

    International Nuclear Information System (INIS)

    Lecomte, J.F.; Schieber, C.

    2000-01-01

    Following the invitation by IRPA to comment the article by Prof. R. Clarke entitled 'Control of Low Level Radiation Exposures: Time for a Change?', the Board of the French Radiological Protection Society (SFRP) has decided to set up a specific Working Group. This Group consists of some twenty members representing the stakeholders involved in radiological protection in France. Its goal is, starting from an analysis of R. Clarke's text, to formulate questions and proposals to assist ICRP in making its radiological protection system more understandable and more efficient. The aim of this review is not to restart from scratch but to consolidate and improve the existing system. The Working Group has therefore focused its thoughts on the following four points: 1. The basis of the radiological risk management system. In the absence of scientific certainty as to the effects of low doses of radiation, a prudent attitude has been adopted as to the manner of managing the radiological risk, based on the hypothesis that the dose-effect relationship is linear with no threshold. The Group discusses this basic assumption and its implications on the elaboration of the objectives of the radiological risk management system. 2. Exposure situations. Exposure situations are multifarious and the existing system divides them into categories for management purpose (e.g. practice/intervention; natural/artificial; medical/public/occupational; actual exposure/potential exposure; etc.). Some of these divisions are pertinent but some are less so and the Group examines if another way of conceptualising exposures situations could be more efficient. 3. Risk management indicators and tools. The radiological protection system provides the professionals with a series of indicators and tools, enabling them to manage exposure situations (dose, dose limit, dose constraint, individual dose, collective dose, investigation level, action level, interventional level, exemption level, clearance level

  19. Environmental and Source Monitoring for Purposes of Radiation Protection. Safety Guide (Spanish ed.)

    International Nuclear Information System (INIS)

    2010-01-01

    The purpose of this Safety Guide is to provide international guidance, coherent with contemporary radiation protection principles and IAEA safety requirements, on the strategy of monitoring in relation to: (a) control of radionuclide discharges under practice conditions, and (b) intervention, such as in cases of nuclear or radiological emergencies or past contamination of areas with long lived radionuclides. Three categories of monitoring are discussed: monitoring at the source of the discharge (source monitoring), monitoring in the environment (environmental monitoring) and monitoring of individual exposure in emergencies (individual monitoring). The Safety Guide also provides general guidance on assessment of the doses to critical groups of the population due to the presence of radioactive materials or radiation fields in the environment both from routine operation of nuclear and other related facilities (practice) and from nuclear or radiological emergencies and past contamination of areas with long lived radionuclides (intervention). The dose assessments are based on the results of source monitoring, environmental monitoring, individual monitoring or their combinations. This Safety Guide is primarily intended for use by national regulatory bodies and other agencies involved in national systems of radiation monitoring, as well as by operators of nuclear installations and other facilities where natural or human made radionuclides are treated and monitored. Contents: 1. Introduction; 2. Meeting regulatory requirements for monitoring in practices and interventions; 3. Responsibilities for monitoring; 4. Generic aspects of monitoring programmes; 5. Programmes for monitoring in practices and interventions; 6. Technical conditions for monitoring procedures; 7. Considerations in dose assessment; 8. Interpretation of monitoring results; 9. Quality assurance; 10. Recording of results; 11. Education and training; Glossary.

  20. Indicative to evaluate the efficiency of a program of radiological protection

    International Nuclear Information System (INIS)

    Lescano, R.; Caspani, C.

    1998-01-01

    The purpose of the present work is to find an indicator that permit to evaluate objectively, that is to say through a number, the efficient accomplishment of radiological protection actions that is reflected in an improvement of the safety conditions with which is developed labor. The employed method consists of average evaluation of the individual doses received by the workers pursuing their occupations, measure in a great population, contrasted with the average of environmental dose of located monitors always in the same place. It can be employed film dosimeters, TLD, direct-reading pocket dosimeters with exposure monitor or any combination between them, provided that in the course of the time are compared always the same. Applying this method between the year 1991 to 1997, in part of Santa Fe province (Argentine), is observed that the individual dose average of the workers varies randomly and also rises and decrease unco-ordinately the environmental dose, but relating booth is arrived to a numerical value that has a comparable behavior to the objectively observed. (author)

  1. Implementation of procedures of radiological protection in the section of Radiology of the emergency Hospital of Porto Alegre-Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Lorenzini, F.; Rizzati, M.R. [Emergency Hospital of Porto Alegre, HPS (Brazil)

    1998-12-31

    The Emergency Hospital of Porto Alegre (HPS) is one of the main reference centers for the population in the attendance of medical emergencies/urgencies. The Section of Radiology, which informs the patients clinical conditions based on radiological images, is the most demanded section of the hospital (81.43 % of the medical cases request radiological exams) in the aid of the diagnosis, in which excels for the search of the quality in the health branch. In this work are presented the procedures to have been implemented about radiological protection according to effective norm, methods, ways and conditions to satisfy the radiation workers and the internal and external patients. (Author)

  2. Implementation of procedures of radiological protection in the section of Radiology of the emergency Hospital of Porto Alegre-Brazil

    International Nuclear Information System (INIS)

    Lorenzini, F.; Rizzati, M.R.

    1998-01-01

    The Emergency Hospital of Porto Alegre (HPS) is one of the main reference centers for the population in the attendance of medical emergencies/urgencies. The Section of Radiology, which informs the patients clinical conditions based on radiological images, is the most demanded section of the hospital (81.43 % of the medical cases request radiological exams) in the aid of the diagnosis, in which excels for the search of the quality in the health branch. In this work are presented the procedures to have been implemented about radiological protection according to effective norm, methods, ways and conditions to satisfy the radiation workers and the internal and external patients. (Author)

  3. Quality assurance programs from laboratories offering radiological protection services

    International Nuclear Information System (INIS)

    Marrero Garcia, M.; Prendes Alonso, M.; Jova Sed, L.; Morales Monzon, J.A.

    1998-01-01

    The implementation of an adequate program for quality assurance in institutions servicing radiological protection programs will become an additional tool to achieve security targets included in that program. All scientific and technical services offered by CPHR employ quality assurance systems

  4. International conference to explore ways to improve radiological protection of patients

    International Nuclear Information System (INIS)

    2001-01-01

    The first international conference specifically focused on the radiological protection of patients will be held in Torremolinos (Malaga), Spain, next week, from 26 to 30 March 2001. The conference, formally titled, 'International Conference on the Radiological Protection of Patients in Diagnostic and Interventional Radiology, Nuclear Medicine and Radiotherapy', is being organized by the IAEA, hosted by the Government of Spain and co-sponsored by the European Commission, the Pan American Health Organization and the World Health Organization. Medical applications of ionizing radiation are accepted world-wide as essential tools for keeping or restoring human health. However, they also represent by far the largest man-made source of radiation exposure. The United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR) estimates that diagnostic medical applications of radiation account for about 95% of the exposure to radiation from man-made sources of radiation and about 12% of total exposure, which includes the exposures received from natural sources. More than 900 participants from 80 countries are expected to attend the conference. They cover a broad spectrum of expertise, including radiologists, nuclear medicine specialists, radiation oncologists, medical physicists, technologists/radiographers, radiological protection officers, equipment manufacturers, experts who develop standards for radiological equipment, hospital administrators and public health officials and representatives of professional societies. In addition, a number of patients who have undergone radiation treatment will represent patients' interests and a patient will chair one of the round table debates. The conclusions of the Conference will be incorporated into the IAEA's programme of work in the field of radiation safety and will be reported to the IAEA General Conference at its next meeting in September 2001

  5. The regulatory application of authorization in radiological protection

    International Nuclear Information System (INIS)

    Lazo, T.; Frullani, S.

    2004-01-01

    Authorization is the process used by governments and regulatory authorities to decide what regulatory controls or conditions, if any, should be applied to radioactive sources or radiation exposure situations in order to protect the public, workers and the environment appropriately. Over the years, governments and regulatory authorities have used various approaches to the authorization process under differing circumstances. Now, with the new draft recommendations from the International Commission on Radiological Protection (ICRP), there is the prospect of being able to use a single, simple and self-coherent approach for the process of regulatory authorization under all circumstances. Previously, the ICRP recommended the use of various approaches to manage radiological protection situations. For what were called practices, exposures were subject to limits, and optimisation was required below these limits. What were called interventions were subject to intervention levels, above which some action could be considered justified, and which should be optimised based on consideration of how much dose could be averted by the countermeasure considered. Radon in homes was subject to action levels, above which some sort of countermeasure could be recommended. These approaches are all philosophically distinct and logically constructed, but their differences, particularly in the types of numerical criteria used (limits, intervention levels, action levels, etc.) contributed to confusion and misunderstanding. (author)

  6. Radiological protection report 2008; Strahlenschutzbericht 2008

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2009-05-15

    This annual report issued by the Swiss Federal Nuclear Inspectorate (ENSI) reports on the work carried out by ENSI in 2008. It provides comprehensive data on radiation protection activities in Switzerland during the year 2008. The first section of the report provides comprehensive data on radiation protection and deals with exposure rates for personnel and individual jobs. The authors note that, in recent years, both collective doses and average individual doses have declined by a factor of two. Radiation doses are commented on as being significantly lower than the maximum annual limit for persons exposed to radiation in the course of their work. Radiation in the four Swiss nuclear power stations and in four further nuclear installations in various Swiss research facilities is commented on. The Swiss radiation measurement network is commented on and the results obtained are discussed. ENSI concludes that the new recommendations published by the International Commission on Radiological Protection (ICRP 103) did not necessitate any significant changes in its surveillance activities.

  7. ICRP PUBLICATION 122: radiological protection in geological disposal of long-lived solid radioactive waste.

    Science.gov (United States)

    Weiss, W; Larsson, C-M; McKenney, C; Minon, J-P; Mobbs, S; Schneider, T; Umeki, H; Hilden, W; Pescatore, C; Vesterlind, M

    2013-06-01

    This report updates and consolidates previous recommendations of the International Commission on Radiological Protection (ICRP) related to solid waste disposal (ICRP, 1985, 1997b, 1998). The recommendations given apply specifically to geological disposal of long-lived solid radioactive waste. The report explains how the ICRP system of radiological protection described in Publication 103 (ICRP, 2007) can be applied in the context of the geological disposal of long-lived solid radioactive waste. Although the report is written as a standalone document, previous ICRP recommendations not dealt with in depth in the report are still valid. The 2007 ICRP system of radiological protection evolves from the previous process-based protection approach relying on the distinction between practices and interventions by moving to an approach based on the distinction between three types of exposure situation: planned, emergency and existing. The Recommendations maintains the Commission's three fundamental principles of radiological protection namely: justification, optimisation of protection and the application of dose limits. They also maintain the current individual dose limits for effective dose and equivalent dose from all regulated sources in planned exposure situations. They re-enforce the principle of optimisation of radiological protection, which applies in a similar way to all exposure situations, subject to restrictions on individual doses: 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. This report describes the different stages in the life time of a geological disposal facility, and addresses the application of relevant radiological protection principles for each stage depending on the various exposure situations that can be encountered. In particular, the crucial factor that

  8. ICRP PUBLICATION 122: Radiological Protection in Geological Disposal of Long-lived Solid Radioactive Waste

    International Nuclear Information System (INIS)

    Weiss, W.; Larsson, C-M.; McKenney, C.; Minon, J-P.; Mobbs, S.; Schneider, T.; Umeki, H.; Hilden, W.; Pescatore, C.; Vesterlind, M.

    2013-01-01

    This report updates and consolidates previous recommendations of the International Commission on Radiological Protection (ICRP) related to solid waste disposal (ICRP, 1985, 1997b, 1998). The recommendations given apply specifically to geological disposal of long-lived solid radioactive waste. The report explains how the ICRP system of radiological protection described in Publication 103 (ICRP, 2007) can be applied in the context of the geological disposal of long-lived solid radioactive waste. Although the report is written as a standalone document, previous ICRP recommendations not dealt with in depth in the report are still valid. The 2007 ICRP system of radiological protection evolves from the previous process-based protection approach relying on the distinction between practices and interventions by moving to an approach based on the distinction between three types of exposure situation: planned, emergency and existing. The Recommendations maintains the Commission’s three fundamental principles of radiological protection namely: justification, optimisation of protection and the application of dose limits. They also maintain the current individual dose limits for effective dose and equivalent dose from all regulated sources in planned exposure situations. They re-enforce the principle of optimisation of radiological protection, which applies in a similar way to all exposure situations, subject to restrictions on individual doses: 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. This report describes the different stages in the life time of a geological disposal facility, and addresses the application of relevant radiological protection principles for each stage depending on the various exposure situations that can be encountered. In particular, the crucial factor that

  9. 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)

  10. The applies specific technical requirements to the services of radiological protection according to the 17025

    Energy Technology Data Exchange (ETDEWEB)

    Marrero Garcia, M.; Fernandez Gomez, I. M.; Prendes Alonso, M.; Molina Perez, D.

    2004-07-01

    The employment in the Center of Radiation Protection and Hygiene (CRPH) of Cuba, of the standard 17025 for the administration of the quality of the calibration laboratories and test that offer services of radiological protection requires of a technical complement to really determine the technical competence. In the standard 17025, the specific requirements, are mentioned in the annex B (with informative character), where it points out that: {sup T}he requirements specified in the standard 17025 are established in general terms and, although they can be applied to all the test laboratories and applications, they could be necessary applications{sup .} In the CRPH these applications are translated in indispensable technical requirements to evaluate the performance of the services of radiological protection that offers, specifically those of personal monitoring, the calibration of instruments and the metrology of radionuclides. Although the standard 17025 is quite rigorous in the evaluation of technical requirements, to have specific materials not serves alone of tool to the laboratories, but also for the body of accreditation . In the CRPH the permanent employment of this tool has not constituted a practice, but had been good before our clients certain nonconformities to evaluate the performance of the laboratory and to achieve the recovery of the trust in its results. With this work we seek to expose some of these experiences. The experiences of the application of some of the technical requirements, in our case, they have been applied to the service of personal monitoring that offers the Laboratory of Personal Dosimetry. This laboratory is accredited by the National Accreditation Board of the Republic of Cuba (NABC) and besides fulfilling that settled down in 17025, the Approaches of Accreditation for test laboratories and calibration and it should also implant that settled down as specific technical requirements for the recognition of technical competence. (Author

  11. Radiological protection in industrial gamma scintigraphy facilities

    International Nuclear Information System (INIS)

    Rodriguez, M.; Suarez, S.

    2002-01-01

    Operational experience has shown that the mobile scintigraphy sector is not only that where individual doses are highest but also where there are the greatest number of high doses, overdoses and incidents. This fact highlights the need for improvement in the optimisation of radiological protection in the sector. In this context the CSN has adopted and implemented an action plan aimed at reducing doses to operation staff. (Author)

  12. Radiological protection in the use of radiotracers in industrial process

    International Nuclear Information System (INIS)

    Costa, M.L L.; Gomes, R.S.; Gomes, J.D.R.L.; Costa, E.L.C.; Thomé, Z.D.

    2017-01-01

    The use of radiotracers plays an important role to provide methods to optimize industrial process and improve product quality. An increase in the use of radiotracers investigations has been observed in Brazil, however, as there is no specific standard for the licensing of these facilities, generic radiation protection regulations have been used, but these are not comprehensive or technically suitable for this purpose. Regulatory inspections in radiotracer facilities have reported failures in disagreement with best practices for radiological safety, mainly in radioactive waste management and in the control of workplaces during radiotracer injections. In this work, an assessment of radiological protection aspects of radioactive tracers is performed, based on the licensing process of radiotracers facilities, as well as the experience of regulatory inspections and a review of international standards, pointing out relevant radiation safety aspects for working practices, procedures and protective measures before, during and after injections of radioactive tracers, in order to contribute to the future development of specific safety regulations on radiotracers in Brazil. (author)

  13. Radiological protection in the use of radiotracers in industrial process

    Energy Technology Data Exchange (ETDEWEB)

    Costa, M.L L.; Gomes, R.S.; Gomes, J.D.R.L.; Costa, E.L.C., E-mail: mara@cnen.gov.br, E-mail: rogeriog@cnen.gov.br, E-mail: jlopes@cnen.gov.br, E-mail: evaldo@cnen.gov.br [Comissão Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil). Diretoria de Radioproteção e Segurança Nuclear; Thomé, Z.D., E-mail: zielithome@gmail.com [Instituto Militar de Engenharia (IME), Rio de Janeiro, RJ (Brazil). Seção de Engenharia Nuclear

    2017-07-01

    The use of radiotracers plays an important role to provide methods to optimize industrial process and improve product quality. An increase in the use of radiotracers investigations has been observed in Brazil, however, as there is no specific standard for the licensing of these facilities, generic radiation protection regulations have been used, but these are not comprehensive or technically suitable for this purpose. Regulatory inspections in radiotracer facilities have reported failures in disagreement with best practices for radiological safety, mainly in radioactive waste management and in the control of workplaces during radiotracer injections. In this work, an assessment of radiological protection aspects of radioactive tracers is performed, based on the licensing process of radiotracers facilities, as well as the experience of regulatory inspections and a review of international standards, pointing out relevant radiation safety aspects for working practices, procedures and protective measures before, during and after injections of radioactive tracers, in order to contribute to the future development of specific safety regulations on radiotracers in Brazil. (author)

  14. Development of infrared communication in radiation protection and monitoring

    International Nuclear Information System (INIS)

    Thakur, Vaishali M.; Choithramani, S.J.; Sharma, D.N.; Abani, M.C.

    2003-01-01

    Infra-red communication has many important applications in instrumentation and control. Different types of nuclear instruments are used for radiation protection and surveillance program. The application of this mode of communication in these instruments helps in monitoring of inaccessible or high radiation field areas by avoiding undue exposure to the occupational worker. The demand for remotely controlled monitoring instruments and wireless data communication in the mobile computing environment has rapidly increased. This is due to the increasing need for on-line radiological data analysis with minimum human interventions, especially so if the monitoring is in hazardous environment. The wireless communication can be achieved using different communication methodology for short and long range communication. The infrared based communication is used for different applications for short range up to 9-10 meters. The use of this mode of communication has been implemented in some of the radiation monitoring instruments developed in house. The evaluation of data communication using this mode was conducted for the systems like Environmental Radiation Monitor (ERM) and results showed that data communication error is less than 0.1% up to 10 meter distance. (author)

  15. Education and training in radiological protection for diagnostic and interventional procedures ICRP 113 in brief

    International Nuclear Information System (INIS)

    Salama, S.; Gomaa, M. A.; Alshoufi, J.H.

    2013-01-01

    The international commission on radiological protection (ICRP) is the primary body in protection against ionizing radiation. Among its latest publication is ICRP publication 113 e ducation and training in radiological protection for diagnostic and interventional procedures . This document introduces diagnostic and interventional medical procedures using ionizing radiations in deep details. The document is approved by the commission in October 2010 and translated into Arabic at December 2011. This work is a continuation of the efforts series to translate some of the most important of the radiological protection references into the Arabic; aiming to maximize the benefit. The previous translation include WHO handbook on indoor radon: a public health perspective, issued by world health organization 2009 and Radiation Protection in Medicine, ICRP Publication 105 2007 that translated into Arabic with support of Arab atomic energy authority at 2011.

  16. Radiological protection in two types of human activities and from potential exposure

    International Nuclear Information System (INIS)

    Li Deping

    1991-01-01

    The new ICPR recommendations emphasize the distinction in radiological protection in two different types of human activities, practice and intervention. The purpose of emphases and measures for controlling or reduction of exposure for each type of activity are discussed. Potential exposure is regarded as an part of radiological protection system in this new recommendations, in a practice, it can be significantly reduced by proper prevention and mitigation measures in design and management. It is pointed out that with modern safety technology, the probability of potential exposure situations can be lowered to many orders of magnitude, even though the estimated value of probability is not accurate. Situations requiring intervention and the principles in protection are also discussed

  17. Surveillance and radiological protection in the Hot Cell laboratory

    International Nuclear Information System (INIS)

    Ramirez, J.M.; Torre, J. De la; Garcia C, M.A.

    2004-01-01

    The Hot Cells Laboratory (LCC) located in the National Institute of Nuclear Research are an installation that was designed for the management at distance of 10,000 Curies of Co-60 or other radioactive materials with different values in activity. The management of such materials in the installation, implies to analyze and to determine the doses that the POE will receive as well as the implementation of protection measures and appropriate radiological safety so that is completed the specified by the ALARA concept. In this work it is carried out an evaluation of the doses to receive for the POE when managing radionuclides with maximum activities that can be allowed in function of the current conditions of the cells and an evaluation of results is made with the program of surveillance and radiological protection implemented for the development of the works that carried out in the installation. (Author)

  18. Quality assurance program on the individual monitory service of the Protection Radiology Laboratory of the Universidade Federal de Pernambuco, Recife, PE (Brazil): preliminary results

    International Nuclear Information System (INIS)

    Antonino, Paulo H.D.; Filho, Joao A.; Silveira, Sueldo V.

    1996-01-01

    The current stage of the quality assurance program on the individual monitoring service of the Protection Radiology Laboratory of the Universidade Federal de Pernambuco, Recife, PE (Brazil) is presented. The program emphasizes the personnel training and its development is focused to meet national and international standards requirements

  19. Radiology standards for primary dental care: report by the Royal College of Radiologists and the National Radiological Protection Board

    International Nuclear Information System (INIS)

    Hudson, Tony

    1994-01-01

    In 1992 a joint venture between the Royal College of Radiologists (RCR) and the National Radiological Protection Board (NRPB) resulted in the formation of a Working Party (WP) to consider dental radiology. Although individual doses to patients are low, WP identified considerable scope for reducing the collective dose to patients and for improving the diagnostic quality of radiographs. The report published in the Documents of the NRPB series presents the WP conclusions in the form of guidelines that deal with all aspects of dental radiology in primary dental care. (Author)

  20. Analysis of conditions to safety and radiological protection of Brazilian research particle accelerators facilities

    International Nuclear Information System (INIS)

    Lourenco, Manuel Jacinto Martins

    2010-01-01

    Eleven institutions of education and research in Brazil use particle accelerators, which fulfill different functions and activities. Currently, these institutions employ a total of fifteen accelerators. In this paper, the object of study is the radiological protection of occupationally exposed individuals, the general public and the radiation safety of particle accelerators. Research facilities with accelerators are classified in categories I and II according to the International Atomic Energy Agency or groups IX and X in accordance with the Brazilian National Commission of Nuclear Energy. Of the 15 accelerators in use for research in Brazil, four belong to category I or group X and eleven belong to category II or group IX. The methodology presented and developed in this work was made through the inspection and assessment of safety and radiological protection of thirteen particle accelerators facilities, and its main purpose was to promote safer use of this practice by following established guidelines for safety and radiological protection. The results presented in this work showed the need to create a program, in our country, for the control of safety and radiological protection of this ionizing radiation practice. (author)

  1. Radiological protection and the selection of management strategies for intermediate level wastes

    International Nuclear Information System (INIS)

    Hill, M.D.; Webb, G.A.M.

    1982-01-01

    This paper describes the steps involved in selecting management systems and an overall management strategy for intermediate level solid radioactive wastes. The radiological protection inputs to intermediate level waste management decisions are discussed, together with the results of preliminary radiological assessments of disposal options. Areas where further work is required are identified. (author)

  2. Monitoring activities review of the Radiological Environmental Surveillance Program

    International Nuclear Information System (INIS)

    Ritter, P.D.

    1992-03-01

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

  3. A common approach for radiological protection of humans and the environment

    International Nuclear Information System (INIS)

    Holm, L.-E.

    2004-01-01

    Protection of the environment is developing rapidly at the national and international level, but there are still no internationally agreed recommendations as to how radiological protection of the environment should be carried out. The International Commission on Radiological Protection (ICRP) is currently reviewing its existing recommendations for human protection. It has set up a task group with the aim of developing a protection policy for, and suggesting a framework of, the protection of the environment that could feed into its recommendations at the start of the 21st century. The task group will propose a framework for the protection of the environment from harmful effects of radiation, harmonising with the principles for the protection of humans. Although the task group has not yet finalised on the objectives for the environment, these might be to safeguard the environment by preventing or reducing the frequency of effects likely to cause early mortality, reduced reproductive success, or the occurrence of scorable DNA damage in individual fauna and flora to a level where they would have a negligible impact on conservation of species, maintenance of biodiversity, or the health and status of natural habitats or communities. To achieve these objectives, a set of reference dose models, reference dose per unit intake and reference organisms will be required

  4. Biological effects and radiation protection in veterinary radiology: a literature review

    International Nuclear Information System (INIS)

    Rosa, P.C.; Siqueira, D.; Barros, F.S.

    2017-01-01

    Veterinary radiology is a tool of excellent diagnostic support. Besides X--ray, it counts on technological advances such as computed tomography, nuclear medicine and interventional radiology . It is common during X-ray practice to use exposure parameters with short times to avoid blurring by the movement of the animal, but the fact that the animals need to be immobilized during the exposures contribute significantly with the increase of the dose received by the professionals, whose biological risks are not yet well established as a result of exposure to other factors harmful to health, such as anesthetic gases, insecticides, zoonoses and others. For this reason, we sought to verify the main radiological risks to which veterinarians are exposed and the best means to guarantee radiological protection

  5. Education and training in radiological protection: the activities of the isRP

    International Nuclear Information System (INIS)

    Coeck, M.

    2005-01-01

    The International School for Radiological Protection, a task force within SCK-CEN, co-ordinates and organises training programs on all aspects of radiological protection. IsRP courses are directed as well to the private sector as to the political and academic world and the general public. International meetings, publications and recommendations with regard to safety culture increasingly stress the importance of education and training in the field of radiological protection. In addition, the need to standardise and harmonise the recognition of skills and practices on a national and European level is emerging. In this sense, the objectives of isRP are threefold : (1) to continue the organisation of open courses and training-on-demand of which the programmes are made up according to the background level and training requirements of the participants, and this for the Belgian medical and industrial sector; (2) to come to a closer cooperation with national universities and high schools and relevant international institutions; (3) to contribute to a better harmonisation of training practice and of skills recognition on a national and European level

  6. Course on radiology and radiation protection. 3. rev. enl. ed.

    International Nuclear Information System (INIS)

    1981-01-01

    This book shall serve as accompanying study text-book for students of medicine, who are in the clinical semesters in the course on radiology and radiation protection. The book deals in general with the field of radiology, starting from the physical and radiobiological fundamentals, through the large field of X-ray diagnostics and radiotherapy to nuclear medicine, including computerized tomography. Broad space is dedicated to radiation protection. A brief, strongly didactically divided text presents this large scientific field of knowledge in systematic order. It is illustrated by numerous tables and sketches, which shall facilitate understanding in cases of difficult problems. The book is completed by a detailed time table, by references to the essential and most important advancing literature and by a comprehensive subject index. (orig./HP) [de

  7. Training in radiological protection for nuclear programmes

    International Nuclear Information System (INIS)

    1975-01-01

    Many Member States are developing or already have developed their own national training programmes. The IAEA is actively involved in promoting training in radiological protection for nuclear programmes. The various types of training are fully discussed, with suggested curricula. An earlier report was published as Technical Reports Series No.31 in 1964. In 1973, new and additional information was received from Member States which is reflected in the present report. Training programmes are classified, according to those requiring training: specialists; persons whose work is closely related to radiological protection (administrators, public health officers and industrial health personnel, safety inspectors and engineers in nuclear installations, public service personnel); persons working with radiation; and the general public. Forms, scope and duration of training are discussed. Different types of training programmes are currently required for training of medical doctors (those providing medical surveillance for radiation workers and others dealing with public health aspects of radiation hazards), for technical supervisors, radiologists, and qualified workers in nuclear medicine, technological staff, administrators, persons working with radiation, and public service personnel. Standard curricula and desirable experiments and exercises are discussed. The organization of training together with the facilities, equipment and teaching staff required are considered, as is follow-up training. Annexes 1 to 4 give examples of training curricula and training courses available in various countries, a suggested syllabus for training of technical supervisors, and a bibliography consisting of 210 references dealing with general topics, nuclear radiation physics, radiochemistry and radiation chemistry, radiation biology and biophysics, dosimetry and health physics and radiation protection, medical aspects and toxicology, and environmental aspects

  8. Optimization of radiological protection in Spanish nuclear power plants

    International Nuclear Information System (INIS)

    O'Donnell, P.; Amor, I.; Butragueno, J.L.

    1997-01-01

    Optimizing the radiological protection of occupationally exposed nuclear power plant workers has become one further item in what is called the safety culture. Spanish facilities are implementing programme with this in mind, grounded on a personal motivation policy with the backing of a suitable organizational structure. (Author)

  9. Radiological protection in the Spanish nuclear industry under Franco, 1939-1975.

    Science.gov (United States)

    Menéndez-Navarro, Alfredo; Vázquez, Luis Sánchez

    2013-01-01

    In debates about nuclear controversy, the issue of occupational safety in radioactive facilities is rarely foregrounded; it has historically been relegated to second place compared to the attention given to potential harm to the general population. Aiming for, at least, partially filling this historiographical gap, this article deals with the development of occupational radiological protection in Spain under the dictatorship of General Franco (1939-1975). It covers the rise of radiological protection measures on an international level and the subsequent development of legislation in the case of Spain, a process that paralleled the growth of the nation's nuclear program. Finally, it explores the main evidence of the impact of ionizing radiation on Spain's working population.

  10. Implications of science and technology on the radiological protection system

    International Nuclear Information System (INIS)

    Metivier, H.; LAZO, T.

    2006-01-01

    Full text of publication follows: The mission of the Nuclear Energy Agency (Nea) Committee on Radiation Protection and Public Health (C.R.P.P.H.) includes providing member -country governments with insight into evolving or emerging issues that could affect radiation protection policy, regulation or application. Although it can not be currently said that the scientific understanding of radiological risks has significantly changed recently, ongoing radio-biological and epidemiological research could challenge the conventional paradigm in the mid -term future. The C.R.P.P.H. finalized in March 2006 finalize a study of possible challenges and their implications. This study includes two principle areas: challenges arising from scientific developments; and, challenges to the implementation of radiation protection. This report updates the earlier C.R.P.P.H. report, 'Developments in Radiation Health Sciences and their Impact on Radiation Protection' (Nea 1998). Broadly speaking, ongoing radiation biology studies present the possibility that our current practice of summing various type s of exposures into a single value of effective dose is not scientifically supported because of significantly differing dose/response relationships (chronic vs. acute, internal vs. external, high Let versus low Let, etc.). In addition, non-targeted effects, and the possibility of individual hyper-sensitivity to radiation further challenge our current notion of the relationship between detriment and dose. Although there is no conclusive evidence for this at this time, the possible implications of such changes will be investigated to better prepare governments and the radiation protection community should sound scientific evidence emerge. In addition to these possible scientific challenges, the applications and events that would require radiological protection input are also evolving. In particular, the use of radiation in medicine, with new techniques and the spread of existing technologies

  11. Influence of physical parameters on radiation protection and image quality in intra-oral radiology

    Science.gov (United States)

    Belinato, W.; Souza, D. N.

    2011-10-01

    In the world of diagnostic imaging, radiography is an important supplementary method for dental diagnosis. In radiology, special attention must be paid to the radiological protection of patients and health professionals, and also to image quality for correct diagnosis. In Brazil, the national rules governing the operation of medical and dental radiology were specified in 1998 by the National Sanitary Surveillance Agency, complemented in 2005 by the guide "Medical radiology: security and performance of equipment." In this study, quality control tests were performed in public clinics with dental X-ray equipment in the State of Sergipe, Brazil, with consideration of the physical parameters that influence radiological protection and also the quality of images taken in intra-oral radiography. The accuracy of the exposure time was considered acceptable for equipment with digital timers. Exposure times and focal-spot size variations can lead to increased entrance dose. Increased dose has also been associated with visual processing of radiographic film, which often requires repeating the radiographic examination.

  12. Influence of physical parameters on radiation protection and image quality in intra-oral radiology

    International Nuclear Information System (INIS)

    Belinato, W.; Souza, D.N.

    2011-01-01

    In the world of diagnostic imaging, radiography is an important supplementary method for dental diagnosis. In radiology, special attention must be paid to the radiological protection of patients and health professionals, and also to image quality for correct diagnosis. In Brazil, the national rules governing the operation of medical and dental radiology were specified in 1998 by the National Sanitary Surveillance Agency, complemented in 2005 by the guide 'Medical radiology: security and performance of equipment.' In this study, quality control tests were performed in public clinics with dental X-ray equipment in the State of Sergipe, Brazil, with consideration of the physical parameters that influence radiological protection and also the quality of images taken in intra-oral radiography. The accuracy of the exposure time was considered acceptable for equipment with digital timers. Exposure times and focal-spot size variations can lead to increased entrance dose. Increased dose has also been associated with visual processing of radiographic film, which often requires repeating the radiographic examination.

  13. Influence of physical parameters on radiation protection and image quality in intra-oral radiology

    Energy Technology Data Exchange (ETDEWEB)

    Belinato, W. [Instituto Federal de Ensino Basico, Tecnico e Tecnologico da Bahia, Av. Amazonas, 1350-45030-220, Zabele, Vitoria da Conquista, BA (Brazil); Departamento de Fisica, Universidade Federal de Sergipe, Av. Marechal Rondon s/n, 49100-000 Rosa Elze, Sao Cristovao, SE (Brazil); Souza, D.N., E-mail: divanizi@ufs.br [Departamento de Fisica, Universidade Federal de Sergipe, Av. Marechal Rondon s/n, 49100-000 Rosa Elze, Sao Cristovao, SE (Brazil)

    2011-10-01

    In the world of diagnostic imaging, radiography is an important supplementary method for dental diagnosis. In radiology, special attention must be paid to the radiological protection of patients and health professionals, and also to image quality for correct diagnosis. In Brazil, the national rules governing the operation of medical and dental radiology were specified in 1998 by the National Sanitary Surveillance Agency, complemented in 2005 by the guide 'Medical radiology: security and performance of equipment.' In this study, quality control tests were performed in public clinics with dental X-ray equipment in the State of Sergipe, Brazil, with consideration of the physical parameters that influence radiological protection and also the quality of images taken in intra-oral radiography. The accuracy of the exposure time was considered acceptable for equipment with digital timers. Exposure times and focal-spot size variations can lead to increased entrance dose. Increased dose has also been associated with visual processing of radiographic film, which often requires repeating the radiographic examination.

  14. Radiological and environmental surveillance in front-end fuel cycle facilities

    International Nuclear Information System (INIS)

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

    2004-01-01

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

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

    International Nuclear Information System (INIS)

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

    2010-01-01

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

  16. Radiological protection. Responsibility of the Safety Engineering Company

    International Nuclear Information System (INIS)

    Netto, A.L.

    1987-01-01

    This subject takes care of the Safety Engineering at the Radiologic Protection area on the X and Gama Rays Services. It mainly emphasis the case of that companies that, due do not have proper X and Gama Rays Services utilize partime task force on this area, but answer themselves for the safety of their employees in case of any accident occurence. (author) [pt

  17. Study on generic intervention levels for protecting the public in a nuclear accident or radiological emergency

    International Nuclear Information System (INIS)

    Suzuki, Fabio Fumio

    2003-01-01

    After a nuclear accident or radiological emergency, several social and economical factors shall be considered for the actions to protect the public and to recover the environment. The application of the radiological protection principles on practices in intervention situations may lead to adoption of protective measures disproportional to the involved risk, compromising the resources available to more effective actions. This causes a negative impact on the population and may conduct to discredit about the protective measures and the lost of confidence on the authorities. In this context, the principles of radiological protection for interventions should be studied and analyzed for being adequately applied in accident situations or radiological emergencies that involves the country. These principles are constantly improved and the concept of generic intervention level plays an important role in the decision-making to protect the public. The costs involved to the protective measures for the public in Brazil were studied and cost benefit analysis techniques were applied to estimate the generic intervention levels for public protection applicable in the country. These results were compared to those values internationally recommended, as well to values obtained in a similar study accomplished for Japan. It was also performed a sensibility analysis of the results regarding a value and a simple analysis of the results considering the costs of the several protective measures. (author)

  18. Korean anatomical reference data for adults for use in radiological protection

    Science.gov (United States)

    Choi, Chansoo; Yeom, Yeon Soo; Nguyen, Thang Tat; Lee, Hanjin; Han, Haegin; Shin, Bangho; Zhang, Xujia; Kim, Chan Hyeong; Chung, Beom Sun

    2018-01-01

    For radiological protection from exposure to ionizing radiation, in which a population-averaged dose evaluation is used, establishing a system of reference anatomical and physiological data for a specific population of interest is important. Some studies were done in the past to establish Korean reference data; however, the data provided the mass values only for a limited number of organs/tissues. In addition, the standing height and total body mass are based on 20-year-old data. In the present study, a new set of Korean reference anatomical values was established for use in the radiological protection of Korean workers and members of the public. The established Korean reference data provide the masses of 58 organs/tissues, including those needed to calculate the effective dose, which were derived by collecting and analyzing various scientific reports in the literature and data. In addition, the data provide not only standing height and total body mass, but also 131 additional anthropometric parameters; these values were derived from the most recent Korean national survey project, 7 th Size Korea. The characteristics of the data were also compared with several other population data, including the Asian and the International Commission on Radiological Protection (ICRP) reference data.

  19. Data Quality Objectives Supporting Radiological Air Emissions Monitoring for the PNNL Site

    Energy Technology Data Exchange (ETDEWEB)

    Barnett, J. Matthew; Meier, Kirsten M.; Snyder, Sandra F.; Fritz, Brad G.; Poston, Theodore M.; Antonio, Ernest J.

    2012-11-12

    Pacific Northwest National Laboratory (PNNL) is in the process of developing a radiological air monitoring program for the PNNL Site that is distinct from that of the nearby Hanford Site. The original DQO (PNNL-19427) considered radiological emissions at the PNNL Site from Physical Sciences Facility (PSF) major emissions units. This first revision considers PNNL Site changes subsequent to the implementation of the original DQO. A team was established to determine how the PNNL Site changes would continue to meet federal regulations and address guidelines developed to monitor air emissions and estimate offsite impacts of radioactive material operations. The result is an updated program to monitor the impact to the public from the PNNL Site. The team used the emission unit operation parameters and local meteorological data as well as information from the PSF Potential-to-Emit documentation and Notices of Construction submitted to the Washington State Department of Health (WDOH). The locations where environmental monitoring stations would most successfully characterize the maximum offsite impacts of PNNL Site emissions from the three PSF buildings with major emission units were determined from these data. Three monitoring station locations were determined during the original revision of this document. This first revision considers expanded Department of Energy operations south of the PNNL Site and relocation of the two offsite, northern monitoring stations to sites near the PNNL Site fenceline. Inclusion of the southern facilities resulted in the proposal for a fourth monitoring station in the southern region. The southern expansion added two minor emission unit facilities and one diffuse emission unit facility. Relocation of the two northern stations was possible due to the use of solar power, rather than the previous limitation of the need for access to AC power, at these more remote locations. Addendum A contains all the changes brought about by the revision 1

  20. Data Quality Objectives Supporting Radiological Air Emissions Monitoring for the PNNL Richland Campus

    Energy Technology Data Exchange (ETDEWEB)

    Snyder, Sandra F. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Moleta, Donna Grace L. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Meier, Kirsten M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Barnett, John M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2017-12-31

    This is the second revision of the DQO Supporting Radiological Air Emissions Monitoring for the Pacific Northwest National Laboratory Richland Campus. In January 2017, the PNNL Richland Campus expanded to the north by 0.35 km2 (85.6 acres). Under the requirements of Washington State Department of Health Radioactive Air Emissions License (RAEL)-005, the PNNL Campus operates and maintains a radiological air monitoring program. This revision documents and evaluates the newly acquired acreage while also removing recreational land at the southwest, and also re-examines all active radioactive emission units on the PNNL Campus. No buildings are located on this new Campus land, which was transferred from the U.S. DOE Hanford Site. Additionally, this revision includes information regarding the background monitoring station PNL-5 in Benton City, Washington, which became active in October 2016. The key purpose of this revision is to determine the adequacy of the existing environmental surveillance stations to monitor radiological air emissions in light of this northern boundary change.

  1. The management of radiological protection in a multi-employer environment

    International Nuclear Information System (INIS)

    Rankine, Alex

    2000-01-01

    For more than 40 years the UKAEA has been a world leader in the field of nuclear power R and D, pioneering the world's first civil nuclear programme and developing new nuclear power reactor technologies. Now that the initial programme has been successfully completed, UKAEA is again leading the world by pioneering new approaches to managing nuclear liabilities. In this new role, UKAEA is making a significant use of other companies in carrying out its decommissioning tasks and in providing support services. Whilst bringing with it new ideas and useful outside experience, this approach has given new challenges to UKAEA in ensuring that the work is carried out safety and that UKAEA is able to continue to exercise it's responsibilities as site operator and nuclear site licensee. This paper draws upon the experience within UKAEA to explore the management of radiological protection in a multi-employer situation emphasising the importance of co-operation between radiological protection experts, the need to clarify roles and responsibilities and the importance of worker participation. It is concluded that properly managed such an arrangement can not only work but can strengthen radiation protection building on various parties' strengths and experiences. One particular area where considerable use of service contractors has been undertaken is in radiological protection support services. UKAEA has now some unique experience in UK and have demonstrated that again, with adequate and appropriate management arrangements a potential challenge can be turned into an advantage. It is vital however that UKAEA is able to demonstrate sufficient in-house knowledge and expertise to remain in control as the site Licensee. (author)

  2. Public monitoring during the radiological accident in Goiania

    International Nuclear Information System (INIS)

    Ferreira, W.M.

    2000-01-01

    During the radiological accident with Cs 137 occurred at Goiania, Brazil, many people were contaminated. To identify the people with possible contamination a large place in the center of the city was selected for screening people with a possibility of contamination. This paper describes the work involved monitoring about 112.800 persons in a period of three month. (author)

  3. Radiological respiratory protection in Angra-1 Nuclear Power Plant; Protecao respiratoria radiologica na Usina Nuclear de Angra

    Energy Technology Data Exchange (ETDEWEB)

    Amaral, Marcos A. do [Furnas Centrais Eletricas S.A., Angra dos Reis, RJ (Brazil). Central Nuclear de Angra I. Div. de Protecao Radiologica e Ambiental

    1996-07-01

    The present paper has the purpose to describe the actual situation of the Radiological respiratory Protection in Angra I Nuclear Power Plant, the difficulties found and the goals to achieve, in order of the radiological protection excellence. (author)

  4. Optimization in radiological protection; Otimizacao em radioprotecao

    Energy Technology Data Exchange (ETDEWEB)

    Acosta Perez, Clarice de Freitas

    1996-07-01

    The optimization concept in radiation protection is, in its essence, practical. In each aspect that we deal with the man, it is necessary to take frequent decisions such as: what is the protection level to be pursued, since the protection levels under consideration provide doses lower than the appropriate annual limits. The optimization gives a basic framework of the minding that is appropriate to conduct to a balance kind of the resources available for the protection and protection level obtained against a multitude of factors and constrains in a manner to obtain the best result. In this work, was performed the optimization, from the radiation protection point of view, of a facility project who enclose two shielded hot cells where will be handled UO{sub 2} small plate with 50% of U-235 burn-up, irradiated in the research swimming pool reactor, IEA-R1. To obtain this goal were specified the relevant factors and criteria, were applied the main techniques used in a decision-making in radiological protection, presently adopted and was performed a sensibility study of the factors and criteria used in this work. In order to obtain a greater agility in applying the techniques for decision-making was developed a micro computer program. (author)

  5. Radiological Engineering: A graduate engineering - based curriculum for radiation protection

    International Nuclear Information System (INIS)

    Kearfott, K.J.; Wepfer, W.J.

    1994-01-01

    Several U.S. universities maintain formal graduate health physics curricula within their Colleges of Engineering. The term radiological engineering was coined to describe the discipline of applying engineering principles to the radiation protection aspects of nuclear technology. Radiological engineering programmes may require a specific core group of courses such as radiation biology, radiation protection practice, nuclear physics, radiation detectors, and radiation dosimetry. Students then might specialist in environmental, nuclear facilities or medical applications areas by selecting advanced courses and graduate design or research projects. In some instances the master's degree may be completed through remotely-delivered lectures. Such programmes promise to assist in educating a new group of engineering professionals dedicated to the safe utilisation of nuclear technology. The Georgis Institute of Technology's programme will serve as the specific example for this report. 8 refs., 1 fig

  6. The DOE policy for protection against radiological and toxicological sabotage

    International Nuclear Information System (INIS)

    Hassell, C. Jr.; Callahan, S.; Myers, D.

    1995-01-01

    In response to a Department of Energy Office of Security Evaluations study on radiological and toxicological sabotage, the Under Secretary of Energy has directed that all departmental elements initiate analyses to determine the extent of radiological and toxicological sabotage threats within the department. To accomplish this, a plan was adopted whereby radioactive and other hazardous materials at DOE sites would be assessed by an interdisciplinary team as to quantities, ranked according to their hazards, subjected to a vulnerability assessment, and appropriate upgrades selected and monitored. This paper is a discussion of those efforts

  7. Nuclear medicine and its radiological protection in China

    International Nuclear Information System (INIS)

    Wu, J.

    2001-01-01

    The China Society of Nuclear Medicine was established on 27 May 1980. Since then, nuclear medicine in clinical diagnosis and therapy has been developed rapidly in China. So far there are more than 4000 members of the Society, and more than 350 sets of SPECT and 12 sets of PET have been installed and are busily running in clinic nowadays and about 1 million patients with different types of diseases have obtained nuclear medicine imaging examinations per year. Concerning the nuclear medicine therapy, a lot of patients with many types of diseases obtained benefit from radioisotope therapy. Accordingly, several Policies and Regulations have been enacted by the Government for the radiological protection. Furthermore, a special book titled 'Standardization in Diagnostic and Therapeutic Nuclear Medicine' has been promulgated in June, 1997 by the Health Administration of People's Republic of China, and this book is distributed to almost every nuclear medicine physician and technician in China for their reference in routine nuclear medicine work or research. In this book three parts of the contents are covered: Policies and Regulations for the radiological protection, basic knowledge and clinical nuclear medicine applications. (author)

  8. Analgosedation and monitoring in interventional radiology

    International Nuclear Information System (INIS)

    Girolami, Guido; Steinbrich, Roman; Jacob, Augustinus Ludwig

    2010-01-01

    This article deals with the change of treatment in interventional radiology during the last decade adding a wider margin of safety through automated monitoring and better patient comfort through a combination of sedation and analgetics. In this regard it is very important to ensure adherence to standard procedures that are as simple as possible, to provide adequate training of staff members and to keep a succinct procedure protocol to ensure a high quality of care. Guidelines and checklists for the safe performance of this 'comfort-therapy' are given. (orig.)

  9. Radiological Protection of Patients in Nuclear Medicine

    International Nuclear Information System (INIS)

    Rojo, A.M.

    2011-01-01

    Full text: This lecture aims at presenting the state of the art of radiological protection of patients in nuclear medicine focusing on three aspects of interest where to achieve improvement. The hierarchy of the justification principle of the radiation protection is one of them. There seems for a change to be presented in the paradigm of the radiological protection of patients. The role of the physician who prescribes the medical practice becomes more relevant, together with the nuclear medicine specialist who should be co-responsible for the application of this justification principle. Regarding the doses optimization and the implementation of Dose Reference Level the involvement extends far beyond the physician and radioprotection officer. It is clear that the Medical Physicist is to play a very relevant role in the coordination of actions, as the nuclear medicine technician is to execute them. Another aspect to consider is patient specific dosimetry. It should become a routine practice through calculation of the absorbed dose based on biodistribution data. It should be assessed for each individual patient, as it depends on a number of patient-specific parameters, such as gender, size and the amount of fatty tissue in the body, as well as the extent and nature of the disease. In most cases, dosimetry calculations are not carried out and patients are administered standard levels of activity. There may be situations with a lack of knowledge on internal dosimetry as in many centers either none or only one or two medical physics experts are available. It shows that a formal training for experts in internal dosimetry at national level is required. However up to now, there has been no satisfactory correlation between absorbed dose estimates and patient response. Moreover, the radiation protection for the patient is not assured, as the dose values given are often numbers without connection to radiobiological and/or hematological findings. Pending tasks related to

  10. Assessment of radiation protection awareness and knowledge about radiological examination doses among Italian radiographers.

    Science.gov (United States)

    Paolicchi, F; Miniati, F; Bastiani, L; Faggioni, L; Ciaramella, A; Creonti, I; Sottocornola, C; Dionisi, C; Caramella, D

    2016-04-01

    To evaluate radiation protection basic knowledge and dose assessment for radiological procedures among Italian radiographers A validated questionnaire was distributed to 780 participants with balanced demographic characteristics and geographic distribution. Only 12.1 % of participants attended radiation protection courses on a regular basis. Despite 90 % of radiographers stating to have sufficient awareness of radiation protection issues, most of them underestimated the radiation dose of almost all radiological procedures. About 5 % and 4 % of the participants, respectively, claimed that pelvis magnetic resonance imaging and abdominal ultrasound exposed patients to radiation. On the contrary, 7.0 % of the radiographers stated that mammography does not use ionising radiation. About half of participants believed that radiation-induced cancer is not dependent on age or gender and were not able to differentiate between deterministic and stochastic effects. Young radiographers (with less than 3 years of experience) showed a higher level of knowledge compared with the more experienced radiographers. There is a substantial need for radiographers to improve their awareness of radiation protection issues and their knowledge of radiological procedures. Specific actions such as regular training courses for both undergraduate and postgraduate students as well as for working radiographers must be considered in order to assure patient safety during radiological examinations. • Radiographers should improve their knowledge on radiation protection issues. • Only 12.1 % of participants attended radiation protection courses on a regular basis. • Specific actions must be considered in order to increase knowledge and awareness.

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

    International Nuclear Information System (INIS)

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

    1998-01-01

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

  12. International recommendations on scope of radiological protection regulations - ICRP Publication 104

    International Nuclear Information System (INIS)

    Stanescu, Gabriel; Avadanei, Camelia; Ghilea, Simion

    2011-01-01

    The system of radiological protection applies, in principle, to all exposures to ionising radiation. Nevertheless, in practice, the measures taken in order to control these exposures should be limited for pragmatic reasons. ICRP Publication 104 deals with the scope of radiological protection control measures and describes the instruments that can be used for this purpose: exclusion, exemption, clearance. This paper aims to present the ICRP recommendations on scope of regulations in all types of exposure situations: planned, emergency and existing. Also, there are discussed the instruments available to regulators in different exposure situations. Exclusion refers to the deliberate omission of exposure situations from the scope of regulatory requirements, and exemption refers to waiving regulatory requirements if their application is not warranted. A special case of exemption, termed 'clearance', refers to the relinquishing of regulatory control if such a control becomes unwarranted. Societal attitudes to the control of exposure situations are taken into account in determining what can be excluded or exempted from regulatory control. People have higher demands for controlling 'artificial' exposure situations than for dealing with 'natural' exposure situations. Therefore, account should be taken not only of the justification and optimisation of controlling measures, but also of the different expectations of those affected by the exposure situations. The recommendations in this report are intended to assist in defining what needs to be the subject of regulatory requirements for radiological protection and what does not. The application of regulatory controls should achieve a net benefit in protection; otherwise, regulatory control is not justified. Similarly, regulatory requirements should be applied in a manner that optimises protection, otherwise the application of regulatory requirements is not warranted. (authors)

  13. Core ethical values of radiological protection applied to Fukushima case: reflecting common morality and cultural diversities.

    Science.gov (United States)

    Kurihara, Chieko; Cho, Kunwoo; Toohey, Richard E

    2016-12-01

    The International Commission on Radiological Protection (ICRP) has established Task Group 94 (TG94) to develop a publication to clarify the ethical foundations of the radiological protection system it recommends. This TG identified four core ethical values which structure the system: beneficence and non-maleficence, prudence, justice, and dignity. Since the ICRP is an international organization, its recommendations and guidance should be globally applicable and acceptable. Therefore, first this paper presents the basic principles of the ICRP radiological protection system and its core ethical values, along with a reflection on the variation of these values in Western and Eastern cultural traditions. Secondly, this paper reflects upon how these values can be applied in difficult ethical dilemmas as in the case of the emergency and post-accident phases of a nuclear power plant accident, using the Fukushima case to illustrate the challenges at stake. We found that the core ethical values underlying the ICRP system of radiological protection seem to be quite common throughout the world, although there are some variations among various cultural contexts. Especially we found that 'prudence' would call for somewhat different implementation in each cultural context, balancing and integrating sometime conflicting values, but always with objectives to achieve the well-being of people, which is itself the ultimate aim of the radiological protection system.

  14. Code of practice and design principles for portable and transportable radiological protection systems

    International Nuclear Information System (INIS)

    Wells, F.H.; Powell, R.G.

    1980-10-01

    The Code of Practice and design principles for portable and transportable radiological protection systems are presented in three parts. Part 1 specifies the requirement for Radiological Protection Instrumentation (RPI) including operational characteristics and the effects of both a radiation and non-radiation environment. Part 2 satisfies the requirement for RPI equipment as regards the overall design, the availability, the reliability, the information display, the human factors, the power supplies, the manufacture and quality assurance, the testing and the cost. Part 3 deals with the supply, location and operation of the RPI equipment. (U.K.)

  15. Radiological protection issues in endovascular use of radiation sources

    International Nuclear Information System (INIS)

    2006-02-01

    The use of radiation from radioactive materials for cancer treatment is well established. However, examples of uses of radiation therapy for benign conditions have been limited. Placing a radioactive source in the blood vessel so as to irradiate the surrounding inner periphery of the vessel has been attempted in recent years to prevent restenosis after percutaneous coronary and peripheral interventions. This kind of endovascular application provides treatment options that are less invasive for various vascular conditions compared with open surgery. As a part of the International Atomic Energy Agency's (IAEA) function for providing for application of the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources (BSS) that were jointly sponsored by the IAEA, FAO, ILO, OECD/NEA, PAHO and WHO, the IAEA planned a coordinated research project (CRP) that was to start in 2002 on radiological protection problems in endovascular use of radiation sources. However, as experts soon realized that the interest in this modality was waning, the CRP was not initiated. Nevertheless, it was felt that it would be appropriate to compile the information available on radiological protection problems observed so far and their possible solutions. This work was seen as part of a broader IAEA programme that covered accident prevention in radiotherapy. Publications on this topic have included, inter alia, Lessons Learned from Accidental Exposures in Radiotherapy (Safety Reports Series No. 17); Accidental Overexposure of Radiotherapy Patients in Bialystok; Investigation of an Accidental Exposure of Radiotherapy Patients in Panama; Accidental Overexposure of Radiotherapy Patients in San Jose, Costa Rica; and Investigation of an Accidental Exposure of Radiotherapy Patients in Poland. Keeping in mind that endovascular applications involve specialists such as cardiologists, angiologists and surgeons, all of whom might not have a

  16. Design principles for radiological protection instrumentation systems

    International Nuclear Information System (INIS)

    Wells, F.H.; Powell, R.G.

    1981-02-01

    This Code of Practice takes the form of recommendations intended for designers and installers of Radiological Protection Instrumentation, and should also be of value to the newcomer to the R.P.I. field. Topics are discussed under the following headings: outline of R.P.I. requirements, specifying the requirement, satisfying the requirements, (overall design, availability and reliability, information display, human factors, power supplies, manufacture, quality assurance, testing, and cost analysis), supply, location and operation of the equipment, importance of documentation. (U.K.)

  17. Characterization of different qualities in X-rays, for instruments calibration in radiological protection

    International Nuclear Information System (INIS)

    Cejudo A, J.; Tovar M, V. M.; Vergara M, F.

    2010-09-01

    In the Secondary Laboratory of Dosimetric Calibration in Mexico was realized the qualities characterization of the series X-rays RQR reported in the International Code of Practices in Dosimetry and Diagnostic Radiology No. 457, using attenuator filters of high purity aluminum and ionizing radiation equipment of inherent filtration of 4 mm Be with and emergent X-radiation beam of 40 grades. For the attenuation was used a geometric arrangement with three beam limiters and a monitor camera prepared on the established form in the mentioned technical report, and a spherical ionization chamber with collection volume of 3.6 cm 3 , aligning its geometric center with the focus of X-rays tube to get that the incident radiation direction will be perpendicular to the ionization chamber. From the perspective of the radiological protection is important to know the X-radiation quality for the application dedicated to the instruments calibration and can to give to these the traceability to a reference laboratory, this way the quality combination and reference chamber can give as a result a procedure for the evaluation of the entrance in surface dose to estimate the dose orientate levels, specified in the basic standards of safety. (Author)

  18. The recommendations 2007 of the International Commission of Radiological Protection (ICRP)

    International Nuclear Information System (INIS)

    Sugier, A.; Lecomte, J.F.; Nenot, J.C.

    2007-01-01

    This article deals with the 2007 Recommendations of the International Commission on Radiological Protection (ICRP), in particular in the situations of emergency exposure, after an accident or to natural radioactivity. (authors)

  19. L-061: EPR--First responders: Risk and Protection radiological emergency

    International Nuclear Information System (INIS)

    2011-01-01

    This conference is about the basic risks, protection and the consequences in a radiological emergency. The first responders have to know the deterministic and stochastic effects in the health as well as the cancer risk due of the high radioactive doses exposure

  20. Online remote radiological monitoring during operation of Advance Vitrification System (AVS), Tarapur

    International Nuclear Information System (INIS)

    Deokar, U.V.; Kulkarni, V.V.; Mathew, P.; Khot, A.R.; Singh, K.K.; Kamlesh; Deshpande, M.D.; Kulkarni, Y.

    2010-01-01

    Advanced Vitrification System (AVS) is commissioned for vitrification of high level waste (HLW) by using Joule heated ceramic melter first time in India. The HLW is generated in fuel reprocessing plant. For radiological surveillance of plant, Health Physics Unit (HPU) had installed 37 Area Gamma Monitors (AGM), 7 Continuous Air Monitors (CAM) and all types of personal contamination monitors. Exposure control is a major concern in operating plant. Therefore in addition to installed monitors, we have developed online remote radiation monitoring system to minimize exposures to the surveyor and operator. This also helped in volume reduction of secondary waste. The reliability and accuracy of the online monitoring system is confirmed by calibrating the system by comparing TLD and DRD readings and by theoretical analysis. In addition some modifications were carried in HP instruments to make them user friendly. This paper summarizes different kinds of remote radiological monitoring systems installed for online monitoring of Melter off Gas (MOG) filter, Hood filter, three exhaust filter banks, annulus air sampling and over pack monitoring in AVS. Our online remote monitoring system has helped the plant management to plan in advance for replacement of these filters, which resulted in considerable saving of collective dose. (author)

  1. 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

  2. Analysis of radiological protection and security in the radioactive diagnosis area in a third level hospital

    International Nuclear Information System (INIS)

    Azorin Vega, J.C.; Aazorin Nieto, J.; Rivera Montalvo, T.

    1998-01-01

    Results from the evaluation made to radiological security and protection conditions prevailing in 13 medical diagnosis rooms with X rays at the National Nutrition Institute Zlavador Zubiran (third level hospital), aiming to give adequate protection and radiological security devices to the staff exposed from that hospital and to comply fully with requirements set by the standards

  3. Radioactivity in the environment. A summary and radiological assessment of the Environment Agency's monitoring programmes; report for 1997

    International Nuclear Information System (INIS)

    1997-01-01

    The Radioactive Substances Act 1993 provides for controls to be exercised over the keeping and use of radioactive materials and, in particular, on the accumulation and disposal of radioactive wastes. The Environment Agency is responsible for administration and enforcement of the Act in England and Wales. In support of these regulatory functions and as part of the UK Government's arrangements for providing information to the European Commission under the Euratom Treaty, the Agency commissions independent monitoring of radioactive waste disposals and their impact on the environment, and monitoring of radioactivity in air, rainwater and drinking water sources. This report presents the data from these monitoring programmes and provides a commentary on their radiological significance. It includes assessments of radiation exposure of members of the public for compliance with the annual dose limit recommended by the International Commission on Radiological Protection. Concentrations of radioactivity in water are also assessed in relation to the guidelines on drinking water quality recommended by the World Health Organisation. This report for 1997 is one of an annual series published by the Agency. It is being distributed to local authorities as part of the arrangements under the Radioactive Substances Act 1993 for provision of access to environmental information. The monitoring programmes and preparation of this report are managed by the Agency's National Compliance Assessment Service. (author)

  4. Annual evaluation of routine radiological survey/monitoring frequencies for the High Ranking Facilities Deactivating Project at Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1998-12-01

    The Bethel Valley Watershed at the Oak Ridge National Laboratory (ORNL) has several Environmental Management (EM) facilities that are designated for deactivation and subsequent decontamination and decommissioning (D and D). The Surplus Facilities Program at ORNL provides surveillance and maintenance support for these facilities as deactivation objectives are completed to reduce the risks associated with radioactive material inventories, etc. The Bechtel Jacobs Company LLC Radiological Control (RADCON) Program has established requirements for radiological monitoring and surveying radiological conditions in these facilities. These requirements include an annual evaluation of routine radiation survey and monitoring frequencies. Radiological survey/monitoring frequencies were evaluated for two High Ranking Facilities Deactivation Project facilities, the Bulk Shielding Facility and Tower Shielding Facility. Considerable progress has been made toward accomplishing deactivation objectives, thus the routine radiological survey/monitoring frequencies are being reduced for 1999. This report identifies the survey/monitoring frequency adjustments and provides justification that the applicable RADCON Program requirements are also satisfied

  5. Radiological protection and environmental monitoring in the area of the Asse mine. Annual report 1991

    International Nuclear Information System (INIS)

    Meyer, H.; Mueller-Lyda, I.

    1992-05-01

    The personnel at the site has been monitored in accordance with the provisions of the Radiation Protection Ordinance. In addition, ambient dose, ambient dose rate, and radioactivity levels of the air in the mine have been measured pursuant to the health physics provisions of the Radiation Protection Ordinance. None of the measured results indicated any dose received by the persons, or ambient radioactivity levels, exceeding the maximum permissible values determined for occupational exposure. Continuous monitoring of the mine off-gas has shown a minor accumulation of the nuclides, H-3, C-14, Pb-210 and of the short-lived daughter products of Rn-222 and Rn-220. The average annual emission values serving as input data, the concentration levels computed for the environment of the mine for some part have been below the levels of the naturally occurring concentrations of these nuclides. The emission-induced radiation dose measured at the least favourable place in the plant's vicinity has been far below the maximum permissible dose defined in the Radiation Protection Ordinance. All activities carried out in the Asse salt mine for the purpose of research work and storage of radioactive waste in the period under review have been contributing only a negligible amount to the radiation exposure of the population or personnel, as compared to the natural or other man-made radioactivity levels in that area. (orig.) [de

  6. Radiological protection and environmental monitoring in the area of the Asse mine. Annual report 1990

    International Nuclear Information System (INIS)

    Meyer, H.; Mueller-Lyda, I.

    1991-07-01

    The personnel at the site has been monitored in accordance with the provisions of the Radiation Protection Ordinance. In addition, ambient dose, ambient dose rate, and radioactivity levels of the air in the mine have been measured pursuant to the health physics provisions of the Radiation Protection Ordinance. None of the measured results indicated any dose received by the persons, or ambient radioactivity levels, exceeding the maximum permissible values determined for occupational exposure. Continuous monitoring of the mine off-gas has shown a minor accumulation of the nuclides. H-3, C-14, Pb-210 and of the short-lived daughter products of Rn-222 and Rn-220. The average annual emission values serving as input data, the concentration levels computed for the environment of the mine for some part have been below the levels of the naturally occurring concentrations of these nuclides. The emission-induced radiation dose measured at the least favourable place in the plant's vicinity has been far below the maximum permissible dose defined in the Radiation Protection Ordinance. All activities carried out in the Asse salt mine for the purpose of research work and storage of radioactive waste in the period under review have been contributing only a negligible amount to the radiation exposure of the population or personnel, as compared to the natural or other man-made radioactivity levels in that area. (orig.) [de

  7. Remote level radiation monitoring system for the brazilian IEA-R1 nuclear research reactor for routine radiation protection procedures and as a support tool in case of radiological emergency

    International Nuclear Information System (INIS)

    Cardenas, Jose P.N.; Romero Filho, Christovam R.; Madi Filho, Tufic

    2008-01-01

    Nuclear facilities must monitoring radiation levels to establish procedures for radiological protection staff involving workers and the public. The Instituto de Pesquisas Energeticas e Nucleares - IPEN has 5 important plants and in case of accident in one of them, the Institute keeps operational an Emergency Response Plan (ERP). This document (ERP) is designed to coordinate all procedures to assure safe and secure conditions for workers, environment and the public. One of this plants is the IEA-R1 reactor, it is the oldest nuclear research reactor (pool type) in Latin America, reached it first criticality in September of 1957. The reactor is used 60 hours/week with continuous operation and with nominal power of 3.5 MW, with technical conditions to operate at 5 MW thermal power. This reactor has a Radiological Emergency Plan that establishes the implementation of rules for workers and people living at the exclusion area in the case of an emergency situation. This paper aims to describe the implementation of a computational system developed for remote radiation monitoring, in a continuous schedule of IEA-R1 nuclear research reactor containment building. Results of this action can be used as a support mean in a radiological emergency. All necessary modules for radiation detection, signals conditioners and processing, data acquisition board, software development and computer specifications are described. The data acquisition system operating in the reactor shows readings concerned to radiation environment such as activity, doses and concentration in real time and displays a periodical data bank (Data Base) of this features allowing through the surveillance of the operation records anytime, leading to studies and analysis of radiation levels. Results of this data acquisition are shown by means of computer graphics screens developed for windows environment using Visual Basic software. (author)

  8. Radiation protection during decommissioning of the salt cavern Asse II. Recommendations by the German Commission on radiological protection; Strahlenschutz bei der Stilllegung der Schachtanlage Asse II. Empfehlung der Strahlenschutzkommission

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2016-09-15

    The recommendations by the German Commission on radiological protection concerning radiation protection during decommissioning of the salt cavern Asse II include the following issues: radiological consequences of non-controllable solution ingress, optional decommissioning modes, basis requirements of decommissioning, fact evaluation, determination of radiation exposure, radiological requirements for long-term safety, analysis of consequences and long-term safety demonstration, data and information, emergency protection, public transparency.

  9. Involving stakeholders in radiological protection decision making: recovery history and lessons from the people of Fukushima.

    Science.gov (United States)

    Lazo, T

    2016-12-01

    Between September 2011 and August 2015, the International Commission on Radiological Protection (ICRP) organised a series of 12 stakeholder dialogue workshops with residents of Fukushima Prefecture. Discussions focused on recovery, addressing topics such as protection of children, management of contaminated food, monitoring, and self-help measures. The OECD Nuclear Energy Agency (NEA) supported, and the Committee on Radiation Protection and Public Health (CRPPH) Secretariat attended, all 12 meetings to listen directly to the concerns of affected individuals and draw lessons for CRPPH. To summarise the dialogue results, ICRP organised a final meeting in Date, Japan with the support of NEA and other organisations. The lessons from and utility of the dialogue meetings were praised by dialogue participants and sponsors, and ICRP agreed that some form of dialogue would continue, although with ICRP participation and support rather than leadership. This paper summarises the internationally relevant lessons learned by CRPPH from this important process.

  10. Radiological protection in medicine. ICRP Publication 105

    International Nuclear Information System (INIS)

    2011-01-01

    This report was prepared to underpin the Commission's 2007 Recommendations with regard to the medical exposure of patients, including their comforters and carers, and volunteers in biomedical research. It addresses the proper application of the fundamental principles (justification, optimisation of protection, and application of dose limits) of the Commission's 2007 Recommendations to these individuals. With regard to medical exposure of patients, it is not appropriate to apply dose limits or dose constraints, because such limits would often do more harm than good. Often, there are concurrent chronic, severe, or even life-threatening medical conditions that are more critical than the radiation exposure. The emphasis is then on justification of the medical procedures and on the optimisation of radiological protection. In diagnostic and interventional procedures, justification of procedures (for a defined purpose and for an individual patient), and management of the patient dose commensurate with the medical task, are the appropriate mechanisms to avoid unnecessary or unproductive radiation exposure. Equipment features that facilitate patient dose management, and diagnostic reference levels derived at the appropriate national, regional, or local level, are likely to be the most effective approaches. In radiation therapy, the avoidance of accidents is a predominant issue. With regard to comforters and carers, and volunteers in biomedical research, dose constraints are appropriate. Over the last decade, the Commission has published a number of documents that provided detailed advice related to radiological protection and safety in the medical applications of ionising radiation. Each of the publications addressed a specific topic defined by the type of radiation source and the medical discipline in which the source is applied, and was written with the intent of communicating directly with the relevant medical practitioners and supporting medical staff. This report

  11. ICRP Publication 105. Radiological Protection in Medicine

    International Nuclear Information System (INIS)

    Aubert, Bernard; Biau, Alain; Derreumaux, Sylvie; Etard, Cecile; Rannou, Alain; Rehel, Jean-Luc; Roch, Patrice Elle a ete validee par le Professeur Jean-Marc Cosset

    2011-01-01

    This report was prepared to underpin the Commission's 2007 Recommendations with regard to the medical exposure of patients, including their comforters and carers, and volunteers in biomedical research. It addresses the proper application of the fundamental principles (justification, optimisation of protection, and application of dose limits) of the Commission's 2007 Recommendations to these individuals. With regard to medical exposure of patients, it is not appropriate to apply dose limits or dose constraints, because such limits would often do more harm than good. Often, there are concurrent chronic, severe, or even life-threatening medical conditions that are more critical than the radiation exposure. The emphasis is then on justification of the medical procedures and on the optimisation of radiological protection. In diagnostic and interventional procedures, justification of procedures (for a defined purpose and for an individual patient), and management of the patient dose commensurate with the medical task, are the appropriate mechanisms to avoid unnecessary or unproductive radiation exposure. Equipment features that facilitate patient dose management, and diagnostic reference levels derived at the appropriate national, regional, or local level, are likely to be the most effective approaches. In radiation therapy, the avoidance of accidents is a predominant issue. With regard to comforters and carers, and volunteers in biomedical research, dose constraints are appropriate. Over the last decade, the Commission has published a number of documents that provided detailed advice related to radiological protection and safety in the medical applications of ionising radiation. Each of the publications addressed a specific topic defined by the type of radiation source and the medical discipline in which the source is applied, and was written with the intent of communicating directly with the relevant medical practitioners and supporting medical staff. This

  12. Radiological planning and implementation for nuclear-facility decommissioning

    International Nuclear Information System (INIS)

    Valentine, A.M.

    1982-01-01

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

  13. The relationship between the expectation of life of workers and the evolution of radiological protection's norms

    International Nuclear Information System (INIS)

    Santos, Marcio Pereira

    2008-01-01

    Full text: With the evolution of the norms of radiological protection in the world in last the 20 years, the life expectancy of Workers increased in direct ratio. The technological advance of the equipment that uses radiation sources and the deepening in the studies and knowledge on the ionizing radiations- e consequent deleterious effect- had contributed significantly for the reduction of the doses received for the Workers in its daily hours of working. Methods: A simple analysis of data, comparing itself the past and the gift, becomes evident that, in if treating to radiological protection, the humanity walks for a new age, which hardly will retrocede. If before the radiological protection was understood as a concern only in the practical doctors, with emphasis in the immediate effects, today already becomes gift in all the practical ones, especially in that they put into motion the planet and its wealth, in the industry. Major Values: Modernity took the man to the daily dependence of the not ionizing radiations, each time inserted of the people's day. As similar to, the radiological protection today if makes gift in diverse practical, to guarantee the cares to be taken and the fulfilment of pertinent norms. The present study it looks for to evidence that last the 20 years- marked for accidents with radioactive sources- they had been essential for a reflection of the norms of radiological protection. Thus, workers, as well as the technological sector, changed it the new reality, either demanding bigger training technician for the practical ones, attention special in security and radiological protection, or same establishing more rigid norms, through the regulating agencies. In the present work had a projection of values of life expectancy of the population, the past until the present. Analyzing Tables, as much for workers how much for the members of the public is noticed that the radiological protection offers to one better quality of life to all those involved

  14. Protective equipment of radiological protection and the worker wear

    International Nuclear Information System (INIS)

    Cassia, Flor Rita de; Huhn, Andrea; Lima, Gelbcke Francine

    2013-01-01

    This qualitative research with workers of seven hemodynamic service of Santa Catarina, Brazil aimed to analyze the use of radiological protection equipment (RPE), as well as wear to the health of workers who use these causes. The study was conducted between March 2010 and November 2010, totaling approximately 30 hours of observations. Results showed resistance to the use of RPE and also showed wear to workers' health, mainly due to the weight and discomfort they cause, as may weigh 7-9 pounds, depending on the model used. Evidenced also the absence of workers due herniated disc, back pain, and other musculo skeletal problems. These complaints, in addition to being related to the use of these protective gear also related with the time that workers remain standing for long periods on certain procedures, such as angioplasty. Given these results, the research recommended the use of these devices with materials, that are already being produced, making lighter aprons, thus avoiding fatigue and back pain and also provide greater comfort by reducing workers' resistance to its use and its adverse consequences

  15. Advanced Neutron Source radiological design criteria

    International Nuclear Information System (INIS)

    Westbrook, J.L.

    1995-08-01

    The operation of the proposed Advanced Neutron Source (ANS) facility will present a variety of radiological protection problems. Because it is desired to design and operate the ANS according to the applicable licensing standards of the Nuclear Regulatory Commission (NRC), it must be demonstrated that the ANS radiological design basis is consistent not only with state and Department of Energy (DOE) and other usual federal regulations, but also, so far as is practicable, with NRC regulations and with recommendations of such organizations as the Institute of Nuclear Power Operations (INPO) and the Electric Power Research Institute (EPRI). Also, the ANS radiological design basis is in general to be consistent with the recommendations of authoritative professional and scientific organizations, specifically the National Council on Radiation Protection and Measurements (NCRP) and the International Commission on Radiological Protection (ICRP). As regards radiological protection, the principal goals of DOE regulations and guidance are to keep occupational doses ALARA [as low as (is) reasonably achievable], given the current state of technology, costs, and operations requirements; to control and monitor contained and released radioactivity during normal operation to keep public doses and releases to the environment ALARA; and to limit doses to workers and the public during accident conditions. Meeting these general design objectives requires that principles of dose reduction and of radioactivity control by employed in the design, operation, modification, and decommissioning of the ANS. The purpose of this document is to provide basic radiological criteria for incorporating these principles into the design of the ANS. Operations, modification, and decommissioning will be covered only as they are affected by design

  16. Radiological protection in the interventional techniques: experience in the Pain Clinic of the CIMEQ

    International Nuclear Information System (INIS)

    Guerrero C, M. C.; Benitez N, P. P.; Gonzalez G, Y.; Martinez G, A.; Gonzalez R, N.; Sanchez Z, L. R.

    2014-08-01

    The Pain Clinic of the CIMEQ offers treatment to patients with different pathologies, using interventional techniques as the radiology like visual guide to reach the target structure and to apply the election technique. The personnel that carry out these procedures are inserted in the program of radiological surveillance of the institution, reason for which a radiological event could be detected where the main physician responsible of the service was implied. In this work the results of an investigation are presented realized with the objective of to know the causes of the event and to determine the necessary measures to avoid that this repeats again. The investigation was oriented to three fundamental aspects: medical exam of the affected worker; evaluation of the operational procedures from the radiological protection view point; and dosimetric measurements simulating the real conditions of work for which were used ionization chamber, radiometer and PMMA mannequin. As a result of the medical exam was detected that the main physician of the service did not use during the execution of all the procedures the extremities dosimetry and that he presented a radio induced erythema in the right hand, reason for which he was separated of the activity with ionizing radiations, until the conclusion of the investigation. With relationship to the evaluation of the operational procedures from the radiological protection view point, was verified that the medical physician not carried out any collimation of the beam and he was located in the positions where the dose rate reached the maximum values, frequently introducing the hands in the direct beam; that which implied an overexposure of the superior extremities and a not optimized exposure for whole body. This result was proven with the realized experimental measurements, which gave dose estimated values in extremities of the order of the deterministic effects. The investigation facilitated to introduce modifications in the

  17. Monitoring techniques for the impact assessment during nuclear and radiological emergencies: current status and the challenges

    International Nuclear Information System (INIS)

    Pradeepkumar, K.S.; Sharma, D.N.

    2003-01-01

    Preparedness and response capability for Nuclear and Radiological emergencies, existing world over, are mainly based on the requirement of responding to radiation emergency caused by nuclear or radiological accidents. Cosmos satellite accident, plutonium contamination at Polaris, nuclear accidents like Kystium, Windscale, TMI and Chernobyl, radiological accidents at Goiania etc have demonstrated the requirement of improved radiation monitoring techniques. For quick decision making, state of the art monitoring methodology which can support quantitative and qualitative impact assessment is essential. Evaluation of radiological mapping of the area suspected to be contaminated needs ground based as well as aerial based monitoring systems to predict the level of radioactive contamination on ground. This will help in delineating the area and deciding the required countermeasures, based on the quantity and type of radionuclides responsible for it. The response can be successful with the effective use of i) Early Warning System ii) Mobile Monitoring System and iii) Aerial Gamma Spectrometric System. Selection of the monitoring methodology and survey parameters and assessment of situation using available resources etc. are to be optimized depending on the accident scenario. Recently, many countries and agencies like IAEA have expressed the requirement for responding to other types of nuclear/radiological emergencies i.e, man made radiation emergency situations aimed at harming public at large that can also lead to environmental contamination and significant exposure to public. Reports of lost / misplaced / stolen radioactive sources from many countries are alarming as safety and security of these radioactive sources are under challenge. The monitoring methodology has to take into account of the increase in such demands and more periodic monitoring in suspected locations is to be carried out. Detection of orphan sources possible amidst large heap of metallic scraps may pose

  18. Work management to optimise occupational radiological protection

    International Nuclear Information System (INIS)

    Ahier, B.

    2009-01-01

    Occupational exposures at nuclear power plants worldwide have steadily decreased since the early 1990's. Regulatory pressures, technological advances, improved plant designs and operational procedures, as low as reasonably achievable (ALARA) culture and information exchange have contributed to this downward trend. However, with the continued ageing and possible life extensions of nuclear power plants, ongoing economic pressures, regulatory, social and political evolutions, and the potential of new nuclear build, the task of ensuring that occupational exposures are kept as low as reasonably achievable continues to present challenges to radiological protection professionals

  19. Implementation of the National Incident Management System (NIMS)/Incident Command System (ICS) in the Federal Radiological Monitoring and Assessment Center(FRMAC) - Emergency Phase

    International Nuclear Information System (INIS)

    NSTec Environmental Restoration

    2007-01-01

    Homeland Security Presidential Directive HSPD-5 requires all federal departments and agencies to adopt a National Incident Management System (NIMS)/Incident Command System (ICS) and use it in their individual domestic incident management and emergency prevention, preparedness, response, recovery, and mitigation programs and activities, as well as in support of those actions taken to assist state and local entities. This system provides a consistent nationwide template to enable federal, state, local, and tribal governments, private-sector, and nongovernmental organizations to work together effectively and efficiently to prepare for, prevent, respond to, and recover from domestic incidents, regardless of cause, size, or complexity, including acts of catastrophic terrorism. This document identifies the operational concepts of the Federal Radiological Monitoring and Assessment Center's (FRMAC) implementation of the NIMS/ICS response structure under the National Response Plan (NRP). The construct identified here defines the basic response template to be tailored to the incident-specific response requirements. FRMAC's mission to facilitate interagency environmental data management, monitoring, sampling, analysis, and assessment and link this information to the planning and decision staff clearly places the FRMAC in the Planning Section. FRMAC is not a mitigating resource for radiological contamination but is present to conduct radiological impact assessment for public dose avoidance. Field monitoring is a fact-finding mission to support this effort directly. Decisions based on the assessed data will drive public protection and operational requirements. This organizational structure under NIMS is focused by the mission responsibilities and interface requirements following the premise to provide emergency responders with a flexible yet standardized structure for incident response activities. The coordination responsibilities outlined in the NRP are based on the NIMS

  20. Application of radiological protection measures to meet different environmental protection criteria

    International Nuclear Information System (INIS)

    Copplestone, D.

    2012-01-01

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

  1. Hanford radiological protection support services annual report for 1987

    International Nuclear Information System (INIS)

    Lyon, M.; Fix, J.J.; Kenoyer, J.L.; Leonowich, J.A.; Palmer, H.E.; Sula, M.J.

    1988-08-01

    This report documents the performance of certain radiological protection sitewide services during calendar year (CY) 1987 by Pacific Northwest Laboratory in support of the US Department of Energy-Richland Operations Office (DOE-RL) and contractor activities on the Hanford Site. The routine program for each service is discussed along with any significant program changes and tasks, investigations, and studies performed in support of each program. Other related activities such as publications, presentations, and memberships on standards or industry committees are also discussed. The programs covered provide services in the areas of: external dosimetry, internal dosimetry, in vivo measurements, instrument calibration and evaluation, calibration of radiation sources traceable to the National Bureau of Standards, and radiological records. 21 refs., 10 figs., 12 tabs

  2. Radiological safety system based on real-time tritium-in-air monitoring indoors and in effluents

    International Nuclear Information System (INIS)

    Bidica, N.; Sofalca, N; Balteanu, O.; Srefan, I.

    2006-01-01

    Exposure to tritium is an important health hazard in any tritium processing facility so that implementing a real-time tritium monitoring system is necessary for its operation in safety conditions. The tritium processing facility operators need to be informed at any time about the in-air tritium concentration indoors or in the stack effluents, in order to detect immediately any leaks in tritium containments, or any releases inside the buildings or to the environment. This information is very important for adopting if necessary protection measures and correcting actions as quickly as possible. In this paper we describe an improved real-time tritium monitoring system designed for the Heavy Water Detritiation Pilot Plant of National Institute for Cryogenics and Isotopes Separation, Rm. Valcea, Romania. The design of the Radiological Safety System implemented for the ICIT Water Detritiation Pilot Plant is intended to provide the maximum safety level based on the ALARA concept. The main functions of tritium monitoring system are: - monitoring the working areas and gaseous effluents by determination of the tritium-in-air activity concentration; - local and remote data display; - assessing of environment dose equivalent rates and dose equivalents in the working environment (for personnel exposure control and work planning); - assessing the total tritium activity released to the environment through ventilation exhaust stack; - safety functions, i.e., local and remote, locking/unlocking personnel access, process shut-down in emergency conditions and start of the air cleaning systems. With all these features our tritium monitoring system is really a safety system adequate for personnel and environmental protection. (authors)

  3. Code of practice and design principles for installed radiological protection systems

    International Nuclear Information System (INIS)

    Powell, R.G.

    1979-03-01

    For some years there has been comprehensive guidance documentation for Nuclear Reactor Instrumentation, but apparently no corresponding guide for designers and installers of Radiological Protection Instrumentation. A small group of instrumentation engineers discussed this lack of a suitable guide, and they examined the main points on which it should be based. This document attempts to present a comprehensive and detailed review of these points. It is intended to give an overall coverage and serve as a reference document for specific points; it should also be of value to the newcomer to the Radiological Protection Instrumentation field. This Code of Practice represents a standard of good practice and takes the form of recommendations only. Each installation must be assessed individually, and agreement on its suitability must be reached locally by the designers and the officers responsible for safety and operation. (author)

  4. Principles of the International Commission on Radiological Protection system of dose limitation

    International Nuclear Information System (INIS)

    Thorne, M.C.

    1987-01-01

    The formulation of a quantitative system of dose limitation based on ICRP principles of 'stochastic' and 'non-stochastic' effects requires that judgements be made on several factors including: relationships between radiation dose and the induction of deleterious effects for a variety of endpoints and radiation types; acceptable levels of risk for radiation workers and members of the public; and methods of assessing whether the cost of introducing protective measures is justified by the reduction in radiation detriment which they will provide. In the case of patients deliberately exposed to ionising radiations, the objectives of radiation protection differ somewhat from those applying to radiation workers and members of the public. For patients, risks and benefits relate to the same person and upper limits on acceptable risks may differ grossly from those appropriate to normal individuals. For these reasons, and because of its historical relationship with the International Congress of Radiology, the ICRP has given special consideration to radiation protection in medicine and has published reports on protection of the patient in diagnostic radiology and in radiation therapy. (author)

  5. Proceedings of the First European workshop on the ethical dimensions of the radiological protection system

    International Nuclear Information System (INIS)

    2013-12-01

    The System of radiological protection develops gradually integrating advances in knowledge about the effects of radiation, the feedback from its practical implementation in all relevant domains, as well as the evolution of the ethical and social values that shape community life in modern societies. Although there is a long tradition of ICRP to consider such values in the development of its Recommendations, there is a need to make them explicit. This should facilitate the understanding of the system for specialists and non-specialists in radiological protection and allow a renewed dialogue on its foundations, its objectives and rationality. It should also encourage the emergence of informed behaviours in society vis-a-vis radiations. In this perspective, ICRP has initiated a reflection in the recent years on the ethical dimensions of the radiological protection system. This reflection has highlighted the links between the fundamental principles of radiation protection (justification, optimization, limitation) and the theories of normative ethics. The recommendations of the Commission are designed to respect individual rights (deontological ethics), to promote the collective interest (utilitarian ethics) and favour vigilance and equity (virtue ethics). This reflection it also identified the interest for the analysis of the radiological protection system to distinguish the ethical values defining the standards by which action should be taken, the ethical procedures for integrating these values in decision making and in the implementation of the decisions, and the ethical behaviour corresponding to the values that are supposed to guide the conduct of the various actors. Because the radiation protection system is intended to be international, the reflection also emphasized the importance of promoting through the Recommendations, values common to different cultures such as autonomy, non-maleficence, beneficence and justice. The objective of the Workshop is to explore

  6. Geoinformation dataware for radiological monitoring of territories

    Science.gov (United States)

    Zatserkovnyi, V. I.; Kozachenko, E. V.; Shishenko, O. I.

    2015-10-01

    The paper provides a study, during which the fully accessible and open information from the literature and thematic maps is processed and systemized, reflecting the state of the problem of the radiological monitoring of the territories using the geoinformation technology. The stated ArcGIS technologies is used in the Web ecological Chernihiv region atlas for the map binding of sites and zones of the radioactive and chemical contamination of the territories as well as filling the atlas data with ecological and economical resources of the region.

  7. The radiological protection in the practice of industrial X-rays

    International Nuclear Information System (INIS)

    Jimenez C, I.; Carrasco C, R.

    2010-09-01

    The kindness of this technique of non destructive assays is very appreciative when the protection standards and radiological protection are completed faithfully, this work show in a succinct way the development through the years where have improved the equipment s, the procedures, the training and the regulation. This development has allowed reduce the dose to the occupational exposed personnel, to the public, but mainly the accidents incidence with loss of fingers, hands, legs and worker lives, children and the people in general. (Author)

  8. The impact of regulatory control on monitoring of pregnant hospital staff in diagnostic radiology

    International Nuclear Information System (INIS)

    Faulkner, K.; Rawlings, D.J.; Marshall, N.W.

    1997-01-01

    In 1990, the International Commission on Radiological Protection recommended the introduction of a supplementary dose limit for pregnant staff so that the foetus was adequately protected. This dose limit was framed in terms of an abdomen surface dose of 2 mSv for the duration of the pregnancy, once it had been declared. The philosophical basis underlying this supplementary dose limit was the desire to treat the foetus as a member of the public in respect of the occupational exposure of the mother. In the Basic Safety Standards, the International Atomic Energy Agency endorsed the need to limit the foetal dose, but in this document the dose limit refers to the foetus. The introduction of dose limits for foetal exposure to radiation has significant implications for hospitals as many workers are women of child bearing age. The practical implications of this dose limit will be discussed as well as suggested monitoring arrangements. (author)

  9. The work of the international commission on radiological protection

    International Nuclear Information System (INIS)

    Clarke, R.H.

    1996-01-01

    ICRP was established in 1928 as the International X-ray and Radium Protection Committee. In 1950 the name was changed to reflect the wider scope of radiological protection. The present membership of the Main Commission and its four committees was established in July 1993 for the period 1993-1997. Their programmes of work are now nearing completion with the Committees having met four times and their progress is summarised. The Main Commission meets in November 1996, when one of the main topics will be the election of the new Commission and members of the four Committees for the period 1997-2001

  10. Rack Protection Monitor - A Simple System

    International Nuclear Information System (INIS)

    Orr, S.

    1997-12-01

    The Rack Protection Monitor is a simple, fail-safe device to monitor smoke, temperature and ventilation sensors. It accepts inputs from redundant sensors and has a hardwired algorithm to prevent nuisance power trips due to random sensor failures. When a sensor is triggered the Rack Protection Monitor latches and annunicates the alarm. If another sensor is triggered, the Rack Protection Monitor locally shuts down the power to the relay rack and sends alarm to central control

  11. Radiological protection national system. Basic security rules

    International Nuclear Information System (INIS)

    1981-01-01

    This work has been prepared as the first one of a set of standards and regulations that will be enforced to provide the protection of men and the environment against the undesirable effects of ionizing radiations. It establishes, in the first place, the system of dose limits for the country and the principles of its utilization. It takes into account the CIPR's recommendations in this area and the mentioned frame of reference, it establishes further the necessary restrictions for the application of the limits to the professionally exposed workers, as well as to the isolated members of the public and the population in general. In addition it establishes the general conditions to be met for the implementation of radiological protection, among them, the classification of working areas and working conditions as well as the compulsory periodical medical surveillance. (H.D.N.)

  12. Formation in radiological protection of the personnel of sanitary installations in Peru

    International Nuclear Information System (INIS)

    Medina G, E.

    2006-01-01

    All the people that work with ionizing radiations should have a singular license according to that settled down in the effective legal standards in force in Peru. This authorization is granted by the Peruvian Institute of Nuclear Energy (IPEN) after the postulant demonstrates that he can work in sure form in the application where it uses ionizing radiations. From 1972 the Superior Center of Nuclear Studies (CSEN) of the IPEN it has carried out diverse training courses on radiological safety and protection in medicine, industry and research, such it is so until the year 2005 it has organized 458 courses where 5872 people have been qualified in the country. 75% of people was qualified in the period 2000 - 2005. The courses are organized according to the specific work with radiations and in the one case of medical radiodiagnostic, dental radiology, nuclear medicine and radiotherapy has been qualified 2337 people (doctors, medical technicians and technicians) by means of 174 courses made among the years 2000 at the 2005, corresponding 69,75% to people qualified in radiological protection in medical radiodiagnostic. (Author)

  13. Generic procedures for monitoring in a nuclear or radiological emergency

    International Nuclear Information System (INIS)

    2005-03-01

    This book is a Japanese version of the International Atomic Energy Agency (IAEA) publication (Report No., IAEA-TECDOC-1092, published in Vienna, 1999) of the same title. The translation of the original English into Japanese was done by the Department of Dose Assessment, Research Center for Radiation Emergency Medicine, National Institute of Radiological Sciences (NIRS). Since the Department was organized in addition to the Emergency Medicine Dept. in the Center in 2003 to establish a system for rapid and accurate dose assessment at emergent radiation exposure, the translation is thus a result of the department works, and is published with permission by IAEA as one of a series of NIRS Report (NIRS-M--179) for use in the country. The book is essentially a manual for providing technical requirements and procedures for radiation monitoring, environmental sampling and laboratory analyses for a nuclear or other radiological emergency. The contents are: Introduction, Outline of monitoring, Monitoring of outdoor radiation and contamination, Outdoor sampling, Gross alpha/beta measurement, Gamma spectrometry, Activation analyses, Basic data assessment, Work-sheets, Check-list for measuring equipments, Appendices, References, and others. (S.I.)

  14. Guidelines for planning and design of mobile radiological units

    Energy Technology Data Exchange (ETDEWEB)

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

    1995-07-01

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

  15. Guidelines for planning and design of mobile radiological units

    International Nuclear Information System (INIS)

    Schelenz, R.

    1995-01-01

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

  16. Legislation and Organization of Radiological Protection in the Republic of Argentina

    International Nuclear Information System (INIS)

    Gonzalez, A.; Carrea, A.; Nowotny, G.

    1979-01-01

    The history of legislation and organization of radiological protection goes hack to 1950 in Argentina. The terms of references of the National Commission of Atomic Energy in Argentina are outlined and the actual organization of the authority is also presented. (author)

  17. Experience of the Argentine Radioprotection Society in training in radiological protection

    International Nuclear Information System (INIS)

    Bomben, A.M.

    2006-01-01

    From its creation in 1967, the Argentine Radioprotection Society (SAR) has as basic purpose promoting all the aspects related with the radiological protection and the nuclear safety. Due to the great increment in the use of radioactive sources in diverse areas, soon it was evident for the SAR the importance and necessity to promote the knowledge of the radioprotection approaches between the users of radioactive sources and ionizing radiations in all its application fields, be these industrial, academic or doctors. From the year 2000, the SAR comes organizing in regular and periodical form basic and specialized courses about radiological safety of radioactive sources for industrial use and profile of oil wells, among others. In this work, the characteristics of the different dictated courses are described whose programs have been developed keeping in mind the requirements of the competent authorities of Argentina. Also, statistical information on the dictated courses and its participants is presented. The number of dictated courses was incremented from 6 (year 2000) up to 16 (year 2005), being also increased significantly the number of participants for course. The dictated courses are theoretical-practical, with a duration average of 20 hs. The educational body is constituted by specialists in the different topics with recognized experience. Its given to the participants notes and support material, as well as copies of the material presented to develop the course. When concluding the courses, its deliver to the participants certifies of attendance and/or approval, as it corresponds. In their headquarters the SAR has didactic facilities and specific equipment for the dictation of the courses. Also accounts with the easiness of dictating those courses outside of their headquarters. This is particularly advantageous for companies or organizations that are seated in points far from the main cities and they should qualify in radiological safety to the personnel but, by

  18. A new means of communication with the populations: the Extremadura Regional Government Radiological Monitoring alert WEB Page

    International Nuclear Information System (INIS)

    Baeza, A.; Vasco, J.; Miralles, Y.; Torrado, L.; Gil, J. M.

    2003-01-01

    XXI a summary sheet, relatively easy to interpret, giving the radiation levels and dosimetry detected during the immediately proceeding semester. Recently too, the challenge has been taken on of providing constantly, updated information on as complex a topic as the radiological monitoring of the environment. To this end, a Web page has been developed dealing with the operation and results provided by the aforementioned Radiological Warning Betwork of Extremadura. The page structure consists of seven major blocks: (i) origin and objectives of the network; (ii) a description of the stations of the network; (iii) their modes of operation in normal circumstances and in the case of an operational or radiological anomaly; (iv) the results that the network provides; (v) a glossary of terms to clarify as straightforwardly as possible some of the terms and concepts that are of unavoidable use, but are unfamiliar to the population in general; (vi) information about links to other Web sites that also deal with this issue to some degree; and (vii) giving the option of questions and contacts between the visitor to the page and those responsible for its creation and maintenance. Actions such as that described here will doubtless contribute positively to increasing the necessary trust that the population deserves to have in the correct operation of the measures adopted to guarantee their adequate radiological protection. (Author)

  19. Report of ICRP Task Group 80: 'radiological protection in geological disposal of long-lived solid radioactive waste'.

    Science.gov (United States)

    Weiss, W

    2012-01-01

    The report of International Commission on Radiological Protection (ICRP) Task Group 80 entitled 'Radiological protection in geological disposal of long-lived solid radioactive waste' updates and consolidates previous ICRP recommendations related to solid waste disposal (ICRP Publications 46, 77, and 81). The recommendations given in this report apply specifically to geological disposal of long-lived solid radioactive waste. The report explains how the 2007 system of radiological protection, described in ICRP Publication 103, can be applied in the context of the geological disposal of long-lived solid radioactive waste. The report is written as a self-standing document. It describes the different stages in the lifetime of a geological disposal facility, and addresses the application of relevant radiological protection principles for each stage depending on the various exposure situations that can be encountered. In particular, the crucial factor that influences application of the protection system over the different phases in the lifetime of a disposal facility is the level of oversight that is present. The level of oversight affects the capability to reduce or avoid exposures. Three main time frames have to be considered for the purpose of radiological protection: time of direct oversight when the disposal facility is being implemented and active oversight is taking place; time of indirect oversight when the disposal facility is sealed and indirect oversight is being exercised to provide additional assurance on behalf of the population; and time of no oversight when oversight is no longer exercised because memory is lost. Copyright © 2012. Published by Elsevier Ltd.

  20. RadNet Radiological Air Monitoring Network

    International Nuclear Information System (INIS)

    Scott Telofski, J.; Askren, D.R.; Petko, Ch.M.; Fraass, R.G.

    2010-01-01

    The United States Environmental Protection Agency operates a national environmental radiation monitoring program called RadNet. RadNet monitors airborne particulates, precipitation, milk, and drinking water for radiation levels. The primary purpose of the original program in the 1950's and 1960's was to collect and analyze samples in various media to assess the effects of radioactive fallout from above-ground nuclear weapon testing. As above-ground testing diminished in the 1970's, the program, especially the air network, became critical in evaluating effects of other types of nuclear incidents, such as the nuclear reactor accident at Chernobyl, as well as monitoring trends in environmental radioactive contamination. The value of rapid data collection subsequent to such incidents led to the consideration of developing air monitors with radiation detectors and telecommunication equipment for real-time radiation measurement. The strengthened United States homeland security posture after 2001 led to production and installation of the current real-time RadNet air monitors. There are now 118 stationary, continuously operating air monitoring stations and 40 mobile air monitors for site specific monitoring. The stationary air monitors include radiation detectors, meteorological sensors, a high-volume air sampler, and communication devices for hourly data transfers. When unusual levels are detected, scientists download a full sodium iodide detector spectrum for analysis. The real-time data collected by RadNet stationary systems permit rapid identification and quantification of airborne nuclides with sufficient sensitivity to provide critical information to help determine protective actions. The data also may help to rapidly refine long-range radioactive plume models and estimate exposure to the population. This paper provides an overview of the airborne particulate monitoring conducted during above-ground nuclear weapon testing, summarizes the uses of data from the program

  1. Quality control in dental diagnostic radiology : anomalous in the use of radiological equipment

    International Nuclear Information System (INIS)

    Alcaraz, M.; Martinez-Beneyto, Y.; Jodar, S.; Velasco, E.; Garcia-Vera, M. C.

    2004-01-01

    7,176 official quality control reports on dental diagnostic radiology were studied, relating to dental clinics located in 37 Spanish provinces covering 16 different autonomous Regions. The reports were issued as a result of the entry into force of Royal Decree 2071/1995 on quality control in General Diagnostic Radiology facilities, this Royal Decree was replaced by R. D. 1976/1999. The reports were writen by the UTPR (Technical Unit of Radiological Protection) Agsigma S. A. L., a company approved by the Nuclear Safety Council, and they correspond with the official reports issued during 1996-2001. This meants that a 5-year period has been monitored in order to observe the impacts of the establlishment of this legislation on quality control in intraoral dental diagnostic radiology facilities. The results show that 72.79% of the reports checked in 2001 would comply with the European Union's official recommendation (70 kVp, 8 mA> 1.5 mm of Al and 20 cm collimator length). Significant alterations have detected in a third (30.59%) of the radiological equipment. (Author) 36 refs

  2. Protecting and improving health through the radiological sciences. A report to the Surgeon General

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1966-04-01

    This is the third in a series of reports prepared by the-National Advisory Committee on Radiation for the Surgeon General of the Public Health Service. The first two were directed to the broad responsibilities of the Service in the field of radiation control and to problems concerned with the protection of the public against undue radiation exposure from contamination of the environment with radioactive materials. In this report the Committee traces the remarkable growth that has taken place in the uses of ionizing radiation in the health professions, in industry, and in other walks of life. It also notes a number of emerging problems which not only are of importance from the point of view of radiation protection, but also, if not alleviated, threaten the quality of medical care in the United States and the translation of the advances of atomic research into needed benefits for the people. These problems include (a) serious weaknesses in academic departments of radiology which have restricted efforts to provide adequate instruction of medical and post-doctoral students in the clinical applications of ionizing radiation, including radiation protection; and (b) an increasingly severe shortage of manpower in all branches of the radiological sciences. The magnitude and complexity of these problems are sufficiently great that a concerted effort is needed by the Public Health Service to correct them. The alleviation of the problems just cited is but a part of a more comprehensive series of responsibilities faced by the Service in the radiological sciences. The Service must play an important role in the prevention of undue exposure of the population from medical, occupational, and environmental sources of ionizing radiation; at the same time, it must actively support the development and application of radiological methods in the diagnosis and treatment of diseases. In order that the Service may effectively meet its enlarging responsibilities in the radiological sciences

  3. Protecting and improving health through the radiological sciences. A report to the Surgeon General

    International Nuclear Information System (INIS)

    1966-04-01

    This is the third in a series of reports prepared by the-National Advisory Committee on Radiation for the Surgeon General of the Public Health Service. The first two were directed to the broad responsibilities of the Service in the field of radiation control and to problems concerned with the protection of the public against undue radiation exposure from contamination of the environment with radioactive materials. In this report the Committee traces the remarkable growth that has taken place in the uses of ionizing radiation in the health professions, in industry, and in other walks of life. It also notes a number of emerging problems which not only are of importance from the point of view of radiation protection, but also, if not alleviated, threaten the quality of medical care in the United States and the translation of the advances of atomic research into needed benefits for the people. These problems include (a) serious weaknesses in academic departments of radiology which have restricted efforts to provide adequate instruction of medical and post-doctoral students in the clinical applications of ionizing radiation, including radiation protection; and (b) an increasingly severe shortage of manpower in all branches of the radiological sciences. The magnitude and complexity of these problems are sufficiently great that a concerted effort is needed by the Public Health Service to correct them. The alleviation of the problems just cited is but a part of a more comprehensive series of responsibilities faced by the Service in the radiological sciences. The Service must play an important role in the prevention of undue exposure of the population from medical, occupational, and environmental sources of ionizing radiation; at the same time, it must actively support the development and application of radiological methods in the diagnosis and treatment of diseases. In order that the Service may effectively meet its enlarging responsibilities in the radiological sciences

  4. Radiological emergencies the first response

    International Nuclear Information System (INIS)

    2011-11-01

    This national training course about radiological emergencies first answer include: Targets and preparation for emergency response in case of a nuclear or radiological accident. Operations center, action guide for fire fighting, medical coverage, forensic test, first aid, basic instrumentation for radiation, safety equipment, monitoring radiation, gamma rays, personnel exposed protection , radiation exposure rate, injury and illness for radiation, cancer risk, contamination, decontamination and treatment, markers, personnel dosimetry, training, medical and equipment transportation, shielded and tools. Psychological, physical (health and illness), economical (agriculture and industry) and environment impacts. Terrorist attacks, security belts. Support and international agreements (IAEA)

  5. Occupational exposure of diagnostic radiology staff in Israel during 1994-1996

    International Nuclear Information System (INIS)

    Biran, T.; Malchi, S.; Shamai, Y.

    1997-01-01

    Personnel who perform interventional radiological procedures which involve long fluoroscopy times and with a high workload, may receive radiation doses comparable to one of the dose limits suggested by the International Commission on Radiological protection. It is therefore important to monitor accurately the radiation dose to every staff member. who is involved in fluoroscopy procedures. (authors)

  6. Medical preparedness and response in nuclear accidents. The health team's experience in joint work with the radiological protection area

    International Nuclear Information System (INIS)

    Maurmo, Alexandre Mesquita

    2007-01-01

    The interaction between the health and the radiological protection areas has proved fundamental, in our work experience, for the quality of response to victims of accidents, involving ionizing radiation. The conceptions and basic needs comprehension of the adequate response, on these two areas, have brought changes to the essential behavior related to the victim's care, the protection response, the environment and waste production. The joint task of health professionals and radiological protection staff, as first responders, demonstrates that it is possible to adjust practices and procedures. The training of professionals of the radiological protection area by health workers, has qualified them on the basic notions of pre-hospital attendance, entitling the immediate response to the victim prior to the health team arrival, as well as the discussion on the basic concepts of radiological protection with the health professionals, along with the understanding of the health area with its specific needs on the quick response to imminent death risk, or even the necessary procedures of decontamination. (author)

  7. Radiological Protection in Transition. Proceedings of the 14. Regular Meeting of the Nordic Society for Radiation Protection, NSFS

    Energy Technology Data Exchange (ETDEWEB)

    Valentin, J; Cederlund, T; Drake, P; Finne, I E; Glansholm, A; Jaworska, A; Paile, W; Rahola, T [eds.

    2005-09-01

    These proceedings comprise the papers and posters presented at the 14th Regular Meeting of the Nordic Society for Radiation Protection, the theme of which was 'Radiological protection in transformation'. There were sessions on international developments and stakeholder involvement, on education, training, and measurements, on emergencies, on nuclear installations, on non-ionising radiation, on medical radiation, on industrial uses of radiation, on radiobiology, on natural sources of radiation, on non-nuclear waste, on NKS (Nordic Nuclear Safety Research), on radioecology and artificial radionuclides in the environment, and on regulatory and international activities. In addition to invited lectures and proffered papers, there were educational primer lessons in the mornings and several roundtable discussions. In all, there were almost 100 contributions from participants representing at least 10 different countries. The range of different topics covered, the scientific quality of the contributions, and the interest shown in this meeting reflect the high standing of radiological protection in the Nordic countries.

  8. Radiological Protection in Transition. Proceedings of the 14. Regular Meeting of the Nordic Society for Radiation Protection, NSFS

    International Nuclear Information System (INIS)

    Valentin, J.; Cederlund, T.; Drake, P.; Finne, I.E.; Glansholm, A.; Jaworska, A.; Paile, W.; Rahola, T.

    2005-09-01

    These proceedings comprise the papers and posters presented at the 14th Regular Meeting of the Nordic Society for Radiation Protection, the theme of which was 'Radiological protection in transformation'. There were sessions on international developments and stakeholder involvement, on education, training, and measurements, on emergencies, on nuclear installations, on non-ionising radiation, on medical radiation, on industrial uses of radiation, on radiobiology, on natural sources of radiation, on non-nuclear waste, on NKS (Nordic Nuclear Safety Research), on radioecology and artificial radionuclides in the environment, and on regulatory and international activities. In addition to invited lectures and proffered papers, there were educational primer lessons in the mornings and several roundtable discussions. In all, there were almost 100 contributions from participants representing at least 10 different countries. The range of different topics covered, the scientific quality of the contributions, and the interest shown in this meeting reflect the high standing of radiological protection in the Nordic countries

  9. Radiological Protection in Transition. Proceedings of the 14. Regular Meeting of the Nordic Society for Radiation Protection, NSFS

    Energy Technology Data Exchange (ETDEWEB)

    Valentin, J.; Cederlund, T.; Drake, P.; Finne, I.E.; Glansholm, A.; Jaworska, A.; Paile, W.; Rahola, T. (eds.)

    2005-09-01

    These proceedings comprise the papers and posters presented at the 14th Regular Meeting of the Nordic Society for Radiation Protection, the theme of which was 'Radiological protection in transformation'. There were sessions on international developments and stakeholder involvement, on education, training, and measurements, on emergencies, on nuclear installations, on non-ionising radiation, on medical radiation, on industrial uses of radiation, on radiobiology, on natural sources of radiation, on non-nuclear waste, on NKS (Nordic Nuclear Safety Research), on radioecology and artificial radionuclides in the environment, and on regulatory and international activities. In addition to invited lectures and proffered papers, there were educational primer lessons in the mornings and several roundtable discussions. In all, there were almost 100 contributions from participants representing at least 10 different countries. The range of different topics covered, the scientific quality of the contributions, and the interest shown in this meeting reflect the high standing of radiological protection in the Nordic countries.

  10. The radiological protection in the nuclear medicine practice

    International Nuclear Information System (INIS)

    Maldonado M, H.

    2010-09-01

    The nuclear medicine practice dates of the 1950 years, in this work the achievements reached as regards radiological protection are shown, although even lack a lot to make, the doses for the occupationally exposed personnel have decreased with lapsing of the years, thanks to the perception of the nuclear physicians to improve the administration techniques of the radioactive material, the decrease of administered activity and the unit doses use among the most remarkable advances. The changes in the equipment s technology to quantify the activity to administer, detection systems and image formation have demanded the development of the new professionals of the nuclear medicine that allows give protection to the patient. This improvement needs to consolidate with the appropriate normative development, the involved personnel qualification and the methods and procedures actualization to improve the protection of the occupationally exposed personnel, the public, the environment and the patient. (Author)

  11. Proceedings of the 3. Brazilian forum on health science and technology; 15. Brazilian congress on biomedical engineering; 6. Brazilian congress of physicists in medicine; 5. Brazilian congress of informatics in health; Brazilian meeting on radiological protection. v. 1

    International Nuclear Information System (INIS)

    1996-01-01

    The importance of radiological protection and monitoring, development of quality control programs, radiation protection standards and procedures, are discussed. Such aspects are highlighted in nuclear medicine and radiodiagnosis to improve performance - considering both better image and safety working conditions

  12. Radiological protection of the worker in medicine and dentistry

    Energy Technology Data Exchange (ETDEWEB)

    1990-01-01

    The first three sections of this report concern general understanding of radiation protection, basic concepts for all workers, and practical problems common to all users of radiation in medicine and dentistry. The remaining sections cover specialist topics covering practical aspects in diagnostic radiology, dental radiography, the use of unsealed radionuclides (in the laboratory, diagnostic and therapeutic uses) balneotherapy, brachytherapy and external beam radiotherapy. (author).

  13. Radiological protection of the worker in medicine and dentistry

    International Nuclear Information System (INIS)

    1990-01-01

    The first three sections of this report concern general understanding of radiation protection, basic concepts for all workers, and practical problems common to all users of radiation in medicine and dentistry. The remaining sections cover specialist topics covering practical aspects in diagnostic radiology, dental radiography, the use of unsealed radionuclides (in the laboratory, diagnostic and therapeutic uses) balneotherapy, brachytherapy and external beam radiotherapy. (author)

  14. The radiological monitoring protocol for metallic products and cleared scrap management

    International Nuclear Information System (INIS)

    Gil Lopez, E.

    2003-01-01

    Event though the use of nuclear and radiological techniques is subject to strict controls in most countries, the presence of radioactive material in batches of metallic scrap has been detected with relative frequency in the last few years. This circumstance has motivated the implementation of a series of national and international initiatives aimed at detecting and preventing this type of events, whether they be intentional or involuntary. The Spanish iron and steel industry is one of the country's most important industrial sectors, and to a great extent it depends on the importation of a very significant amount of metallic scrap that it uses as raw material. Experience has shown that countries that import large amounts of scrap, apart from supporting the mentioned international initiatives, should complement them with other national initiatives to reduce the risks resulting from the presence of radioactive material in scrap. In this context, the Spanish authorities, together with trade unions and entrepreneurial associations in the metal reclamations and smelting sectors and ENRESA, have signed a voluntary Protocol that defines and implements a national radiological monitoring and control system for scrap materials and their byproducts. The Protocol defines the obligations and rights of the signatories, and it describes the monitoring and control system and its legal bases, the operation of both specific and other general-purpose radiological monitoring equipment that existed prior to this initiative, the development of radiological training and dissemination plans for professionals in the metal reclamation and smelting sectors, the establishment of effective systems for the safe management of any radioactive materials detected, and the general improvement of the national response system in the event of radiological emergencies. Since the Protocol took effect in November 1999, more than 100 enterprises from the metallurgical (steel, copper, lead and aluminum

  15. Hanford Radiological Protection Support Services Annual Report for 1999

    Energy Technology Data Exchange (ETDEWEB)

    TP Lynch; DE Bihl; ML Johnson; MA MacLellan; RK Piper

    2000-05-19

    During calendar year (CY) 1999, the Pacific Northwest National Laboratory (PNNL) performed its customary radiological protection support services in support of the U.S. Department of Energy (DOE) Richland Operations Office (RL) and the Hanford contractors. These services included: (1) external dosimetry, (2) internal dosimetry, (3) in vivo measurements, (4) radiological records, (5) instrument calibration and evaluation, and (6) calibration of radiation sources traceable to the National Institute of Standards and Technology (NIST). The services were provided under a number of programs as summarized here. Along with providing site-wide nuclear accident and environmental dosimetry capabilities, the Hanford External Dosimetry Program (HEDP) supports Hanford radiation protection programs by providing external radiation monitoring capabilities for all Hanford workers and visitors to help ensure their health and safety. Processing volumes decreased in CY 1999 relative to prior years for all types of dosimeters, with an overall decrease of 19%. During 1999, the HEDP passed the National Voluntary Laboratory Accreditation Program (NVLAP) performance testing criteria in 15 different categories. HEDP computers and processors were tested and upgraded to become Year 2000 (Y2K) compliant. Several changes and improvements were made to enhance the interpretation of dosimeter results. The Hanford Internal Dosimetry Program (HIDP) provides for the assessment and documentation of occupational dose from intakes of radionuclides at the Hanford Site. Performance problems carried over from CY 1998 continued to plague the in vitro bioassay contractor. A new contract was awarded for the in vitro bioassay program. A new computer system was put into routine operation by the in vivo bioassay program. Several changes to HIDP protocols were made that were related to bioassay grace periods, using field data to characterize the amount of alpha activity present and using a new default particle

  16. Hanford Radiological Protection Support Services Annual Report for 1999

    International Nuclear Information System (INIS)

    TP Lynch; DE Bihl; ML Johnson; MA MacLellan; RK Piper

    2000-01-01

    During calendar year (CY) 1999, the Pacific Northwest National Laboratory (PNNL) performed its customary radiological protection support services in support of the U.S. Department of Energy (DOE) Richland Operations Office (RL) and the Hanford contractors. These services included: (1) external dosimetry, (2) internal dosimetry, (3) in vivo measurements, (4) radiological records, (5) instrument calibration and evaluation, and (6) calibration of radiation sources traceable to the National Institute of Standards and Technology (NIST). The services were provided under a number of programs as summarized here. Along with providing site-wide nuclear accident and environmental dosimetry capabilities, the Hanford External Dosimetry Program (HEDP) supports Hanford radiation protection programs by providing external radiation monitoring capabilities for all Hanford workers and visitors to help ensure their health and safety. Processing volumes decreased in CY 1999 relative to prior years for all types of dosimeters, with an overall decrease of 19%. During 1999, the HEDP passed the National Voluntary Laboratory Accreditation Program (NVLAP) performance testing criteria in 15 different categories. HEDP computers and processors were tested and upgraded to become Year 2000 (Y2K) compliant. Several changes and improvements were made to enhance the interpretation of dosimeter results. The Hanford Internal Dosimetry Program (HIDP) provides for the assessment and documentation of occupational dose from intakes of radionuclides at the Hanford Site. Performance problems carried over from CY 1998 continued to plague the in vitro bioassay contractor. A new contract was awarded for the in vitro bioassay program. A new computer system was put into routine operation by the in vivo bioassay program. Several changes to HIDP protocols were made that were related to bioassay grace periods, using field data to characterize the amount of alpha activity present and using a new default particle

  17. ENETRAP: training and education in radiological protection

    International Nuclear Information System (INIS)

    Coeck, M.

    2006-01-01

    The development of a common European radiation protection and safety culture and, based on that, the mutual recognition of radiation protection courses and the acquired competencies of radiation protection experts (RPE) and officers (RPO) is becoming a real need. The ENETRAP project ('European Network for Education and Training in RAdiological Protection') aims at bringing together different ideas and approaches of education and training (E and T) in radiological protection (RP) in order to better integrate and harmonise national E and T activities on a European level. The project started in April 2005. 10 partners are involved in ENETRAP: SCK-CEN (coordinator), CEA-INSTN, FZK-FTU, BfS, ENEA, NRG, CIEMAT, HPA-RPD, UJF and UHI-NHC. These partners have years of experience with established E and T programmes and play an important role in the development of specific techniques such as e-learning or On-the-Job Training (OJT) related to RP. As a result of their fundamental scientific research, collaboration with industry and practical experience, the partners have a solid scientific knowledge of all aspects of RP and are ideally placed to transfer the know-how and estimate the needs in this field. The ENETRAP project aims at establishing a sustainable E and T infrastructure for RP as an essential component to combat the perceived decline in expertise and to ensure the continuation of the high level of RP knowledge. The main objectives of the ENETRAP project are (1) to better integrate existing E and T activities in the RP infrastructure of the European countries in order to combat the decline in both student numbers and teaching institutions, (2) to develop more harmonised approaches for E and T in RP in Europe, (3) to better integrate the national resources and capacities for E and T and (4) to provide the necessary competence and expertise for the continued safe use of radiation in industry, medicine and research. Any such infrastructure must ensure that provision is

  18. National Institute for Radiological Protection and Nuclear Safety - IRSN. Annual Report 2016, Financial Report 2016

    International Nuclear Information System (INIS)

    2017-01-01

    IRSN is the nation's public service expert in nuclear and radiation risks, and its activities cover all the related scientific and technical issues in France and in the international arena. Its work therefore concerns a wide range of complementary fields, including environmental monitoring, radiological emergency response, radiation protection and human health in normal and accident situations, prevention of major accidents, and safety and security relating to nuclear reactors, plants, laboratories, transportation, and waste. It also carries out assessments in the nuclear defense field. In addition, IRSN contributes to government policy in nuclear safety, the protection of human health and the environment against ionizing radiation, and measures aimed at safeguarding nuclear materials, facilities and transportation operations against the risk of malicious acts. Within this context, it interacts with all the organizations concerned including public authorities, in particular nuclear safety and security authorities, local authorities, businesses, research organizations, and stakeholder associations. This document is IRSN's annual and financial report for 2016. Content: 1 - Activity Key Figures; 2 - Strategy; 3 - Panorama 2016; 4 - Activities: safety (Safety of civil nuclear facilities, Experimental reactors, Nuclear fuel cycle facilities, Human and organizational factors, Reactor aging, Severe accidents, Fuel, Criticality, Fire and containment, Natural hazards, Defense-related facilities and activities, Radioactive waste management, Geological disposal of radioactive waste); security and nonproliferation (Nuclear security, Nuclear nonproliferation, Chemical weapons ban); radiation protection - human and environment health (Environmental monitoring, Radon and polluted sites, Radiation protection in the workplace, Effects of chronic exposure, Protection in health care); emergency and post-accident situations (Emergency preparedness and response, Post

  19. Emergency monitoring strategy and radiation measurements document of the NKS project emergency management and radiation monitoring in nuclear and radiological accidents (EMARAD)

    Energy Technology Data Exchange (ETDEWEB)

    Lahtinen, J. [Radiation and Nuclear Safety Authority (STUK) (Finland)

    2006-04-15

    This report is one of the deliverables of the NKS Project Emergency management and radiation monitoring in nuclear and radiological accidents (EMARAD) (20022005). The project and the overall results are briefly described in the NKS publication 'Emergency Management and Radiation Monitoring in Nuclear and Radiological Accidents. Summary Report on the NKS Project EMARAD' (NKS-137, April 2006). In a nuclear or radiological emergency, all radiation measurements must be performed efficiently and the results interpreted correctly in order to provide the decision-makers with adequate data needed in analysing the situation and carrying out countermeasures. Managing measurements in different situations in a proper way requires the existence of pre-prepared emergency monitoring strategies. Preparing a comprehensive yet versatile strategy is not an easy task to perform because there are lots of different factors that have to be taken into account. The primary objective of this study was to discuss the general problematics concerning emergency monitoring strategies and to describe a few important features of an efficient emergency monitoring system as well as factors affecting measurement activities in practise. Some information concerning the current situation in the Nordic countries has also been included. (au)

  20. Independent auto evaluation of an operative radiological protection program; Autoevaluacion independiente de un programa de proteccion radiologica operativa

    Energy Technology Data Exchange (ETDEWEB)

    Medrano L, M.A.; Rodriguez C, C.C.; Linares R, D.; Zarate M, N.; Zempoalteca B, R. [Gerencia Subsede Sureste Instituto Nacional de Investigaciones Nucleares, 52045 Ocoyoacac, Estado de Mexico (Mexico)]. e-mail: maam@nuclear.inin.mx

    2006-07-01

    The program of operative radiological protection of a nuclear power plant consists of multiple procedures and associate tasks that have as purpose the radiological protection of the workers of the power station. It is for this reason that the constant evaluation of the one it programs it is an important tool in the identification of their weaknesses (and strengths), so they can be assisted appropriately. In this work the main elements of the program of independent auto evaluation of the program of operative radiological protection of the Laguna Verde Central that has been developed and implemented by the National Institute of Nuclear Research are described. (Author)

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

    International Nuclear Information System (INIS)

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

    2015-09-01

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

  2. Postgraduate training in radiological protection by e-learning the technological platforms

    Energy Technology Data Exchange (ETDEWEB)

    Verdu, G., E-mail: gverdu@iqn.upv.es [Departamento de Ingeniera Quimica y Nuclear, Universidad Politcnica de Valencia (Spain); Mayo, P.; Alcaraz, D., E-mail: p.mayo@titaniast.com, E-mail: d.alcaraz@titaniast.com [TITANIA Servicios Teconologicos, Grupo Dominguis, Valencia (Spain); Campayo, J.M., E-mail: j.campayo@lainsa.com [LAINSA, Grupo Dominguis, Valencia, (Spain)

    2011-07-01

    The companies that are working in decontamination, dismantling and assessment in nuclear power plants, usually have their employees in different facilities far from its central offices. When there is a training in radiological protection applied to the nuclear field, it is difficult for these people the attendance to the course because of different reasons as the location of the formation centres which sometimes are not near from the nuclear facilities, so they usually cannot attend their daily work with the same effectiveness. In this work we present a postgraduate training in radiological protection supervised by Polytechnical University of Valencia (Spain) applied to nuclear and radioactive facilities by a technological platform developed in collaboration with the university. This platform is adapted and designed to different high level contents and applications in different areas and sections, related to a general part, radioactive facilities, nuclear facilities and advanced concepts. When the student finishes an area, an evaluation has to be done to prove the understanding of the lessons. We have included films of different activities as decontamination devices, radiation detectors..etc with the contents to make the explanations more understandable to the student. The course is complemented with a final review and exam that are not online to guarantee that the training is well finished. In addition the student has some practice related with different items explained during the training as the use of equipment in radiological protection tasks. This type of training is more flexitime and can be adapted to the necessities of each user, avoiding high costs and unnecessary displacements. (author)

  3. Postgraduate training in radiological protection by e-learning the technological platforms

    International Nuclear Information System (INIS)

    Verdu, G.; Mayo, P.; Alcaraz, D.; Campayo, J.M.

    2011-01-01

    The companies that are working in decontamination, dismantling and assessment in nuclear power plants, usually have their employees in different facilities far from its central offices. When there is a training in radiological protection applied to the nuclear field, it is difficult for these people the attendance to the course because of different reasons as the location of the formation centres which sometimes are not near from the nuclear facilities, so they usually cannot attend their daily work with the same effectiveness. In this work we present a postgraduate training in radiological protection supervised by Polytechnical University of Valencia (Spain) applied to nuclear and radioactive facilities by a technological platform developed in collaboration with the university. This platform is adapted and designed to different high level contents and applications in different areas and sections, related to a general part, radioactive facilities, nuclear facilities and advanced concepts. When the student finishes an area, an evaluation has to be done to prove the understanding of the lessons. We have included films of different activities as decontamination devices, radiation detectors..etc with the contents to make the explanations more understandable to the student. The course is complemented with a final review and exam that are not online to guarantee that the training is well finished. In addition the student has some practice related with different items explained during the training as the use of equipment in radiological protection tasks. This type of training is more flexitime and can be adapted to the necessities of each user, avoiding high costs and unnecessary displacements. (author)

  4. Analysis of the criteria used by the International Commission on Radiological Protection to justify the setting of numerical protection level values.

    Science.gov (United States)

    2006-01-01

    This report compiles the various numerical protection level values published by the International Commission on Radiological Protection (ICRP) since its 1990 Recommendations (Publication 60). Several terms are used to denominate the protection levels: individual dose limit, 'maximum' individual dose, dose constraint, exemption level, exclusion level, action level, or intervention level. The reasons provided by the Commission for selecting the associated numerical values is quoted as far as available. In some cases the rationale is not totally explicit in the original ICRP report concerned; in such cases the Task Group that prepared the present report have proposed their own interpretation. Originally, this report was prepared by a Task Group at CEPN, a French research and development center, in behalf of IRSN, a French public expert body engaged in radiological protection and nuclear safety. It is published here with kind permission by CEPN and IRSN.

  5. Radiological Control Manual

    Energy Technology Data Exchange (ETDEWEB)

    1993-04-01

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

  6. Radiological Control Manual

    International Nuclear Information System (INIS)

    1993-04-01

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

  7. Education and training in radiological protection in the Argentine region- IAEA, toward a long term commitment

    International Nuclear Information System (INIS)

    Terrado, C.; Arbor G, A.; Bozzo, R.; Larcher, A.; Menossi, C.; Sajaroff, P.

    2006-01-01

    The Argentine Republic has extensive antecedents in education and training in radiological protection. From the beginning of the nuclear activity in the country was given preponderance to the aspects related with the radiological protection and the personnel's training involved in the employment of ionizing radiations. At the present time these educational activities already overcome the 50 years, there being accumulated a rich and important experience in the matter. In the country the organisms that have assigned by law the responsibility of the regulation and the control of practice them with ionizing radiations are the Nuclear Regulatory Authority and the Ministry of Health and Atmosphere of the Nation. The first one has the mission of protecting people of the noxious effects of the ionizing radiations derived of nuclear activities, the second is in charge of the control of the equipment dedicated specifically to generate X-rays. This includes the responsibility of elaborating, to emit and to make complete the regulations, standards and other corresponding requirements, in particular - in the mark of the present work - regarding to establish demands and to promote education activities and training in radiological protection. The sure use of the benefits that offers the nuclear development in its diverse applications implies to overturn resources, experience and dedication for the personnel's training. In that sense the Argentina has committed recently to undertake the necessary actions to constitute a Regional Center of Education and Training for Latin America and the Caribbean, taking advantage of the important experience obtained in more of 25 years of imparting graduate degree courses in radiological protection and nuclear safety with inter regional and regional character. With that purpose a process of self evaluation has begun (self appraisal), following the limits settled down by the International Atomic Energy Agency in the document 'Education and

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2012-03-15

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

  9. Data acquisition, monitoring and diagnostic system for predictive control and protection of rotating components of IEAR-1 reactor by vibration analysis

    International Nuclear Information System (INIS)

    Serra, Reynaldo Cavalcanti; Tecco, Dorival Goncalves

    1996-01-01

    This work presents the vibration and temperature data acquisition, monitoring and diagnostic systems, recently installed in the primary circuit, secondary circuit and emergency generator of the IEA-R1 reactor at IPEN during the course of the first power elevation tests to 5MW. It incorporates a series of routines for equipment configuration, interactive automatic monitoring , data processing and documentation/storage without the exposure of operators in the radiological protection areas. (author)

  10. Conference on soldiers, civilians and environment protection against contaminations

    International Nuclear Information System (INIS)

    1994-01-01

    The military and civil aspects of radiation protection have been discussed. The special emphasize has been done on contamination monitoring of environment, soldier radiological protection during hypothetical warfare, radiological health hazard assessment, post Chernobyl contamination control of environment and food products in Poland, dose equivalent estimation and radiometric control equipment used in military and civil service

  11. Endoscopy versus radiology in post-procedural monitoring after peroral endoscopic myotomy (POEM).

    Science.gov (United States)

    Nast, Jan Friso; Berliner, Christoph; Rösch, Thomas; von Renteln, Daniel; Noder, Tania; Schachschal, Guido; Groth, Stefan; Ittrich, Harald; Kersten, Jan F; Adam, Gerhard; Werner, Yuki B

    2018-03-15

    The newly developed technique of peroral endoscopic myotomy (POEM) has been shown to be effective in several short- and mid-term studies. Limited information is available about the adequacy of immediate post-POEM monitoring tests. POEM was performed under general anesthesia in 228 patients (59.6% male, mean age 45.6 ± 15.5 years). Post-procedural checks comprised clinical and laboratory examination, and, during post-procedure days 1-5, endoscopy and-in the first 114 cases-radiologic examination using water-soluble contrast (1st group); the remaining patients underwent post-procedure controls without radiology (2nd group). Main outcome was value of endoscopic compared to radiologic control for recognition of early adverse events. In the first group, routine fluoroscopic contrast swallow suggested minor leakages at the mucosal entry site in two cases which was confirmed endoscopically in only one. Endoscopy revealed two minor entry site leakages and, in six additional cases, dislocated clips without leakage (overall 5.3%). All eight patients underwent reclipping and healed without clinical sequelae. In the 2nd group, endoscopy showed 5 clip dislocations (all reclipped) and one ischemic cardiac perforation in a patient with clinical deterioration on post-POEM day 1 who had to undergo surgery after confirmation of leakage by CT. Radiologic monitoring (contrast swallow) after POEM is not useful and can be omitted. Even routine endoscopic monitoring for detection and closure of minor defects of the mucosal entry site yields limited information with regards to final outcome; major complications are very rare and probably associated with clinical deterioration. Clinical Trials Gov Registration number of the main study: NCT01405417.

  12. Situation of the radiological protection in hospitals of the Department the Freedom - Peru

    International Nuclear Information System (INIS)

    Gonzales Rojas, Jose Mercedes

    2001-01-01

    The present work is first one in this gener that it is made in the Department of the Freedom - Peru. The intention was to do a diagnose of the radiation protection in the sanitary scope taking into account some main parameters like the level of qualification of the worker occupational exposed, the design of environment and the quality of the equipment in aspects like: collimation, filtration, kV and time. In this study were taken into account the Hospitals of the Department of the Freedom that belong to the Ministry of Health, Social Security and Private Centers of Health. From each hospital a random sample of the radiology worker was taken and it was applied a survey with related questions to radiological safety. The gather of the information became by means of direct survey. The obtained results are very useful, because besides to make a real diagnose of the radiation protection, evaluating the human and technical factor, they serve to improve the aspects of quality in radiological diagnosis, since the conclusions allow to establish if it is counted on a suitable level of radiation protection on the part of the workers and if the equipment fulfills the quality necessary to reach an efficient use of x-rays

  13. Radiation protection in the diagnostic radiology. General viewpoint including CT; Strahlenschutz in der diagnostischen Radiologie. Allgemeine Sichtweise einschliesslich CT

    Energy Technology Data Exchange (ETDEWEB)

    Kroepil, Patric [Universitaetsklinikum Duesseldorf (Germany). Inst. fuer Diagnostische und Interventionelle Radiologie

    2017-07-01

    Radiation protection in radiology has received public attention due to reports in the media on radiation hazards due to CT. The contribution covers the issues radiation protection in radiology, including the documentation of dose information, the responsibility of radiologists for their patients, new developments with respect to dose intensive CT and the changes due to the new radiation protection law.

  14. Developments in radiological protection of the environment and a commentary on its implications for new build of nuclear reactors

    International Nuclear Information System (INIS)

    Brownless, George; Lazo, Ted

    2008-01-01

    Full text: Development of radiological protection of non-human biota continues to be the focus of much interest and differing views amongst the radiological protection community. To nurture discussion of these developments, the Nuclear Energy Agency's Committee on Radiological Protection and Public Health is taking the lead in organising coverage of a spectrum of views on the topic at the International Conference on Radioecology and Radioactivity in the Environment (Bergen, 2008), with the aim of assisting the international community to construct a consensual, fit-for-purpose approach. To support discussion of these views, the session will also include scientific presentations and reports from implementers. This paper will report on these developments, based principally on the session at the Conference but also other activities in which NEA participates, to provide an up-to-date summary in this area including progress in developing understanding of how radiological protection of the environment will be implemented for the three exposure situations - planned, existing and emergency - set out in the new ICRP general recommendations. Furthermore, given the NEA's mandate across the civil nuclear energy field, the paper will give a commentary on how developments in radiological protection of the environment may interplay with new build of nuclear power plants. (author)

  15. Information on radiation hazard and on radiological protection in medical school in Italy

    International Nuclear Information System (INIS)

    Biagini, C.

    1993-01-01

    The state of teaching Radiation Protection in Medical School in Italy was considered. An historical approach was utilized, in order to define periods of time characterized by different conditions. Some data are collected by a concise enquiry on the information given during the course of Radiology in the second triennial cycle, and on some other teaching courses including information on radiation effects. The conclusion is that teaching times are exceedingly reduced, and the need of improving the diffusion of knowledge in the field is stressed. An official Act of the OECD and of European Community is expected, with the aim of emphasizing the importance of the information of doctors on Radiation Protection as a problem of public interest. A proposal is advanced of implementing the Teaching of Radiobiology in the second triennial cycle, changing the name of the course in 'Radiobiology and Radiological Protection'. 6 tabs

  16. Ethical and social implications of microdosing clinical trial (3). Radiological protection of human subjects in research

    International Nuclear Information System (INIS)

    Kurihara, Chieko

    2008-01-01

    Internal irradiation of human subjects in research is discussed. Radiological protection of human subjects in medical research in a framework of radiation protection is surveyed from a viewpoint of general life-ethics and research-ethics. A workshop 'On the internal irradiation of human subjects' to summarize special and systematic knowledge was organized by Research Center for Radiation Protection, National Institute of Radiological Sciences in the beginning of 2008. Activities of this workshop are introduced. Discussion covers also (1) Research ethics and radiation protection, (2) Fundamentals and applications of risk-benefit assessment, (3) Human subjects risk assessment in ICRP recommendation, (4) Mechanism of human subjects internal irradiation assessment, and (5) Present status and future prospects in Japan. (K.Y.)

  17. Radiation protection in interventional radiology; Strahlenschutz in der interventionellen Radiologie

    Energy Technology Data Exchange (ETDEWEB)

    Adamus, R.; Loose, R.; Galster, M. [Klinikum Nuernberg Nord, Institut fuer Diagnostische und Interventionelle Radiologie, Nuernberg (Germany); Wucherer, M. [Klinikum Nuernberg Nord, Institut fuer Medizinische Physik, Nuernberg (Germany); Uder, M. [Friedrich-Alexander-Universitaet Erlangen-Nuernberg, Institut fuer Radiologie, Erlangen (Germany)

    2016-03-15

    The application of ionizing radiation in medicine seems to be a safe procedure for patients as well as for occupational exposition to personnel. The developments in interventional radiology with fluoroscopy and dose-intensive interventions require intensified radiation protection. It is recommended that all available tools should be used for this purpose. Besides the options for instruments, x-ray protection at the intervention table must be intensively practiced with lead aprons and mounted lead glass. A special focus on eye protection to prevent cataracts is also recommended. The development of cataracts might no longer be deterministic, as confirmed by new data; therefore, the International Commission on Radiological Protection (ICRP) has lowered the threshold dose value for eyes from 150 mSv/year to 20 mSv/year. Measurements show that the new values can be achieved by applying all X-ray protection measures plus lead-containing eyeglasses. (orig.) [German] Die Anwendung ionisierender Strahlung in der Medizin scheint sowohl fuer Patienten als auch fuer beruflich exponierte Personen sicher zu sein. Die interventionellen Entwicklungen der letzten Jahre mit sehr durchleuchtungs- und dosisintensiven Eingriffen erfordern allerdings eine Intensivierung des Strahlenschutzes. Es empfiehlt sich, die zur Verfuegung stehenden Moeglichkeiten auszuschoepfen. Neben den Geraeteoptionen muss der Strahlenschutz am Eingriffstisch durch Bleilamellenaufstecker und montiertes Bleiglas intensiv betrieben werden. Besonderen Fokus muss auf den Schutz der Augen zur Kataraktvermeidung gelegt werden. Da dessen Ausbildung nach neuen Erkenntnissen moeglicherweise nicht mehr deterministisch zu sehen ist, hat die Internationale Strahlenschutzkommission (IRCP) den Grenzwert von 150 auf 20 Mikrosievert (mSv)/Jahr erniedrigt. Messungen belegen, dass unter Einhaltung aller Strahlenschutzmassnahmen plus Bleiglasbrille dieser einzuhalten ist. (orig.)

  18. Recent developments underlying the recommendations of the International Commission on Radiological Protection

    International Nuclear Information System (INIS)

    Dunster, H.J.

    1989-01-01

    A brief indication is given of the structure of the International Commission on Radiological Protection and of the main programme of work in hand at the start of 1989. This is followed by a discussion of some of the more important issues of policy under discussion during the preparation of the Commission's new recommendations on dose limits, units radiation quality, worker protection, risk assessment. (author)

  19. Radiological Environmental Protection for LCLS-II High Power Operation

    Science.gov (United States)

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

    2017-09-01

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

  20. The quality assurance in diagnostic radiology and their effect in the quality image and radiological protection of the patient

    International Nuclear Information System (INIS)

    Gaona, Enrique

    2002-01-01

    The quality assurance in diagnostic radiology in Mexico before 1997 was virtually nonexistent except in few academic institutions and hospitals. The purpose of this study was to carry out an exploratory survey of the issue of quality control parameters of general and fluoroscopy x-ray systems in the Mexican Republic and their effects in the quality image and radiological protection of the patient. A general result of the survey is that there is not significant difference in the observed frequencies among public and private radiology departments for α = 0.05, then the results are valid for both departments. 37% of x-ray systems belong to public radiology departments. In the radiology departments that didn't agree with the Mexican regulations in: light field to mach the x-ray field, light field intensity, kV, time and output. In those cases, we found a repeat rate of radiography studies >30% with non necessary dose to patient, low quality image and high operating costs of the radiology service. We found in x-ray fluoroscopy systems that 62% had a low quality image due to electronic noise in the television chain. In general the x-ray systems that didn't agree with Mexican regulations are 35% and they can affect in a way or other the quality image and the dose to patient

  1. Hanford radiological protection support services annual report for 1988

    International Nuclear Information System (INIS)

    Lyon, M.; Fix, J.J.; Kenoyer, J.L.; Leonowich, J.A.; Palmer, H.E.; Sula, M.J.

    1989-06-01

    The report documents the performance of certain radiological protection sitewide services during calendar year (CY) 1988 by Pacific Northwest Laboratory (PNL) in support of the US Department of Energy-Richland Operations Office (DOE-RL) and contractor activities on the Hanford Site. The routine program for each service is discussed along with any significant program changes and tasks, investigations, and studies performed in support of each program. Other related activities such as publications, presentations, and memberships on standard or industry committees are also listed. The programs covered provide services in the areas of (1) internal dosimetry, (2) in vivo measurements, (3) external dosimetry, (4) instrument calibration and evaluation, (5) calibration of radiation sources traceable to the National Institute of Standards and Technology (NIST) (formerly the National Bureau of Standards), and (6) radiological records. 23 refs., 15 figs., 15 tabs

  2. Program of training and technical expertise in radiation protection for personnel of medical radiology

    International Nuclear Information System (INIS)

    Oliveira, Sergio R. de

    2013-01-01

    This work aims to verify the actual conditions for the training of technicians in Radiology, in relation to the knowledge of radiation protection in the field of Medical Diagnostic Radiology. To evaluate the knowledge of professionals was prepared a questionnaire on the topic, having been answered by workers with varied experience. The questionnaire was divided into three parts, being the initial self-evaluation, followed by closed and open issues, all specific knowledge. With a total of 55 questionnaires answered, it was found that 85% of respondents consider themselves able to work in the area performing the function, but when questioned about the technical details regarding the exposure to ionizing radiation, it was found that only 15% of respondents had some knowledge about the subject. In relation to Radiological Protection, was found that little more than 10% of the respondents know about the subject. The results found in this survey outlined the creation of a technical specialization course in radiation protection, which is part of the permanent staff of course of the Polytechnical School of Health of FIOCRUZ, solving, partially, one of the problems pointed out today by health bodies, that is the lack of trained personnel

  3. Radiological protection and nuclear safety postgraduate course

    International Nuclear Information System (INIS)

    Segado, R.C.; Menossi, C.A.

    1998-01-01

    Full text: The first Radiation Protection and Nuclear Safety Postgraduate Course was held in 1977, when the former Radioprotection and Nuclear Safety Branch of the National Atomic Energy Commission decided implement that course for the qualification of its professionals. After then, in 1980, by agreement between the CNEA, the National University of Buenos Aires and the Ministry of Health and Social Welfare got its present academic qualification as a Post-Graduate Course. Since then, it was sponsored by the IAEA. This Organization annually grants fellowships to fifteen students from different countries. Up to now, twenty consecutive courses have been delivered and more than five hundredth graduated, more than half of them coming from abroad. The aim of the course is the qualification and training in Radiological Protection and Nuclear Safety of those professionals involved in the design, construction, operation and decommissioning of Nuclear and Radioactive Installation and their related regulatory issues. (author) [es

  4. Radiation protection in the intervenmtional radiology; Strahlenschutz in der interventionellen Radiologie

    Energy Technology Data Exchange (ETDEWEB)

    Becker, Benjamin V. [Institut fuer Radiobiologie der Bundeswehr, Muenchen (Germany); Ulm Univ. (Germany); Lissek, Friedrich; Waldeck, Stephan [Bundeswehrzentralkrankenhaus Koblenz (Germany). Klinik fuer Radiologie und Neuroradiologie

    2017-07-01

    Interventional radiology and neuroradiology covers a variety of diagnostic and therapeutic methods. A minimal invasive percutaneous access under imaging guidance is common for all these methods. The legal regulations for quality assurance are reviewed, technical possibilities for dose reduction and the importance of modern radiation protection procedures are discussed.

  5. Emergency monitoring strategy and radiation measurements. Working document of the NKS project emergency management and radiation monitoring in nuclear and radiological accidents (EMARAD)

    International Nuclear Information System (INIS)

    Lahtinen, J.

    2006-04-01

    This report is one of the deliverables of the NKS Project Emergency management and radiation monitoring in nuclear and radiological accidents (EMARAD) (20022005). The project and the overall results are briefly described in the NKS publication 'Emergency Management and Radiation Monitoring in Nuclear and Radiological Accidents. Summary Report on the NKS Project EMARAD' (NKS-137, April 2006). In a nuclear or radiological emergency, all radiation measurements must be performed efficiently and the results interpreted correctly in order to provide the decision-makers with adequate data needed in analysing the situation and carrying out countermeasures. Managing measurements in different situations in a proper way requires the existence of pre-prepared emergency monitoring strategies. Preparing a comprehensive yet versatile strategy is not an easy task to perform because there are lots of different factors that have to be taken into account. The primary objective of this study was to discuss the general problematics concerning emergency monitoring strategies and to describe a few important features of an efficient emergency monitoring system as well as factors affecting measurement activities in practise. Some information concerning the current situation in the Nordic countries has also been included. (au)

  6. Development and trends in radiological protection and the NEA programme in this field

    International Nuclear Information System (INIS)

    Ilari, O.; Wallauschek, E.

    1980-01-01

    The evolution of radiological protection problems and achievements during the more than twenty years of existence of the Nuclear Energy Agency, are reviewed in the light of the Agency's involvement and activities in this field. Some current problems of specific concern to public health aithorities in Member countries are discussed. The areas covered include the application of the ICRP optimisation principle to practical cases, the occupational exposure trends in the nuclear industry, the protection of workers and the public and the measurement and dosimetry problems associated with the front-end of the uranium fuel cycle, the radiological implications of dumping low-level radioactive wastes into the oceans, and the long-term detriment associated with the geological disposal of high-level radioactive wastes. (H.K.)

  7. Experience to the center of radiations hygiene and protection and Hygiene in the training as regards radiological protection

    International Nuclear Information System (INIS)

    Domenech Nieves, H.; Jove ased, L.A.

    1998-01-01

    The CPHR comes carrying out for several years a group activities among them regular courses for the basic formation as regards radiological protection the personnel with responsibilities as for the security the nuclear facilities. Presently work summary these experiences

  8. Radiation protection of patients in general diagnostic radiology in Lithuania

    International Nuclear Information System (INIS)

    Morkunas, G.; Ziliukas, J.

    2001-01-01

    The situation in control of exposure due to general diagnostic radiological examinations in Lithuania is described. Experience in creation of legal basis for radiation protection, results of measurements of patients' doses and quality control tests of x-ray units are given. The main problems encountered in implementation of international recommendations and requirements of European Medical Exposure Directive are discussed. (author)

  9. Mobilization suited for each radiological emergency

    International Nuclear Information System (INIS)

    Chambrette, V.

    2013-01-01

    This poster presents the role played by IRSN (French Institute for Radiation protection and Nuclear Safety) in case of radiological alert. This alert can be sent by the administration, a fire brigade, a nuclear operator or a remote monitor of radioactivity. In case of an emergency situation: IRSN provides radiological intervention and assistance on the site. In case of national crisis organization, IRSN will implement the emergency technical center and will send a mobile cell to the Operational Command Station of the Prefecture concerned. In both cases IRSN will be in charge of assessing the individuals' exposure and the impact on the environment

  10. Radiological Protection in Odontology: Analysis from the Faculty of Odontology at Rio de Janeiro concerning standards, licenses, controls and installations

    International Nuclear Information System (INIS)

    Padilha Filho, L.G.; Borgues, J.C.; Raymundo Junior, R.; Koch, H.A.

    1998-01-01

    This work shows the need and the importance training odontologists on radiological protection has. This is based on a proposal recently made by Technical Regulations: Trends for Radiological Protection in Medical and Odontological Radiodiagnosis from the Secretariat of Health Security from the Ministry of Health. These establish basic standards for radiation protection in medical and odontological areas

  11. Application of the ICRP approach for radiological protection of the marine environment in generic impact assessments

    Energy Technology Data Exchange (ETDEWEB)

    Kliaus, Viktoryia [Republican Scientific-Practical Centre of Hygiene, Laboratory of Radiation Safety, Akademicheskaya str. 8, 220012, Minsk (Belarus); Telleria, Diego M. [IAEA-Assessment and Management of Environmental Releases Unit, Wagramer Strasse 5 - PO Box 100, A-1400, Vienna (Austria); Cabianca, Tiberio [Centre for Radiation, Chemical and Environmental Hazards, PHE, Chilton, Didcot, Oxfordshire OX11 0RQ (United Kingdom)

    2014-07-01

    This paper presents a way to use the ICRP approach for protection of the environment in generic assessments of the radiological impact of radioactive releases to the marine environment. Generic assessments of radiological impact to the environment are needed in certain circumstances, for example, when input data are limited or when the likely radiological consequences are expected to be not significant. Under these circumstances the effort in performing the assessment must be commensurate with the potential radiological consequences. The generic assessment described in this paper is a simple tool which provides reasonable and cautious results and is applicable to multiple exposure scenarios associated with the assessment of the radiological impact of releases to the marine the environment. This generic assessment can be also used to provide preliminary results which, when compared to radiological criteria, may determine the need of further specific assessments. The ICRP based its approach to protect the environment in the definition of a set of reference animals and plants and the use of related radiological criteria, in the form of derived consideration reference levels. The paper discusses selection and exposure conditions of the reference animals and plants, methods to estimate their doses and the use of the radiological criteria, for the purpose of a generic assessment. The IAEA is elaborating applications of these generic impact assessments presented in the paper to be included in international guidance under development. (authors)

  12. Quality control of the interpretation monitors of digital radiological images

    International Nuclear Information System (INIS)

    Favero, Mariana S.; Goulart, Adriano Oliveira S.

    2016-01-01

    The performance monitors has great importance in image quality of digital radiographic systems. In environments without films, it became necessary to implement acceptance testing and quality control monitors used for interpretation of medical images. The monitors dedicated to radiodiagnostic should provide information that represent slight differences in x-ray attenuation or minor differences in some anatomical region of interest. This should also result in small differences in luminance of an image represented. Factors affecting the quality of medical imaging are contrast, noise, resolution, artifacts and distortions. Therefore, a monitor must have specific characteristics, making it possible for the observer to carry out an assessment that leads to better diagnosis. Based on the need to evaluate diagnostic monitors in various radiological applications, this paper presents a summary for implementation and standardization of tests that are recommended by the publication AAPM Report 03. (author)

  13. Individual radiological monitoring for exposed personnel of Nuclear Fuel Plant at Pitesti

    International Nuclear Information System (INIS)

    Ivana, T.; Epure, Gh.

    2010-01-01

    In the activity of nuclear fuel fabrication of CANDU type, based on natural and depleted uranium, individual radiological monitoring of the personnel exposed to ionizing radiation is very carefully approached. For Nuclear Fuel Plant (NFP) facility, where uranium appears in bulk and itemized form, measures for individual radiological monitoring are established by Radiological Safety Manual (MSR) in accordance with national and international legislation. All NFP employees are classified in either category A or category B of exposure to ionizing radiation. The classification is a function of type of activity and magnitude of exposure. All the exposed personnel are monitored for external doses (from gamma radiation) by measuring the equivalent dose H p (10) with monthly frequency. The system used for external individual dosimetric monitoring is based on the thermoluminescent dosimeter (TLD) of PANASONIC type UD813AS14. The NFP incorporates an in-house dosimetric laboratory notified by Romanian regulatory body CNCAN (National Commission for Control of Nuclear Activities). The workers handling nuclear materials are exposed to internal intake of uranium, mainly by inhalation. For internal doses monitoring is included part of exposed employees working directly with radioactive open sources (pulverulent or liquid nuclear materials), UO 2 sinterable powder, green pellets, sintered pellets, scrap and radioactive effluents. The estimation of internal exposure is made quarterly using the results from radioactive airborne monitors operating in the working places. The internal dose of each person exposed to open sources is calculated taking into account the rate of breathing, the time spent at the work place and the dose-activity coefficient (variable function of uranium absorption rate). The total effective individual dose is obtained by summing the external dose and internal dose (E=E ext +E int ). For conformity, the total effective individual dose (E) is compared with dose

  14. Report on a visit to Canada to discuss tritium instrumentation and radiological protection

    International Nuclear Information System (INIS)

    Gibson, J.A.B.

    1984-10-01

    A report is presented of a visit to Canada on behalf of the CEC DG II/Fusion between the 8th to 13th April 1984. Discussions were arranged by the Canadian Fusion-Fuels Technology Project near Toronto and covered all aspects of tritium technology but especially radiological protection. Visits included the CFFTP Centre, Pickering Nuclear Generating Section, Ontario Hydro's Head Office, Safety Services Department and Research Division, Scintrex Ltd (tritium instrument manufacturers) and the Atomic Energy of Canada (AECL) Chalk River Nuclear laboratories (CRNL). There are clearly many areas for the use of Canadian Technology in Europe, particularly with CRNL and Scintrex on the development of 3 H 2 / 3 H 2 O discriminating monitors. There is some doubt whether these development will be in time for applications at the JET laboratory and the JRC at ISPRA but this collaboration will be pursued. (author)

  15. Proceedings of the 15th nuclear safety research association symposium ICRP's 2005 Recommendations on radiological protection

    International Nuclear Information System (INIS)

    2003-02-01

    This is the document of the Symposium in the title, held in Tokyo, 2003. The document contains the greeting by chairperson (Toshiso Kosako, International Commission of Radiological Protection (ICRP) member, Tokyo University): lecture 1; for the title subject presented as ''ICRP's 2005 Recommendations on Radiological Protection'' with its slides entitled ''The Evolution of the System of Radiological Protection-The Justification for ICRP's 2005 Recommendations'' by L.-E. Holm (ICRP Vice-Chairman, Swedish Radiation Protection Authority): lecture 2; ''Protection of the Environment: from Ethics to Genetics''' with slides, ''Ionising Radiation and the Environment'', by R. J. Pentreath (ICRP member, The University of Reading, the United Kingdom (UK)): respectively followed by discussion with 3 Japanese panelists for each lecture: and chairperson's summary. The chair's greeting is about the rise of interest in environmental radiation protection, its background, and related trends in The Organization for Economic Co-operation and Development (OECD)/Nuclear Energy Agency (NEA) Committee on Radiation Protection and Public Health (CRPPH). L-EH's presentation involves sections of the background of the recommendations and protection of the environment, mentioning some of the proposed changes in the Commission's recommendations for its 2005 Recommendations. RJP's presentation involves sections of a philosophical platform, environmental management, relevance to radiation and its effects, points of reference and discussion where the impact of radionuclides and radiation in environment on various biological systems is mentioned in view for future. (R.T.)

  16. The Nea contribution to the evolution of the international system of radiological protection

    International Nuclear Information System (INIS)

    2009-01-01

    Since the International Commission on Radiological Protection (ICRP) initiated a dialogue in 1999 on the evolution of the system of radiological protection, the NEA Committee on Radiation Protection and Public Health (CRPPH) has actively engaged in providing the ICRP with input and views. The Committee's work on this subject has included eight expert group reports, seven international conferences, and four detailed review and comment assessments of draft ICRP recommendations. This report presents a chronological summary of the issues, views and concerns raised by the CRPPH as the ICRP issued various draft versions of its new recommendations (ICRP Publication 103, published in December 2007), and of the response by the ICRP as seen in its subsequent draft recommendations. The interest of this summary report is that it will not only assist readers in understanding the main themes and concepts of the new ICRP recommendations, but also why and how the changes from the previous ICRP Publication 60 recommendations came about. (author)

  17. RadSTraM: Radiological Source Tracking and Monitoring, Phase II Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Warren, Tracy A [ORNL; Walker, Randy M [ORNL; Hill, David E [ORNL; Gross, Ian G [ORNL; Smith, Cyrus M [ORNL; Abercrombie, Robert K [ORNL

    2008-12-01

    This report focuses on the technical information gained from the Radiological Source Tracking and Monitoring (RadSTraM) Phase II investigation and its implications. The intent of the RadSTraM project was to determine the feasibility of tracking radioactive materials in commerce, particularly International Atomic Energy Agency (IAEA) Category 3 and 4 materials. Specifically, Phase II of the project addressed tracking radiological medical isotopes in commerce. These categories of materials are susceptible to loss or theft but the problem is not being addressed by other agencies.

  18. RadSTraM: Radiological Source Tracking and Monitoring, Phase II Final Report

    International Nuclear Information System (INIS)

    Warren, Tracy A.; Walker, Randy M.; Hill, David E.; Gross, Ian G.; Smith, Cyrus M.; Abercrombie, Robert K.

    2008-01-01

    This report focuses on the technical information gained from the Radiological Source Tracking and Monitoring (RadSTraM) Phase II investigation and its implications. The intent of the RadSTraM project was to determine the feasibility of tracking radioactive materials in commerce, particularly International Atomic Energy Agency (IAEA) Category 3 and 4 materials. Specifically, Phase II of the project addressed tracking radiological medical isotopes in commerce. These categories of materials are susceptible to loss or theft but the problem is not being addressed by other agencies

  19. Application of the diagnostic radiological index of protection to protective garments

    Energy Technology Data Exchange (ETDEWEB)

    Pasciak, Alexander S. [Department of Radiology, The University of Tennessee Medical Center at Knoxville, Knoxville, Tennessee 37922 (United States); Jones, A. Kyle, E-mail: kyle.jones@mdanderson.org [Department of Imaging Physics, The University of Texas MD Anderson Cancer Center, Houston, Texas 77030 (United States); Wagner, Louis K. [Department of Diagnostic and Interventional Imaging, The University of Texas Medical School at Houston, Houston, Texas 77030 (United States)

    2015-02-15

    Purpose: Previously, the diagnostic radiological index of protection (DRIP) was proposed as a metric for quantifying the protective value of radioprotective garments. The DRIP is a weighted sum of the percent transmissions of different radiation beams through a garment. Ideally, the beams would represent the anticipated stray radiation encountered during clinical use. However, it is impractical to expect a medical physicist to possess the equipment necessary to accurately measure transmission of scattered radiation. Therefore, as a proof of concept, the authors tested a method that applied the DRIP to clinical practice. Methods: Primary beam qualities used in interventional cardiology and radiology were observed and catalogued. Based on the observed range of beam qualities, five representative clinical primary beam qualities, specified by kV and added filtration, were selected for this evaluation. Monte Carlo simulations were performed using these primary beams as source definitions to generate scattered spectra from the clinical primary beams. Using numerical optimization, ideal scatter mimicking primary beams, specified by kV and added aluminum filtration, were matched to the scattered spectra according to half- and quarter-value layers and spectral shape. To within reasonable approximation, these theoretical scatter-mimicking primary beams were reproduced experimentally in laboratory x ray beams and used to measure transmission through pure lead and protective garments. For this proof of concept, the DRIP for pure lead and the garments was calculated by assigning equal weighting to percent transmission measurements for each of the five beams. Finally, the areal density of lead and garments was measured for consideration alongside the DRIP to assess the protective value of each material for a given weight. Results: The authors identified ideal scatter mimicking primary beams that matched scattered spectra to within 0.01 mm for half- and quarter-value layers in

  20. Application of the diagnostic radiological index of protection to protective garments.

    Science.gov (United States)

    Pasciak, Alexander S; Jones, A Kyle; Wagner, Louis K

    2015-02-01

    Previously, the diagnostic radiological index of protection (DRIP) was proposed as a metric for quantifying the protective value of radioprotective garments. The DRIP is a weighted sum of the percent transmissions of different radiation beams through a garment. Ideally, the beams would represent the anticipated stray radiation encountered during clinical use. However, it is impractical to expect a medical physicist to possess the equipment necessary to accurately measure transmission of scattered radiation. Therefore, as a proof of concept, the authors tested a method that applied the DRIP to clinical practice. Primary beam qualities used in interventional cardiology and radiology were observed and catalogued. Based on the observed range of beam qualities, five representative clinical primary beam qualities, specified by kV and added filtration, were selected for this evaluation. Monte Carlo simulations were performed using these primary beams as source definitions to generate scattered spectra from the clinical primary beams. Using numerical optimization, ideal scatter mimicking primary beams, specified by kV and added aluminum filtration, were matched to the scattered spectra according to half- and quarter-value layers and spectral shape. To within reasonable approximation, these theoretical scatter-mimicking primary beams were reproduced experimentally in laboratory x ray beams and used to measure transmission through pure lead and protective garments. For this proof of concept, the DRIP for pure lead and the garments was calculated by assigning equal weighting to percent transmission measurements for each of the five beams. Finally, the areal density of lead and garments was measured for consideration alongside the DRIP to assess the protective value of each material for a given weight. The authors identified ideal scatter mimicking primary beams that matched scattered spectra to within 0.01 mm for half- and quarter-value layers in copper and within 5% for the