Radiological safety by design

International Nuclear Information System (INIS)

Gundaker, W.E.

1977-01-01

Under the Radiation Control for Health and Safety Act enacted by the U.S. Congress in 1968, the Food and Drug Administration's Bureau of Radiological Health may prescribe performance standards for products that emit radiation. A description is given of the development of these standards and outlines the administrative procedures by which they are enforced. (author)

Radiological safety in petroleum industry. Towards prevention culture

International Nuclear Information System (INIS)

Truppa, Walter A.

2007-01-01

Within the frame of regulatory control of industrial applications the audit of sealed and open radioactive sources in oil uses is one of the most relevant. The handling of radioactive sources, the requirement of procedures and training are just a few examples among all those that make up the radiological safety culture. A number of requirements divided into three main groups: operational safety at the storage area of radioactive sources, during transportation and during the applications (Cementation, well logging and use of radiotracers) are highlighted. Due to the great number of aspects that have to be taken in account as well as the interrelation of all control processes it is highly recommended that aspects of safety culture and quality should be considered and improvements regarding prevention, should be introduced so as to correct deviations that could arise in order to avoid radiological risk situations, emphasizing risk perception situations, attitude training, implementation of audit and level of safety in the facilities and control of duties, involving radiological material handling, described in the present work. (author) [es

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

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.

Radiological safety and risk assessment

International Nuclear Information System (INIS)

Hunter, P.H.; Barg, D.C.; Baird, R.D.; Card, D.H.; de Souza, F.; Elder, J.; Felthauser, K.; Jensen, C.; Winkler, V.

1982-02-01

A brief radiological safety and risk assessment of a nuclear power generation center with an adjacent on-site waste disposal facility at a specific site in the State of Utah is presented. The assessment was conducted to assist in determining the feasibility and practicality of developing a nuclear energy center (NEC) in Utah consisting of nine 1250 MWe nuclear pressurized water reactor (PWR) electrical generating units arranged in 3 clusters of 3 units each known as triads. The site selected for this conceptual study is in the Horse Bench area about 15 miles directly south of the town of Green River, Utah. The radiological issues included direct radiation exposures to on-site workers and the off-site population, release of radioactive material, and effects of these releases for both normal operations and accidental occurrences. The basic finding of this study is that the concept of an NEC in the Green River area, specifically at the Horse Bench site, is radiologically feasible

Implementation of the new regulation on radiological safety in Peru

International Nuclear Information System (INIS)

Medina Gironzini, E.

1997-01-01

Since its creation in 1975, the Peruvian Institute of Nuclear Energy (IPEN) has enacted three regulations of national importance on the norms of protection against ionizing radiation. The first regulation, which is called regulation of radiological protection (1980) approved by a resolution of IPEN, is the result of the work of a committee constituted by IPEN and the Ministry of Health. Its implementation caused some problems as result of which, in 1989, a new regulation on radiological protection was enacted through a supreme decree. Taking into account the new recommendation of the International Commission on Radiological Protection and the International Basic Safety Standard for Protection against Ionizing Radiation and for the Safety of Radiation Sources, approved in May 1997, the regulation of radiological safety also considers evolving aspects in the Project ARCAL XVII/IAEA. This regulation includes various topics such as exclusions, requirements of protection (medical exposure, occupational exposure, public exposure, chronic exposure), requirements of source safety, interventions and emergencies, control of sources and practices (exemptions, authorizations, inspections) etc. The implementation of this regulation at the national level falls to IPEN, the unique authority commissioned to control nuclear installations, radioactivity and x ray facilities in medicine, industry and research

Interim radiological safety standards and evaluation procedures for subseabed high-level waste disposal

International Nuclear Information System (INIS)

Klett, R.D.

1997-06-01

The Seabed Disposal Project (SDP) was evaluating the technical feasibility of high-level nuclear waste disposal in deep ocean sediments. Working standards were needed for risk assessments, evaluation of alternative designs, sensitivity studies, and conceptual design guidelines. This report completes a three part program to develop radiological standards for the feasibility phase of the SDP. The characteristics of subseabed disposal and how they affect the selection of standards are discussed. General radiological protection standards are reviewed, along with some new methods, and a systematic approach to developing standards is presented. The selected interim radiological standards for the SDP and the reasons for their selection are given. These standards have no legal or regulatory status and will be replaced or modified by regulatory agencies if subseabed disposal is implemented. 56 refs., 29 figs., 15 tabs

Radiological evaluation of dysphagia

Energy Technology Data Exchange (ETDEWEB)

Ott, D.J.; Gelfand, D.W.; Wu, W.C.; Chen, Y.M.

1986-11-21

Dysphagia is a common complaint in patients presenting for radiological or endoscopic examination of the esophagus and is usually due to functional or structural abnormalities of the esophageal body or esophagogastric region. The authors review the radiological evaluation of the esophagus and esophagogastric region in patients with esophageal dysphagia and discuss the roentgenographic techniques used, radiological efficacy for common structural disorders, and evaluation of esophageal motor function. Comparison is made with endoscopy in assessing dysphagia, with the conclusion that the radiological examination be used initially in patients with this complaint.

Radiological evaluation of dysphagia

International Nuclear Information System (INIS)

Ott, D.J.; Gelfand, D.W.; Wu, W.C.; Chen, Y.M.

1986-01-01

Dysphagia is a common complaint in patients presenting for radiological or endoscopic examination of the esophagus and is usually due to functional or structural abnormalities of the esophageal body or esophagogastric region. The authors review the radiological evaluation of the esophagus and esophagogastric region in patients with esophageal dysphagia and discuss the roentgenographic techniques used, radiological efficacy for common structural disorders, and evaluation of esophageal motor function. Comparison is made with endoscopy in assessing dysphagia, with the conclusion that the radiological examination be used initially in patients with this complaint

Radiological protection. Textbook for radiographers and reference book for radiological safety officers

International Nuclear Information System (INIS)

Stieve, F.E.; Stargardt, A.; Stender, H.S.

1996-01-01

The textbook is primarily intended for radiologic staff and radiologic safety officers and gives information on the current regulatory provisions of the German X-ray Ordinance, applications of X-rays, quality assurance, organisational aspects of film processing and quality requirements of X-rays. An annex lists the guidelines of the Bundesaerztekammer (German National Chamber of Physicians) relating to quality assurance aspects, and further useful information on commercially available film-screen systems, the various associations of physicians in Germany, and requirements and performance of radiation surveys. (vhe) [de

Radiological safety and control

International Nuclear Information System (INIS)

Kim, Jang Hee; Kim, Ki Sub

1995-01-01

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

Evaluation of radiological safety conditions of panoramic portable irradiators of industrial radiography used in Brazil

International Nuclear Information System (INIS)

Aquino, Josilto Oliveira de

2003-08-01

In Brazil, the applications of ionizing radiation in industrial area are performed in about 900 installations, in which around 3000 radioactive sources are handled. Industrial radiography represents 14 % of this total, with 217 X rays equipment and 287 gamma radiography apparatus, according to a survey conducted in the present work. From these gamma apparatus, 90 % employ 192 Ir sources, followed by 60 Co and 75 Se, with 5 % each. The great majority of the 192 Ir apparatus have been in continuous usage in Brazil for more than 20 years, which means that they are old equipment. The totality of the 11 models of 192 Ir apparatus used in Brazil is imported from abroad. Those apparatus are portable, and almost all operate according to category II, i.e., the source assembly is mechanically projected out of the container. This last characteristic, besides the fact that the apparatus are already old-fashioned and worn-out, raises concerns about their radiological safety. The main objective of this work was to develop a specific methodology for inspection, testing and assessment of the radiological safety devices and state of maintenance of the 192 Ir apparatus. The idea is to prevent accidents, as physical failures can lead to overexposure of working staffs. In order to accomplish this, almost a hundred 192 Ir apparatus, from the 11 models used in Brazil, were studied. According to our results, almost 20 % of the 97 apparatus evaluated presented some kind of unsafe condition for proper operation, like poor state of maintenance and faults at the lock that retains the source at the secure position. From the 11 imported models of 192 Ir apparatus in use in Brazil, six models were already manufactured incorporating the safety devices specified by the first edition of the Standard ISO 3999, edited in 1977. However, five models do not comply even with this first edition of the Standard ISO 3999. Thus, they lack some important and basic safety devices. None of the 11 models comply

Evaluation of radiological dispersion/consequence codes supporting DOE nuclear facility SARs

International Nuclear Information System (INIS)

O'Kula, K.R.; Paik, I.K.; Chung, D.Y.

1996-01-01

Since the early 1990s, the authorization basis documentation of many U.S. Department of Energy (DOE) nuclear facilities has been upgraded to comply with DOE orders and standards. In this process, many safety analyses have been revised. Unfortunately, there has been nonuniform application of software, and the most appropriate computer and engineering methodologies often are not applied. A DOE Accident Phenomenology and Consequence (APAC) Methodology Evaluation Program was originated at the request of DOE Defense Programs to evaluate the safety analysis methodologies used in nuclear facility authorization basis documentation and to define future cost-effective support and development initiatives. Six areas, including source term development (fire, spills, and explosion analysis), in-facility transport, and dispersion/ consequence analysis (chemical and radiological) are contained in the APAC program. The evaluation process, codes considered, key results, and recommendations for future model and software development of the Radiological Dispersion/Consequence Working Group are summarized in this paper

Fuel Receiving and Storage Station. Nuclear Regulatory Commission's safety evaluation report

International Nuclear Information System (INIS)

1976-01-01

The safety evaluation report covers design of structures, components, equipment, and systems; nuclear criticality safety; radiological safety; accident analysis; conduct of operations; quality assurance; common defense and security; financial qualifications; financial protection and indemnity requirements; and technical specifications

Radiological anatomy - evaluation of integrative education in radiology.

Science.gov (United States)

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

2013-09-01

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

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

International Nuclear Information System (INIS)

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

1995-01-01

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

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

Radiological safety research for nuclear excavation projects - Interoceanic canal studies

Energy Technology Data Exchange (ETDEWEB)

Klement, Jr, A W [U.S. Atomic Energy Commission, Las Vegas, NV (United States)

1969-07-01

The general radiological problems encountered in nuclear cratering and nuclear excavation projects are discussed. Procedures for assessing radiological problems in such projects are outlined. Included in the discussions are source term, meteorology, fallout prediction and ecological factors. Continuing research requirements as well as pre- and post-excavation studies are important considerations. The procedures followed in the current interoceanic canal feasibility studies provide examples of radiological safety problems, current solutions and needed research. (author)

Radiological safety research for nuclear excavation projects - Interoceanic canal studies

International Nuclear Information System (INIS)

Klement, A.W. Jr.

1969-01-01

The general radiological problems encountered in nuclear cratering and nuclear excavation projects are discussed. Procedures for assessing radiological problems in such projects are outlined. Included in the discussions are source term, meteorology, fallout prediction and ecological factors. Continuing research requirements as well as pre- and post-excavation studies are important considerations. The procedures followed in the current interoceanic canal feasibility studies provide examples of radiological safety problems, current solutions and needed research. (author)

'On line' course for the periodical training in radiological safety of the workers of a radioactive facility

International Nuclear Information System (INIS)

Amador B, Z.H.; Ayra P, F.E.; Torres B, M.B.

2006-01-01

The results of an 'on line' course for the periodical training in radiological safety of the workers of a radioactive installation are presented. The course is developed for own specialists. The following topics are approached: the state of the art of the studies on the biological effects of the ionizing radiations, the new national regulations, the analysis of the behavior of the occupational exposure, of the obtained experiences of the radiological events, of the results of the radiological surveillance of the work positions, of the detected violations and of the behavior of the outstanding systems and the optimization. The study of the acquired experiences in the packing and the transportation of radioactive materials and the administration of the radioactive waste are included. The study of the course by one month is organized and then two convocations of theoretical exams are executed and one for the evaluation practices of the instructions and procedures. To evaluate the effectiveness of the course a survey it is applied and the later behavior of indicators of the radiological safety of the plant is analyzed. The results that are obtained show a positive balance. (Author)

Report on nuclear and radiological safety in 1995

International Nuclear Information System (INIS)

Lovincic, D.

1996-07-01

The Slovenian Nuclear Safety Administration (SNSA) in cooperation with the Health Inspectorate of the Republic of Slovenia and the Administration for Rescue and Disaster Relief (URSZR) has prepared a Report on Nuclear and Radiological Safety in the Republic of Slovenia for 1995. The report is presenting: the activities of the SNSA; the operation of nuclear facilities; monitoring of radioactivity; control of ionizing radiation and nuclear electricity generation.

Effective radiological safety program for electron linear accelerators

International Nuclear Information System (INIS)

Swanson, W.P.

1980-10-01

An outline is presented of some of the main elements of an electron accelerator radiological safety program. The discussion includes types of accelerator facilities, types of radiations to be anticipated, activity induced in components, air and water, and production of toxic gases. Concepts of radiation shielding design are briefly discussed and organizational aspects are considered as an integral part of the overall safety program

Radiological Safety Officer (RSO): role and responsibilities

International Nuclear Information System (INIS)

Joshi, M.L.; Yadav, J.S.; Gopalakrishnan, R.K.; Ansari, I.A.

2017-01-01

The fundamental safety objective in a radiological facility (RF) is to protect people and the environment from harmful effects of ionising radiation. The radiation risks to people and the environment that may arise from the use of radiation and radioactive material must be assessed and must be controlled by means of the application of the relevant standards of safety. Thus, all facilities handling radioactive material must have experts, who are responsible for assisting the plant management in radiation protection programme

International Cooperation of the Republic of Croatia in the Field of Radiological and Nuclear Safety

International Nuclear Information System (INIS)

Novosel, N.

2011-01-01

International cooperation of the Republic of Croatia in the field of radiological and nuclear safety can be divided in two parts - political part, for which the Ministry of Foreign Affairs and European Integration is responsible, and technical part, for which the State Office for Radiological and Nuclear Safety is responsible. According to the Radiological and Nuclear Safety Act (OG 28/10) the State Office for Radiological and Nuclear Safety: ''coordinates technical cooperation with the International Atomic Energy Agency for all participants from the Republic of Croatia''; ''fulfils the obligations which the Republic of Croatia has assumed through international conventions and bilateral agreements concerning protection against ionising radiation, nuclear safety and the application of protective measures aimed at the non-proliferation of nuclear weapons'' and ''cooperates with international and domestic organisations and associations in the area of protection against ionising radiation and nuclear safety, and appoints its own expert representatives to take part in the work of such organisations and associations or to monitor their work''. In this paper various aspects of the technical cooperation with the International Atomic Energy Agency, as well as international conventions and bilateral agreements in the field of radiological and nuclear safety, are presented. Also, cooperation with other international organizations and associations in the area of radiological and nuclear safety, such as Nuclear Suppliers Group, the Zangger Committee, the Wassenaar Arrangement, Comprehensive Nuclear-Test-Ban Treaty Organization, Euratom and certain civil expert groups of NATO, is described. (author)

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)

Effect of changes in technical parameters in radiological safety

International Nuclear Information System (INIS)

Avendano, Ge; Fernandez, C

2007-01-01

This work analyzes the generation of secondary radiation that affects the professionals of health during interventional X ray procedures in first level hospitals. The research objectives were, on the one hand, to quantify the amount of radiation and to compare it with norms in force with respect to magnitudes, and on the other hand to evaluate the elements of protection used. The measurements will help to improve the radiological safety, to assess the eventuality of risks and, in the last term, to the possibility of norms modification for the improvement of the protection, especially that of the personnel who daily make a certain amount of interventional procedures guided by radiation, like angiographic cine applications, using continuous or pulsed fluoroscopy. The motivation of the study is in the suspicion that present interventionism is made with a false sensation of safety, based only in the use of lead apron and protection elements incorporated in the equipment by the manufacturer, nevertheless not always the health personnel are conscious that an excessive proximity with the tube and the patient body becomes a risky source of secondary and scattered radiation. The obtained results allow us to demonstrate the existence of conditions of risk, even possible iatrogenic events, in particular when the procedures imply the use of certain techniques of radiographic exploration, thus reaching the conclusion that the radiographic methodology must be changed in order to rationalize so much?. In order to achieve this we propose modifications to the present norms and legislation referred to the radiological safety in Chile

Nuclear and radiological safety in Slovenia in 1995

International Nuclear Information System (INIS)

Lovincic, D.

1996-01-01

The Slovenian Nuclear Safety Administration (SNSA) in cooperation with the Health Inspectorate of the Republic of Slovenia and the Administration for Rescue and Disaster Relief (URSZR) has prepared a Report on Nuclear and Radiological Safety in the Republic of Slovenia for 1995. The report is presenting: the activities of the SNSA; the operation of nuclear facilities; monitoring of radioactivity; control of ionizing radiation and nuclear electricity generation. (author)

Development of an auditable safety analysis in support of a radiological facility classification

International Nuclear Information System (INIS)

Kinney, M.D.; Young, B.

1995-01-01

In recent years, U.S. Department of Energy (DOE) facilities commonly have been classified as reactor, non-reactor nuclear, or nuclear facilities. Safety analysis documentation was prepared for these facilities, with few exceptions, using the requirements in either DOE Order 5481.1B, Safety Analysis and Review System; or DOE Order 5480.23, Nuclear Safety Analysis Reports. Traditionally, this has been accomplished by development of an extensive Safety Analysis Report (SAR), which identifies hazards, assesses risks of facility operation, describes and analyzes adequacy of measures taken to control hazards, and evaluates potential accidents and their associated risks. This process is complicated by analysis of secondary hazards and adequacy of backup (redundant) systems. The traditional SAR process is advantageous for DOE facilities with appreciable hazards or operational risks. SAR preparation for a low-risk facility or process can be cost-prohibitive and quite challenging because conventional safety analysis protocols may not readily be applied to a low-risk facility. The DOE Office of Environmental Restoration and Waste Management recognized this potential disadvantage and issued an EM limited technical standard, No. 5502-94, Hazard Baseline Documentation. This standard can be used for developing documentation for a facility classified as radiological, including preparation of an auditable (defensible) safety analysis. In support of the radiological facility classification process, the Uranium Mill Tailings Remedial Action (UMTRA) Project has developed an auditable safety analysis document based upon the postulation criteria and hazards analysis techniques defined in DOE Order 5480.23

Preliminary report of radiological safety to hydrology 1993 campaign

International Nuclear Information System (INIS)

Badano, A.; Suarez Antola, R.; Dellepere, A.; Barreiro, M.

1993-01-01

This report has been prepared based on the interaction between project managers and division radiological Protection and Nuclear Safety. In seeking to establish a basis for approval from the point of view of radiation safety practices . The idea for the audit has been provided at all times because the interest was the exchange of ideas and the use of common sense to improve the safety of radioactive substances, security of operators and public safety and environment.The above shows that in the planned radiation safety condition described in this report,the practice can be carried out according to the criteria of safety accepted .

Development of a management system of radiological safety with application to hospitals

International Nuclear Information System (INIS)

Velazquez M, J.D.; Rivera M, T.; Santos R, J.R.

2008-01-01

The medicine is the area that more it has benefited with the implementation of the radiation. However, a great number of incidents/accidents they have happened in hospitals in recent years. The above-mentioned stands out the necessity to improve the acting of the radiological safety management systems in Hospitals. This work presents a Management System of Radiological Safety (SGSR). The SGSR has as fundamental objective the one of maintaining the radiological risks inside acceptable levels. The SGSR is generic and it can be applied in the nuclear medicine, radiodiagnostic, radiotherapy, and in other areas of the health sector where it is required to prevent accidents or incidents that affect the health or the well-being of the worker or user. Also it was diagnosed a Specialties Hospital of the Mexico City using some characteristics of the SGSR. The obtained results show that the SGSR can contribute significantly in the improvement of the quality of the service in the attention to the patients and in the radiological safety. (Author)

Implementation of a radiological safety management system in a hospital of Mexico City

International Nuclear Information System (INIS)

Martinez V, D.; Rivera M, T.; Velez D, V.

2007-01-01

Full text: The reflection of this work is based in some radiological accidents that its have happened in some hospital centers or of research. The over exposure of some people is due to the pursuit of the procedures, the lack of quality assurance of the equipment or the inappropriate actions of the technicians. In Mexico one has seen in several hospitals the lack of existence of a Quality Assurance Program to prevent the accidents, the execution of the same ones and those good practices and the lack of Safety Culture makes that the hospital radiological safety it is faulty. The objective of the present work is the implementation of a radiological safety management in a hospital of Mexico City. (Author)

Barriers to Safety Event Reporting in an Academic Radiology Department: Authority Gradients and Other Human Factors.

Science.gov (United States)

Siewert, Bettina; Swedeen, Suzanne; Brook, Olga R; Eisenberg, Ronald L; Hochman, Mary

2018-05-15

Purpose To investigate barriers to reporting safety concerns in an academic radiology department and to evaluate the role of human factors, including authority gradients, as potential barriers to safety concern reporting. Materials and Methods In this institutional review board-approved, HIPAA-compliant retrospective study, an online questionnaire link was emailed four times to all radiology department staff members (n = 648) at a tertiary care institution. Survey questions included frequency of speaking up about safety concerns, perceived barriers to speaking up, and the annual number of safety concerns that respondents were unsuccessful in reporting. Respondents' sex, role in the department, and length of employment were recorded. Statistical analysis was performed with the Fisher exact test. Results The survey was completed by 363 of the 648 employees (56%). Of those 363 employees, 182 (50%) reported always speaking up about safety concerns, 134 (37%) reported speaking up most of the time, 36 (10%) reported speaking up sometimes, seven (2%) reported rarely speaking up, and four (1%) reported never speaking up. Thus, 50% of employees spoke up about safety concerns less than 100% of the time. The most frequently reported barriers to speaking up included high reporting threshold (69%), reluctance to challenge someone in authority (67%), fear of disrespect (53%), and lack of listening (52%). Conclusion Of employees in a large academic radiology department, 50% do not attain 100% reporting of safety events. The most common human barriers to speaking up are high reporting threshold, reluctance to challenge authority, fear of disrespect, and lack of listening, which suggests that existing authority gradients interfere with full reporting of safety concerns. © RSNA, 2018.

Evaluation of the radiological safety of the working area in the installation of experimental fuel elements in 2010

International Nuclear Information System (INIS)

Nudia Barenzani

2011-01-01

Evaluations of radiological safety in working areas in IEBE during 2010 have been conducted. The purpose of this evaluation was to determine that the working area in IEBE is safe for workers to conducting research and development of nuclear fuel. The evaluation is done by analyzing the results of routine monitoring in the laboratory of IEBE during the year 2010, such as gamma exposure, alpha radioactivity in air and surface contamination. The result is the highest gamma exposure (3.213 ± 0.121) µSv/h at the desk-work-B in HR-05, alpha Radioactivity in air at (4.980 ± 0.444) Bq/m 3 and the average surface contamination (0.090 ± 0.008) Bq/cm 2 . The result is still above Permissible Maximum Concentration (MPC) and in the Lower Dose Limit Value established by the Regulatory Body. So it can be concluded that IEBE laboratory is safe for workers in conducting research and development nuclear fuel. (author)

Expanding the scope of practice for radiology managers: radiation safety duties.

Science.gov (United States)

Orders, Amy B; Wright, Donna

2003-01-01

In addition to financial responsibilities and patient care duties, many medical facilities also expect radiology department managers to wear "safety" hats and complete fundamental quality control/quality assurance, conduct routine safety surveillance in the department, and to meet regulatory demands in the workplace. All managers influence continuous quality improvement initiatives, from effective utilization of resource and staffing allocations, to efficacy of patient scheduling tactics. It is critically important to understand continuous quality improvement (CQI) and its relationship with the radiology manager, specifically quality assurance/quality control in routine work, as these are the fundamentals of institutional safety, including radiation safety. When an institution applies for a registration for radiation-producing devices or a license for the use of radioactive materials, the permit granting body has specific requirements, policies and procedures that must be satisfied in order to be granted a permit and to maintain it continuously. In the 32 U.S. Agreement states, which are states that have radiation safety programs equivalent to the Nuclear Regulatory Commission programs, individual facilities apply for permits through the local governing body of radiation protection. Other states are directly licensed by the Nuclear Regulatory Commission and associated regulatory entities. These regulatory agencies grant permits, set conditions for use in accordance with state and federal laws, monitor and enforce radiation safety activities, and audit facilities for compliance with their regulations. Every radiology department and associated areas of radiation use are subject to inspection and enforcement policies in order to ensure safety of equipment and personnel. In today's business practice, department managers or chief technologists may actively participate in the duties associated with institutional radiation safety, especially in smaller institutions, while

Ensuring the safety of surgical teams when managing casualties of a radiological dirty bomb.

Science.gov (United States)

Williams, Geraint; O'Malley, Michael; Nocera, Antony

2010-09-01

The capacity for surgical teams to ensure their own safety when dealing with the consequences caused by the detonation of a radiological dirty bomb is primarily determined by prior knowledge, familiarity and training for this type of event. This review article defines the associated radiological terminology with an emphasis on the personal safety of surgical team members in respect to the principles of radiological protection. The article also describes a technique for use of hand held radiation monitors and will discuss the identification and management of radiologically contaminated patients who may pose a significant danger to the surgical team. 2010 Elsevier Ltd. All rights reserved.

Radiologic safety program for ionizing radiation facilities in Parana, Brazil

International Nuclear Information System (INIS)

Schmidt, M.F.S.; Tilly Junior, J.G.

1997-01-01

A radiologic safety program for inspection, licensing and control of the use of ionizing radiation in medical, industrial and research facilities in Parana, Brazil is presented. The program includes stages such as: 1- division into implementation phases considering the activity development for each area; 2-use of the existing structure to implement and to improve services. The development of the program will permit to evaluate the improvement reached and to correct operational strategic. As a result, a quality enhancement at the services performed, a reduction for radiation dose exposure and a faster response for emergency situations will be expected

Radiological safety assessment of transporting radioactive waste to the Gyeongju disposal facility in Korea

Energy Technology Data Exchange (ETDEWEB)

Jeong, Jong Tae; Baik, Min Hoon; Kang, Mun Ja; Ahn, Hong Joo; Hwang, Doo Seong; Hong, Dae Seok; Jeong, Yong Hwan; Kim, Kyung Su [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2016-12-15

A radiological safety assessment study was performed for the transportation of low level radioactive wastes which are temporarily stored in Korea Atomic Energy Research Institute (KAERI), Daejeon, Korea. We considered two kinds of wastes: (1) operation wastes generated from the routine operation of facilities; and (2) decommissioning wastes generated from the decommissioning of a research reactor in KAERI. The important part of the radiological safety assessment is related to the exposure dose assessment for the incident-free (normal) transportation of wastes, i.e., the radiation exposure of transport personnel, radiation workers for loading and unloading of radioactive waste drums, and the general public. The effective doses were estimated based on the detailed information on the transportation plan and on the radiological characteristics of waste packages. We also estimated radiological risks and the effective doses for the general public resulting from accidents such as an impact and a fire caused by the impact during the transportation. According to the results, the effective doses for transport personnel, radiation workers, and the general public are far below the regulatory limits. Therefore, we can secure safety from the viewpoint of radiological safety for all situations during the transportation of radioactive wastes which have been stored temporarily in KAERI.

Radiological Safety Assessment of Transporting Radioactive Wastes to the Gyeongju Disposal Facility in Korea

Directory of Open Access Journals (Sweden)

Jongtae Jeong

2016-12-01

Full Text Available A radiological safety assessment study was performed for the transportation of low level radioactive wastes which are temporarily stored in Korea Atomic Energy Research Institute (KAERI, Daejeon, Korea. We considered two kinds of wastes: (1 operation wastes generated from the routine operation of facilities; and (2 decommissioning wastes generated from the decommissioning of a research reactor in KAERI. The important part of the radiological safety assessment is related to the exposure dose assessment for the incident-free (normal transportation of wastes, i.e., the radiation exposure of transport personnel, radiation workers for loading and unloading of radioactive waste drums, and the general public. The effective doses were estimated based on the detailed information on the transportation plan and on the radiological characteristics of waste packages. We also estimated radiological risks and the effective doses for the general public resulting from accidents such as an impact and a fire caused by the impact during the transportation. According to the results, the effective doses for transport personnel, radiation workers, and the general public are far below the regulatory limits. Therefore, we can secure safety from the viewpoint of radiological safety for all situations during the transportation of radioactive wastes which have been stored temporarily in KAERI.

Westinghouse corporate development of a decision software program for Radiological Evaluation Decision Input (REDI)

International Nuclear Information System (INIS)

Bush, T.S.

1995-01-01

In December 1992, the Department of Energy (DOE) implemented the DOE Radiological Control Manual (RCM). Westinghouse Idaho Nuclear Company, Inc. (WINCO) submitted an implementation plan showing how compliance with the manual would be achieved. This implementation plan was approved by DOE in November 1992. Although WINCO had already been working under a similar Westinghouse RCM, the DOE RCM brought some new and challenging requirements. One such requirement was that of having procedure writers and job planners create the radiological input in work control procedures. Until this time, that information was being provided by radiological engineering or a radiation safety representative. As a result of this requirement, Westinghouse developed the Radiological Evaluation Decision Input (REDI) program

Westinghouse corporate development of a decision software program for Radiological Evaluation Decision Input (REDI)

Energy Technology Data Exchange (ETDEWEB)

Bush, T.S. [Westinghosue Idaho Nuclear Co., Inc., Idaho Falls, ID (United States)

1995-03-01

In December 1992, the Department of Energy (DOE) implemented the DOE Radiological Control Manual (RCM). Westinghouse Idaho Nuclear Company, Inc. (WINCO) submitted an implementation plan showing how compliance with the manual would be achieved. This implementation plan was approved by DOE in November 1992. Although WINCO had already been working under a similar Westinghouse RCM, the DOE RCM brought some new and challenging requirements. One such requirement was that of having procedure writers and job planners create the radiological input in work control procedures. Until this time, that information was being provided by radiological engineering or a radiation safety representative. As a result of this requirement, Westinghouse developed the Radiological Evaluation Decision Input (REDI) program.

Report on nuclear and radiological safety in 1994

International Nuclear Information System (INIS)

Lovincic, D.

1995-01-01

The Slovenian Nuclear Safety Administration (SNSA) in cooperation with the Health Inspectorate, prepared the Report on Nuclear and Radiological Safety in the Republic of Slovenia for 1994 as part of its regular practice of reporting on its activities to the Government and the Parliament of the Republic of Slovenia. The report is divided into seven thematic chapters covering the activities of the SNSA, the operation of nuclear facilities in Slovenia, the activities of the Agency for Radwaste Management (ARAO), the activities of international safety missions in Slovenia, environmental radioactivity monitoring in Slovenia, ionizing radiation sources control by Slovenian Health Inspectorate and review of the operation of nuclear facilities around the world.

Patient Safety in Interventional Radiology: A CIRSE IR Checklist

NARCIS (Netherlands)

Lee, M. J.; Fanelli, F.; Haage, P.; Hausegger, K.; van Lienden, K. P.

2012-01-01

Interventional radiology (IR) is an invasive speciality with the potential for complications as with other invasive specialities. The World Health Organization (WHO) produced a surgical safety checklist to decrease the morbidity and mortality associated with surgery. The Cardiovascular and

Nuclear and radiological safety in Slovenia in 1998

International Nuclear Information System (INIS)

Lovincic, D.

1999-09-01

This is an English version of the Annual Report of Nuclear and Radiological Safety in the Republic of Slovenia for 1998, which was prepared by The Slovenian Nuclear Safety Administration (SNSA), in cooperation with, Health Inspectorate of the Republic of Slovenia and the Administration for Civil Protection and Disaster Relief. The report presents activities of the SNSA, operation of nuclear facilities, activities of the Agency of Radwaste Management, work of international missions, emergency plan, authorized organizations, monitoring of radioactivity, control of ionizing radiation and nuclear electricity generation

Radiologic techniques in evaluation endocrine disorders

International Nuclear Information System (INIS)

Martino, C.R.; Schultz, C.L.; Butler, H.E.; Haaga, J.R.

1988-01-01

This paper discusses evaluation of normal and diseased endocrine organs that has been facilitated by the development of new radiologic-imaging techniques including nuclear medicine, ultrasound, computed tomography, and magnetic resonance imaging. With improvement in resolution and tissue contrast, abnormalities as small as 5 mm can now be imaged with these modalities. Endocrinologists and clinicians involved in the evaluation and diagnosis of patients with endocrine diseases can be substantially aided by a proper radiologic workup. The authors describe and illustrate various radiologic techniques that are useful for evaluating thyroid and parathyroid derangements

Training Programs on Radiological Safety for users of Ionizing Radiations in Peru

International Nuclear Information System (INIS)

Medina Gironzini, E.

2003-01-01

In Peru, people who work with ionizing radiations must have an authorization (Individual License) as established in the Radiological Safety Regulations, which are the mandatory rules. The Technical Office of the National Authority (OTAN), which is the technical organ of the Peruvian Institute of Nuclear Energy (IPEN) in charge of controlling radiations within the country , grants the authorization after the candidate demonstrates that he/she knows the specific use of the technique using radiations, as well a s the aspects related to safety and radiological protection. Since it was created in 1972, the Superior Center of Nuclear Studies (VSEN) from IPEN has carried out different training courses so that people can work safety with ionizing radiations in medicine, industry and investigation. The analysis of the radiological safety programs carried out by CSEN during the last 30 years, which allowed the training of more than 2200 people in the country and, at the same time, made possible the securing of the respective Individual License, is presented in this work. The courses, nuclear medicine, radiotherapy, industrial radiography, nuclear gauges gamma irradiator, etc...) and are part of the continuous education program of CSEN. (Author)

Accelerator driven systems from the radiological safety point of view

Indian Academy of Sciences (India)

application of the probabilistic safety analysis technique by assessing the probability and ... Technological and theoretical developments necessary for more precise .... Monte Carlo-based) to enable quick estimation of radiological hazards.

Safety coaches in radiology: decreasing human error and minimizing patient harm

Energy Technology Data Exchange (ETDEWEB)

Dickerson, Julie M.; Adams, Janet M. [Cincinnati Children' s Hospital Medical Center, Department of Radiology, MLC 5031, Cincinnati, OH (United States); Koch, Bernadette L.; Donnelly, Lane F. [Cincinnati Children' s Hospital Medical Center, Department of Radiology, MLC 5031, Cincinnati, OH (United States); Cincinnati Children' s Hospital Medical Center, Department of Pediatrics, Cincinnati, OH (United States); Goodfriend, Martha A. [Cincinnati Children' s Hospital Medical Center, Department of Quality Improvement, Cincinnati, OH (United States)

2010-09-15

Successful programs to improve patient safety require a component aimed at improving safety culture and environment, resulting in a reduced number of human errors that could lead to patient harm. Safety coaching provides peer accountability. It involves observing for safety behaviors and use of error prevention techniques and provides immediate feedback. For more than a decade, behavior-based safety coaching has been a successful strategy for reducing error within the context of occupational safety in industry. We describe the use of safety coaches in radiology. Safety coaches are an important component of our comprehensive patient safety program. (orig.)

Safety coaches in radiology: decreasing human error and minimizing patient harm

International Nuclear Information System (INIS)

Dickerson, Julie M.; Adams, Janet M.; Koch, Bernadette L.; Donnelly, Lane F.; Goodfriend, Martha A.

2010-01-01

Successful programs to improve patient safety require a component aimed at improving safety culture and environment, resulting in a reduced number of human errors that could lead to patient harm. Safety coaching provides peer accountability. It involves observing for safety behaviors and use of error prevention techniques and provides immediate feedback. For more than a decade, behavior-based safety coaching has been a successful strategy for reducing error within the context of occupational safety in industry. We describe the use of safety coaches in radiology. Safety coaches are an important component of our comprehensive patient safety program. (orig.)

Safety coaches in radiology: decreasing human error and minimizing patient harm.

Science.gov (United States)

Dickerson, Julie M; Koch, Bernadette L; Adams, Janet M; Goodfriend, Martha A; Donnelly, Lane F

2010-09-01

Successful programs to improve patient safety require a component aimed at improving safety culture and environment, resulting in a reduced number of human errors that could lead to patient harm. Safety coaching provides peer accountability. It involves observing for safety behaviors and use of error prevention techniques and provides immediate feedback. For more than a decade, behavior-based safety coaching has been a successful strategy for reducing error within the context of occupational safety in industry. We describe the use of safety coaches in radiology. Safety coaches are an important component of our comprehensive patient safety program.

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)

Nuclear and radiological safety in Slovenia in 1994

Energy Technology Data Exchange (ETDEWEB)

Lovincic, D [Slovenian Nuclear Safety Administration, Ljubljana (Slovenia)

1995-07-01

The Slovenian Nuclear Safety Administration (SNSA) in cooperation with the Health Inspectorate, prepared the Report on Nuclear and Radiological Safety in the Republic of Slovenia for 1994 as part of its regular practice of reporting on its activities to the Government and the Parliament of the Republic of Slovenia. The report is divided into seven thematic chapters covering the activities of the SNSA, the operation of nuclear facilities in Slovenia, the activities of the Agency for Radwaste Management (ARAO), the activities of international safety missions in Slovenia, environmental radioactivity monitoring in Slovenia, ionizing radiation sources control by Slovenian Health Inspectorate and review of the operation of nuclear facilities around the world. (author)

Nuclear and radiological safety in Slovenia in 1994

International Nuclear Information System (INIS)

Lovincic, D.

1995-01-01

The Slovenian Nuclear Safety Administration (SNSA) in cooperation with the Health Inspectorate, prepared the Report on Nuclear and Radiological Safety in the Republic of Slovenia for 1994 as part of its regular practice of reporting on its activities to the Government and the Parliament of the Republic of Slovenia. The report is divided into seven thematic chapters covering the activities of the SNSA, the operation of nuclear facilities in Slovenia, the activities of the Agency for Radwaste Management (ARAO), the activities of international safety missions in Slovenia, environmental radioactivity monitoring in Slovenia, ionizing radiation sources control by Slovenian Health Inspectorate and review of the operation of nuclear facilities around the world. (author)

Radiological Evaluation Standards in the Radiology Department of Shahid Beheshti Hospital (RAH YASUJ Based on Radiology standards in 92

Directory of Open Access Journals (Sweden)

A َKalantari

2014-08-01

Full Text Available Background & aim: Radiology personnel’s working in terms of performance and safety is one of the most important functions in order to increase the quality and quantity. This study aimed to evaluate the radiological standards in Shahid Beheshti Hospital of Yasuj, Iran, in 2013. Methods: The present cross-sectional study was based on a 118 randomly selected graphs and the ranking list, with full knowledge of the standards in radiology was performed two times. Data were analyzed using descriptive statistics. Results: 87.3% of the students chose the cassette, 76.3%, patients chose the position, 87.3%, member state, the central ray 83.9%, and the distance between the tube and the patient 68.6% had been operated in accordance with the standards practice. Among all the factors and variables, between view with cassette, view with SID, sex with position patients, grid with central ray, grid with SID, Request with positioning the patient and between density with patient position and member position significant relationship were observed p<0.05 . Conclusions: Staff and students in terms of performance were at high levels, but in the levels of protection were in poor condition. Therefore, in order to promote their conservation, education and periodical monitoring should be carried out continuously.

Informatics in radiology: evaluation of an e-learning platform for teaching medical students competency in ordering radiologic examinations.

Science.gov (United States)

Marshall, Nina L; Spooner, Muirne; Galvin, P Leo; Ti, Joanna P; McElvaney, N Gerald; Lee, Michael J

2011-01-01

A preliminary audit of orders for computed tomography was performed to evaluate the typical performance of interns ordering radiologic examinations. According to the audit, the interns showed only minimal improvement after 8 months of work experience. The online radiology ordering module (ROM) program included baseline assessment of student performance (part I), online learning with the ROM (part II), and follow-up assessment of performance with simulated ordering with the ROM (part III). A curriculum blueprint determined the content of the ROM program, with an emphasis on practical issues, including provision of logistic information, clinical details, and safety-related information. Appropriate standards were developed by a committee of experts, and detailed scoring systems were devised for assessment. The ROM program was successful in addressing practical issues in a simulated setting. In the part I assessment, the mean score for noting contraindications for contrast media was 24%; this score increased to 59% in the part III assessment (P = .004). Similarly, notification of methicillin-resistant Staphylococcus aureus status and pregnancy status and provision of referring physician contact information improved significantly. The quality of the clinical notes was stable, with good initial scores. Part III testing showed overall improvement, with the mean score increasing from 61% to 76% (P radiology services, and the experience typically afforded to interns does not address this lack of knowledge. The ROM program was a successful intervention that resulted in statistically significant improvements in the quality of radiologic examination orders, particularly with regard to logistic and radiation safety issues.

Evaluation of atmospheric dispersion/consequence models supporting safety analysis

International Nuclear Information System (INIS)

O'Kula, K.R.; Lazaro, M.A.; Woodard, K.

1996-01-01

Two DOE Working Groups have completed evaluation of accident phenomenology and consequence methodologies used to support DOE facility safety documentation. The independent evaluations each concluded that no one computer model adequately addresses all accident and atmospheric release conditions. MACCS2, MATHEW/ADPIC, TRAC RA/HA, and COSYMA are adequate for most radiological dispersion and consequence needs. ALOHA, DEGADIS, HGSYSTEM, TSCREEN, and SLAB are recommended for chemical dispersion and consequence applications. Additional work is suggested, principally in evaluation of new models, targeting certain models for continued development, training, and establishing a Web page for guidance to safety analysts

Radiological and environmental safety in front-end fuel cycle facilities

International Nuclear Information System (INIS)

Puranik, V.D.

2011-01-01

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

Spent fuel transport in Romania by road: An approach considering safety, risk and radiological consequences

International Nuclear Information System (INIS)

Vieru, G.

2001-01-01

The transport of high-level radioactive wastes, involving Type B packages, is a part of the safety of the Romanian waste management programme and the overall aim of this activity is to promote the safe transport of radioactive materials in Romania. The paper presents a safety case analysis of the transport of a single spent fuel CANDU bundle, using a Romanian built Type B package, from the CANDU type nuclear power plant Cernavoda to the INR Pitesti, in order to be examined within INR's hot-cells facilities. The safety assessment includes the following main aspects: (1) evaluation and analysis of available data on road traffic accidents; (2) estimation of the expected frequency for severe road accident scenarios resulting in potential radionuclide release; and (3) evaluation of the expected radiological consequences and accident risks of transport operations. (author)

Nuclear and Radiological Safety in Slovenia. Annual Report 1996

International Nuclear Information System (INIS)

Lovincic, D.

1997-08-01

The Slovenian Nuclear Safety Administration (SNSA), in cooperation with Health Inspectorate of the Republic of Slovenia, the Administration for Civil Protection and Disaster Relief and the Ministry of the Interior, has prepared a Report on Nuclear and Radiological Safety in the Republic of Slovenia for 1996. The report presents activities of the SNSA; operation of nuclear facilities; activities of the Agency for Radwaste Management; work of international missions; emergency plan; authorized organizations; monitoring of radioactivity; control of ionizing radiation and nuclear electricity generation

Post-deployment usability evaluation of a radiology workstation

NARCIS (Netherlands)

Jorritsma, Wiard; Cnossen, Fokie; Dierckx, Rudi; Oudkerk, Matthijs; van Ooijen, Peter

2015-01-01

Objective To evaluate the usability of a radiology workstation after deployment in a hospital. Significance In radiology, it is difficult to perform valid pre-deployment usability evaluations due to the heterogeneity of the user group, the complexity of the radiological workflow, and the complexity

Informatics in radiology: evaluation of an e-learning platform for teaching medical students competency in ordering radiologic examinations.

LENUS (Irish Health Repository)

Marshall, Nina L

2011-09-01

A preliminary audit of orders for computed tomography was performed to evaluate the typical performance of interns ordering radiologic examinations. According to the audit, the interns showed only minimal improvement after 8 months of work experience. The online radiology ordering module (ROM) program included baseline assessment of student performance (part I), online learning with the ROM (part II), and follow-up assessment of performance with simulated ordering with the ROM (part III). A curriculum blueprint determined the content of the ROM program, with an emphasis on practical issues, including provision of logistic information, clinical details, and safety-related information. Appropriate standards were developed by a committee of experts, and detailed scoring systems were devised for assessment. The ROM program was successful in addressing practical issues in a simulated setting. In the part I assessment, the mean score for noting contraindications for contrast media was 24%; this score increased to 59% in the part III assessment (P = .004). Similarly, notification of methicillin-resistant Staphylococcus aureus status and pregnancy status and provision of referring physician contact information improved significantly. The quality of the clinical notes was stable, with good initial scores. Part III testing showed overall improvement, with the mean score increasing from 61% to 76% (P < .0001). In general, medical students lack the core knowledge that is needed for good-quality ordering of radiology services, and the experience typically afforded to interns does not address this lack of knowledge. The ROM program was a successful intervention that resulted in statistically significant improvements in the quality of radiologic examination orders, particularly with regard to logistic and radiation safety issues.

Radiological safety of nuclear power plants in India

International Nuclear Information System (INIS)

Sathish, A.V.

2015-01-01

Safety in nuclear power plants (NPPs) is often less understood and more talked about, thus the author wanted to share the facts to clear the myths. Safety is accorded overriding priority in all the activities. All nuclear facilities are sited, designed, constructed, commissioned and operated in accordance with strict quality and safety standards. Principles of defence in depth, redundancy and diversity are followed in the design of all nuclear facilities and their systems/components. PPs in India are not only safe but are also well regulated, have proper radiological protection of workers and the public, regular surveillance, approved standard operating and maintenance procedures, a well-defined waste management methodology, periodically rehearsed emergency preparedness and disaster management plans. The regulatory framework in the country is robust, with the independent Atomic Energy Regulatory Board (AERB) having powers to frame the policies, laying down safety standards, monitoring and enforcing all the safety provisions. As a result, India's safety record has been excellent in over 400 reactor years of operation of power reactors

Patient Safety in Interventional Radiology: A CIRSE IR Checklist.

LENUS (Irish Health Repository)

2012-02-01

Interventional radiology (IR) is an invasive speciality with the potential for complications as with other invasive specialities. The World Health Organization (WHO) produced a surgical safety checklist to decrease the morbidity and mortality associated with surgery. The Cardiovascular and Interventional Society of Europe (CIRSE) set up a task force to produce a checklist for IR. Use of the checklist will, we hope, reduce the incidence of complications after IR procedures. It has been modified from the WHO surgical safety checklist and the RAD PASS from Holland.

The present condition of the radiation safety control education in training schools for radiological technologists

International Nuclear Information System (INIS)

Takahashi, Yasuyuki; Saito, Kyoko; Hirai, Shoko; Igarashi, Hiroshi; Negishi, Tooru; Hirano, Kunihiro; Kawaharada, Yasuhiro

2010-01-01

We made a detailed study on the course of study in radiation safety control prescribed on March 28, 2003. Questionnaires were sent to 39 training schools for radiological technology, to which 66.7% replied (26/39). Subjects on radiation safety control must include knowledge and technology in both radiation control and medical safety. The contents for instruction of radiation control were in accordance with those given in the traditional program; however, some discrepancies were found in the contents of medical safety. As medical safety, emphasized by the revised Medical Service Law, is regarded as very important by many hospitals, safety control education that include medical ethics should be required as part of the curriculum in the training schools for radiological technologists. (author)

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

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.

Evaluation of radiological safety assessment of a repository in a clay rock formation

International Nuclear Information System (INIS)

1999-01-01

This report presents a comprehensive description of the post-closure radiological safety assessment of a repository for the spent fuel arisings resulting from the Spanish nuclear program excavated in a clay host rock formation. In this report three scenarios have been analysed in detail. The first scenario represents the normal in detail. The first scenario represents the normal evolution of the repository (Reference Scenario); and includes a set of variants to investigate the relative importance of the various repository components and examine the sensitivity of the performance to parameters variations. Two altered scenarios have also been considered: deep well construction and poor sealing of the repository. This document contains a detailed description of the repository system, the methodology adopted for the scenarios generation, the process modelling approach and the results of the consequences analysis. (Author)

Nuclear and radiological safety in Slovenia in 1998, Annual report

International Nuclear Information System (INIS)

Lovincic, D.

1999-09-01

The Slovenian Nuclear Safety Administration (SNSA), in cooperation with Health Inspectorate of the Republic of Slovenia and the Administration for Civil Protection and Disaster Relief, has prepared a Report of Nuclear and Radiological Safety in the Republic of Slovenia for 1998. The report presents activities of the SNSA, operation of nuclear facilities, activities of the Agency of Radwaste Management, work of international missions, emergency plan, authorized organizations, monitoring of radioactivity, control of ionizing radiation and nuclear electricity generation

Nuclear and radiological safety 1980-1994. International Atomic Energy Agency Publications

International Nuclear Information System (INIS)

1995-06-01

This catalogue lists all sales publications of the International Atomic Energy Agency dealing with Nuclear and Radiological Safety issued during the period 1980-1994. The following aspects are covered: Uranium mining and milling, Fuel fabrication and storage, Nuclear power plants, Research reactors, Radiation sources and accelerators, Transport of radioactive materials, Waste repositories, Radiation protection, Accident response, Radioactive waste management, Safety analysis, Quality management, Legal and governmental aspects

Nuclear and radiological safety. 1986-1998. International Atomic Energy Agency publications

International Nuclear Information System (INIS)

1999-04-01

This catalogue lists all sales publications of the IAEA dealing with nuclear and radiological safety issued from 1986 to 1998. Publications are sorted according to the following subjects: Uranium mining and milling; Fuel fabrication and storage; Nuclear power plants; Research reactors; Radiation sources and accelerators; Transport of radioactive material; Waste repositories; Radiation protection; Accident response; Radioactive waste management; Safety analysis; Quality management; Legal and governmental aspects

Nuclear and radiological safety. 1990-2001. International Atomic Energy Agency publications

International Nuclear Information System (INIS)

2001-08-01

This catalogue lists all sales publications of the IAEA dealing with nuclear and radiological safety issued from 1990 to 2001. Publications are sorted according to the following subjects: Uranium mining and milling. Fuel fabrication and storage. Nuclear power plants. Research reactors. Radiation sources and accelerators. Transport of radioactive material. Waste repositories. Radiation protection. Accident response. Radioactive waste management. Safety analysis. Quality management. Legal and governmental aspects

Nuclear and radiological safety. 1990-2001. International Atomic Energy Agency publications

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-08-01

This catalogue lists all sales publications of the IAEA dealing with nuclear and radiological safety issued from 1990 to 2001. Publications are sorted according to the following subjects: Uranium mining and milling. Fuel fabrication and storage. Nuclear power plants. Research reactors. Radiation sources and accelerators. Transport of radioactive material. Waste repositories. Radiation protection. Accident response. Radioactive waste management. Safety analysis. Quality management. Legal and governmental aspects.

Radiological and nuclear safety- evolution, standards and similarity

International Nuclear Information System (INIS)

Soman, S.D.

1996-01-01

With the realisation of potential for severe health affects after the discovery of x-rays and radioactivity, the radiation protection aspect became focus of interest for medical users from the beginning of this century. With the activities of International Commission on Radiological Protection (ICRP), the standards evolved during all these years based on epidemiological data and radio-biological research. The current standards are the ICRP recommendations of 1990. Based on these, internationally harmonised standards for protection against ionising radiation and safety of radioactive sources were brought out by IAEA in 1994. The nuclear safety (implies safety of nuclear power plants) came into prominence when large scale units were designed and operated since mid 1950s. The philosophy in nuclear safety has evolved in past 2-3 decades taking into account the lessons learned from accidents, mainly Three Mile Island (1979) and Chernobyl-4 (1986). These current nuclear safety standards are incorporated in INSAG reports, particularly INSAG-3. This paper brings out salient features of these evolutions, current standards and similarity of radiation and nuclear safety standards in their present form. (author). 7 refs., 10 tabs

Circles of quality in radiological safety

International Nuclear Information System (INIS)

Gonzalez F, J.A.

1991-01-01

The concept of Circles of quality arose in Japan like an option to capitalize the enormous potential that the workers had developed as a result of its training in the statistical tools of quality. There are presented a series of steps that could be given with the purpose of implementing a program of ALARA circles. The radiological safety is in it finishes instance responsibility of each hard-working one and there won't be a protection program that can work among apathetic people, it is in this sense where the ALARA circles can provide its maximum contribution creating a conscience of responsibility and participation

Radiological risk guidelines for nonreactor nuclear facilities at the Pacific Northwest Laboratory

International Nuclear Information System (INIS)

Lucas, D.E.; Ikenberry, T.A.

1994-03-01

Radiological risk evaluation guidelines for the public and workers have been developed at the Pacific Northwest Laboratory (PNL) based upon the Nuclear Safety Policy of the US Department of Energy (DOE) established in Secretary of Energy Notice SEN-35-91 (DOE 1991). The DOE nuclear safety policy states that the general public be protected-such that no individual bears significant additional risk to health and safety from the operation of a DOE nuclear facility above the risks to which members of the general population are normally exposed. The radiological risk evaluation guidelines developed at PNL are unique in that they are (1) based upon quantitative risk goals and (2) provide a consistent level of risk management. These guidelines are used to evaluate the risk from radiological accidents that may occur during research and development activities at PNL. A safety analyst uses the frequency of the potential accident and the radiological dose to a given receptor to determine if the accident consequences meet the objectives of the Nuclear Safety Policy

Radiological safety assessment of a reference INTOR facility

International Nuclear Information System (INIS)

Khan, T.A.; Stasko, R.R.; Watts, R.T.; Shaw, G.; Morrison, C.A.; Russell, S.; Kempe, T.; Zimmerman, R.

1985-03-01

This report consists of a number of separate studies all of which were performed in support of INTOR Critical Issue D: Tritium Containment and Personnel Access vs Remote Maintenance. The common thread running through these studies is the radiological safety element in the design and operation of the INTOR facility. The intent is to help establish a firm basis for comparisons between a reactor cell maintenance option which requires personnel access, and one which involves completely remote maintenance

CP-50 calibration facility radiological safety assessment document

International Nuclear Information System (INIS)

Chilton, M.W.; Hill, R.L.; Eubank, B.F.

1980-03-01

The CP-50 Calibration Facility Radiological Safety Assessment document, prepared at the request of the Nevada Operations Office of the US Department of Energy to satisfy provisions of ERDA Manual Chapter 0531, presents design features, systems controls, and procedures used in the operation of the calibration facility. Site and facility characteristics and routine and non-routine operations, including hypothetical incidents or accidents are discussed and design factors, source control systems, and radiation monitoring considerations are described

Current Approaches of Regulating Radiological Safety of Medical and Industrial Practices in Romania

International Nuclear Information System (INIS)

Goicea, C.

2016-01-01

The principal document regulating the radiological safety of ionizing radiation application in Romania is the “Fundamental Norms for Radiological Safety”. These norms establish the requirements concerning the assurance of radiological safety of occupational exposed workers, population and environment, in accordance with the provisions of Law 111/1996 on the safe deployment of nuclear activities, republished. Justification of practices for all new practices which lead to exposure to ionizing radiation shall be justified in writing by their initiator, underlining their economic, social or other nature advantages, in comparison with the detriment which they could cause to health. CNCAN authorise these practices, provided that they consider the justification as being thorough. The applicant, respectively the authorisation holder, has to demonstrate that all actions to ensure radiation protection optimization are undertaken, with a view to ensure that all exposures, including the potential ones, within the framework of practice developed are maintained at the lowest reasonable achievable level, taking into account the economic and social factors: ALARA principle.

Radiological risk guidelines for nonreactor nuclear facilities at the Pacific Northwest Laboratory

International Nuclear Information System (INIS)

Lucas, D.E.; Ikenberry, T.A.

1993-09-01

Radiological risk evaluation guidelines for the public and workers have been developed at the Pacific Northwest Laboratory (PNL) based upon the Nuclear Safety Policy of the US Department of Energy (DOE) established in Secretary of Energy Notice SEN-35-91. The DOE nuclear safety policy states that the general public shall be protected such that no individual bears significant additional risk to health and safety from the operation of a DOE nuclear facility above the risks to which members of the general population are normally exposed. The radiological risk evaluation guidelines developed at PNL are unique in that they are (1) based upon quantitative risk goals and (2) provide a consistent level of risk management. These guidelines are used to evaluate the risk from radiological accidents that may occur during research and development activities at PNL, and are not intended for evaluation of routine exposures. A safety analyst uses the,frequency of the potential accident and the radiological dose to a given receptor to determine if the accident consequences meet the objectives of the Nuclear Safety Policy. The radiological risk evaluation guidelines are an effective tool for assisting in the management of risk at DOE nonreactor nuclear facilities. These guidelines (1) meet the nuclear safety policy of DOE, (2) establish a tool for managing risk at a consistent level within the defined constraints, and (3) set risk at an appropriate level, as compared with other risks encountered by the public and worker. Table S.1 summarizes the guidelines developed in this report

The NKS programmes for Nordic cooperation on nuclear and radiological safety

DEFF Research Database (Denmark)

Andersson, Kasper Grann; Leino, Kaisu; Magnússon, Sigurður M.

2013-01-01

NKS is a platform for Nordic cooperation and competence maintenance in nuclear and radiological safety, including emergency preparedness. It is an informal forum serving as an umbrella for Nordic initiatives and interests. It runs joint activities of interest to financing organisations and other...

Radiological consequence evaluation of DBAs with alternative source term method for a Chinese PWR

International Nuclear Information System (INIS)

Li, J.X.; Cao, X.W.; Tong, L.L.; Huang, G.F.

2012-01-01

Highlights: ► Radiological consequence evaluation of DBAs with alternative source term method for a Chinese 900 MWe PWR has been investigated. ► Six typical DBA sequences are analyzed. ► The doses of control room, EAB and outer boundary of LPZ are acceptable. ► The differences between AST method and TID-14844 method are investigated. - Abstract: Since a large amount of fission products may releases into the environment, during the accident progression in nuclear power plants (NPPs), which is a potential hazard to public risk, the radiological consequence should be evaluated for alleviating the hazard. In most Chinese NPPs the method of TID-14844, in which the whole body and thyroid dose criteria is employed as dose criteria, is currently adopted to evaluate the radiological consequences for design-basis accidents (DBAs), but, due to the total effective dose equivalent is employed as dose criteria in alternative radiological source terms (AST) method, it is necessary to evaluate the radiological consequences for DBAs with AST method and to discuss the difference between two methods. By using an integral safety analysis code, an analytical model of the 900 MWe pressurized water reactor (PWR) is built and the radiological consequences in DBAs at control room (CR), exclusion area boundary (EAB), low population zone (LPZ) are analyzed, which includes LOCA and non-LOCA DBAs, such as fuel handling accident (FHA), rod ejection accident (REA), main steam line break (MSLB), steam generator tube rupture (SGTR), locked rotor accident (LRA) by using the guidance of the RG 1.183. The results show that the doses in CR, EAB and LPZ are acceptable compared with dose criteria in RG 1.183 and the differences between AST method and TID-14844 method are also discussed.

Indicators of the management for the continuous improvement of the radiological safety in a radioactive facility; Indicadores de gestion para la mejora continua de la seguridad radiologica en una instalacion radiactiva

Energy Technology Data Exchange (ETDEWEB)

Amador B, Z. H. [Centro de Isotopos, Ave. Monumental y Carretera La Rada, Km 3, Guanabacoa, Apartado 3415, Ciudad de La Habana (Cuba)]. e-mail: zabalbona@centis.edu.cu

2006-07-01

The use of safety indicators is common in the nuclear industry. In this work the implementation of indicators for the efficiency analysis of the radiological safety management system of a radioactive installation is presented. Through the same ones the occupational exposure, the training Y authorization of the personnel, the control of practices Y radioactive inventory, the results of the radiological surveillance, the occurrence of radiological events, the aptitude of the monitoring equipment, the management of the radioactive waste, the public exposure, the audits Y the costs of safety are evaluated. Its study is included in the periodic training of the workers. Without this interrelation it is not possible to maintain the optimization of the safety neither to achieve a continuous improvement. (Author)

Radiological evaluation of esophageal motility and gastroesophageal reflux disease

International Nuclear Information System (INIS)

Schima, W.; Pokieser, P.; Schober, E.

1995-01-01

Radiological evaluation of esophageal motility and the lower esophageal sphincter has gained increased attention in recent years. Videofluoroscopic investigation of esophageal motor function is superior to static film radiography, as repeated analysis of the videotaped recordings is possible. With emphasis on radiological techniques, normal esophagel physiology and motility and a variety of esophageal motor disorders are discussed in this review paper. Radiological evaluation of gastroesophageal reflux and reflux esophagitis is described. Clinical and radiological findings in esophageal motility disorders and gastroesophageal reflux disease and the radiological efficacy compared to that of manometry and pH-metry are discussed. (orig.) [de

Evaluation of common mode failure of safety functions for limiting fault events

International Nuclear Information System (INIS)

Rezendes, J.P.; Hyde, A.W.

2004-01-01

The draft U.S. Nuclear Regulatory Commission (NRC) policy on digital protection system software requires all Advanced Light Water Reactors (ALWRs) to be evaluated assuming a hypothetical common mode failure (CMF) which incapacitates the normal automatic initiation of safety functions. The System 80 + ALWR has been evaluated for such hypothetical conditions. The results show that the diverse automatic and manual protective systems in System 80 + provide ample safety performance margins relative to core coolability, offsite radiological releases. Reactor Coolant System (RCS) pressurization and containment integrity. This deterministic evaluation served to quantify the significant inherent safety margins in the System 80 + Standard Plant design even in the event of this extremely low probability scenario of a common mode failure. (author)

Efficacy of radiology of the esophagus for evaluation of dysphagia

Energy Technology Data Exchange (ETDEWEB)

Ott, D.J.; Gelfand, D.W.; Wu, W.C.

1981-05-15

The efficacy of radiology in evaluating dysphagia was studied in 86 patients by comparison to endoscopic findings. In the 66 patients with endoscopic abnormalities radiology was correct in 54, for a sensitivity of 82%. Sensitivity of radiology improved to 95% if mild esophagitis was excluded. In the 20 patients with normal endoscopy, radiology was normal in 18 (90%). Thus radiology proved to be a reliable means of evaluating the esophagus in patients with dysphagia.

Critical evaluation of safety and radiological protection requirements adopted for the transport of uranium and thorium ores and concentrates

International Nuclear Information System (INIS)

Mezrahi, Arnaldo; Crispim, Verginia R.

2009-01-01

This work evaluates in a critical way the safety and radiological protection recommendations established by the International Atomic Energy Agency - IAEA and adopted national and internationally, for the transport of uranium and thorium ores and concentrates, known according the transport regulations, as being of the Low Specific Activity Material Type-I, LSA-I, basing on more realistic scenarios than the presently existent, aiming at the determination of maximum exposure levels of radiation as well as the maximal contents of those materials in packages and conveyance. A general overview taking into account the scenarios foreseen by the regulations of the IAEA pointed out for a need of a better justification of the requirements edited by the Agency or should be used to support a request of revision of those regulations, national and internationally adopted, in the pertinent aspects to the transport of uranium and thorium ores and concentrates. (author)

Overview of Generation IV (Gen IV) Reactor Designs - Safety and Radiological Protection Considerations

International Nuclear Information System (INIS)

Baudrand, Olivier; Blanc, Daniel; Ivanov, Evgeny; Bonneville, Herve; Clement, Bernard; Kissane, Martin; Meignen, Renaud; Monhardt, Daniel; Nicaise, Gregory; Bourgois, Thierry; Bruna, Giovanni; Hache, Georges; Repussard, Jacques

2012-01-01

The purpose of this document is to provide an updated overview of specific safety and radiological protection issues for all the reactor concepts adopted by the GIF (Generation IV International Forum), independent of their advantages or disadvantages in terms of resource optimization or long-lived-waste reduction. In particular, this new document attempts to bring out the advantages and disadvantages of each concept in terms of safety, taking into account the Western European Nuclear Regulators' Association (WENRA) statement concerning safety objectives for new nuclear power plants. Using an identical framework for each reactor concept (sodium-cooled fast reactors or SFR, high / very-high temperature helium-cooled reactors of V/HTR, gas-cooled fast reactors or GFR, lead-or lead / bismuth-cooled fast reactors or LFR, molten salt reactors or MSR, and supercritical-water-cooled reactors or SCWR), this summary report provides some general conclusions regarding their safety and radiological protection issues, inspired by WENRA's safety objectives and on the basis of available information. Initial lessons drawn from the events at the Fukushima-Daiichi nuclear power plant in March 2011 have also been taken into account in IRSN's analysis of each reactor concept

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.

Radiological safety aspects of the operation of neutron generators

International Nuclear Information System (INIS)

Boggs, R.F.

1976-01-01

The purpose of the manual is to provide some basic guidelines to persons with a minimum of training in radiological health or health physics, on some safety aspects of the operation of sealed-tube and Cockcroft-Walton type neutron generators. The manual does not state rules or regulations but presents a description of the most likely hazards. It is relevant to those relatively compact neutron generators which usually operate at less than 150-200 kV for the purpose of producing 14-MeV neutrons. The scope is limited to basic discussions of hazards and measurement techniques. Separate chapters are devoted to the characteristics and use of neutron generators; radiation hazards and safety considerations; radiation monitoring and interpretation of measurements; and requirements for an effective safety programme. Two appendices deal with non-radiation hazards and safety considerations, and with a neutron generator laboratory, respectively. An extensive list of bibliographic references is included

ORNL necessary and sufficient standards for environment, safety, and health. Final report of the Identification Team for other industrial, radiological, and non-radiological hazard facilities

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-07-01

This Necessary and Sufficient (N and S) set of standards is for Other Industrial, Radiological, and Non-Radiological Hazard Facilities at Oak Ridge National Laboratory (ORNL). These facility classifications are based on a laboratory-wide approach to classify facilities by hazard category. An analysis of the hazards associated with the facilities at ORNL was conducted in 1993. To identify standards appropriate for these Other Industrial, Radiological, and Non-Radiological Hazard Facilities, the activities conducted in these facilities were assessed, and the hazards associated with the activities were identified. A preliminary hazards list was distributed to all ORNL organizations. The hazards identified in prior hazard analyses are contained in the list, and a category of other was provided in each general hazard area. A workshop to assist organizations in properly completing the list was held. Completed hazard screening lists were compiled for each ORNL division, and a master list was compiled for all Other Industrial, Radiological Hazard, and Non-Radiological facilities and activities. The master list was compared against the results of prior hazard analyses by research and development and environment, safety, and health personnel to ensure completeness. This list, which served as a basis for identifying applicable environment, safety, and health standards, appears in Appendix A.

ORNL necessary and sufficient standards for environment, safety, and health. Final report of the Identification Team for other industrial, radiological, and non-radiological hazard facilities

International Nuclear Information System (INIS)

1998-07-01

This Necessary and Sufficient (N and S) set of standards is for Other Industrial, Radiological, and Non-Radiological Hazard Facilities at Oak Ridge National Laboratory (ORNL). These facility classifications are based on a laboratory-wide approach to classify facilities by hazard category. An analysis of the hazards associated with the facilities at ORNL was conducted in 1993. To identify standards appropriate for these Other Industrial, Radiological, and Non-Radiological Hazard Facilities, the activities conducted in these facilities were assessed, and the hazards associated with the activities were identified. A preliminary hazards list was distributed to all ORNL organizations. The hazards identified in prior hazard analyses are contained in the list, and a category of other was provided in each general hazard area. A workshop to assist organizations in properly completing the list was held. Completed hazard screening lists were compiled for each ORNL division, and a master list was compiled for all Other Industrial, Radiological Hazard, and Non-Radiological facilities and activities. The master list was compared against the results of prior hazard analyses by research and development and environment, safety, and health personnel to ensure completeness. This list, which served as a basis for identifying applicable environment, safety, and health standards, appears in Appendix A

Data processing for the evaluation of the thickness of protective barriers : Case of radiology rooms and external beam radiotherapy

International Nuclear Information System (INIS)

RANDRIANANTOANDRO, R.G.G.

2004-01-01

The regulation requires that the legal persons who have an intention to use radiation sources shall submit a notification to the Regulatory Authority of such an intention, which shall take the form of a licence or an authorization. The documents of radiological safety including design, construction, clinical utilisation...are attached to this notification. This work intends to assess the thickness of protection barrier and to suggest a facility design in radiology and in radiotherapy which comply with the safety standards. Because the steps of the thickness evaluation require a lot of calculation and abacs, the computer is used for this processing with Visual Basic. [fr

Assessment of Safety Parameters for Radiological Explosion Based on Gaussian Dispersion Model

Energy Technology Data Exchange (ETDEWEB)

Pandey, Alok [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of); Yu, Hyungjoon; Kim, Hong Suk [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

2014-10-15

These sources if used with explosive (called RDD - radiological dispersion device), can cause dispersion of radioactive material resulting in public exposure and contamination of the environment. Radiological explosion devices are not weapons for the mass destruction like atom bombs, but can cause the death of few persons and contamination of large areas. The reduction of the threat of radiological weapon attack by terrorist groups causing dispersion of radioactive material is one of the priority tasks of the IAEA Nuclear Safety and Security Program.Emergency preparedness is an essential part for reducing and mitigating radiological weapon threat. Preliminary assessment of dispersion study followed by radiological explosion and its quantitative effect will be helpful for the emergency preparedness team for an early response. The effect of the radiological dispersion depends on various factors like radioisotope, its activity, physical form, amount of explosive used and meteorological factors at the time of an explosion. This study aim to determine the area affected by the radiological explosion as pre assessment to provide feedback to emergency management teams for handling and mitigation the situation after an explosion. Most practical scenarios of radiological explosion are considered with conservative approach for the assessment of the area under a threat for emergency handling and management purpose. Radioisotopes under weak security controls can be used for a radiological explosion to create terror and socioeconomic threat for the public. Prior assessment of radiological threats is helpful for emergency management teams to take prompt decision about evacuation of the affected area and other emergency handling actions. Comparable activities of Co-60 source used in radiotherapy and Sr-90 source of disused and orphaned RTGs with two different quantities of TNT were used for the scenario development of radiological explosion. In the Basic Safety Standard (BSS

Assessment of Safety Parameters for Radiological Explosion Based on Gaussian Dispersion Model

International Nuclear Information System (INIS)

Pandey, Alok; Yu, Hyungjoon; Kim, Hong Suk

2014-01-01

These sources if used with explosive (called RDD - radiological dispersion device), can cause dispersion of radioactive material resulting in public exposure and contamination of the environment. Radiological explosion devices are not weapons for the mass destruction like atom bombs, but can cause the death of few persons and contamination of large areas. The reduction of the threat of radiological weapon attack by terrorist groups causing dispersion of radioactive material is one of the priority tasks of the IAEA Nuclear Safety and Security Program.Emergency preparedness is an essential part for reducing and mitigating radiological weapon threat. Preliminary assessment of dispersion study followed by radiological explosion and its quantitative effect will be helpful for the emergency preparedness team for an early response. The effect of the radiological dispersion depends on various factors like radioisotope, its activity, physical form, amount of explosive used and meteorological factors at the time of an explosion. This study aim to determine the area affected by the radiological explosion as pre assessment to provide feedback to emergency management teams for handling and mitigation the situation after an explosion. Most practical scenarios of radiological explosion are considered with conservative approach for the assessment of the area under a threat for emergency handling and management purpose. Radioisotopes under weak security controls can be used for a radiological explosion to create terror and socioeconomic threat for the public. Prior assessment of radiological threats is helpful for emergency management teams to take prompt decision about evacuation of the affected area and other emergency handling actions. Comparable activities of Co-60 source used in radiotherapy and Sr-90 source of disused and orphaned RTGs with two different quantities of TNT were used for the scenario development of radiological explosion. In the Basic Safety Standard (BSS

Radiological and the other safety aspects in the operation of electron beam facility

International Nuclear Information System (INIS)

Loterina, Roel Alamares

2003-01-01

The radiological safety aspects of the operation of an electron beam facility in general and the 3 MeV ALURTRON electron beam facility of the Malaysian Institute of Nuclear Technology Research (MINT) in particular were reviewed and evaluated. Evaluation was made based on existing records as well as actual monitoring around facility. Area monitoring results using TLDs are within permissible levels. The maximum reading of 7.29 mSv measured in year 2000 is very low as compared to the annual dose limit of 50 mSv/year. In general, the shielding for the installation is adequate and no significant radiation leakage were detected based on radiation survey results. However, measured radiation levels with a maximum of 1.9 mSv/h at the sampling ports easily exceed the limit of 25μSv/h. The facility is equipped with safety features, such as interlocked system, adequate shielding, engineered safety design of irradiation and accelerator rooms, and accessories such as conveyor system and product handling system. Warning lights and signals are adequately installed around the facility. Other identified hazards that may affect the operator, workers, and personnel were also evaluated based on previous records of monitoring. The ozone concentration levels with a maximum reading of 0.05 ppm measured in the environment of the facility are within the threshold limit value of 0.1 ppm. The measured noise levels at all locations around facility are generally below the maximum permissible level of 80dB. The ALURTRON has achieved a minimum safety requirement to warrant its full operation without relying on administrative controls and procedures to ensure safety in operation. (Auth.)

Diagnosis of current state of the radiological safety system in the radiotherapy services of CCSS

International Nuclear Information System (INIS)

Calvo, Carolina Masis

2013-01-01

This article presents an analysis of evaluation reports issued by the Area of Control of Quality and Radiation Protection (ACCPR) of the Caja Costarricense de Seguro Social (CCSS, unit responsible for monitoring and auditing the System of Institutional Radiation Safety of the Costa Rica. In addition, were conducted a series of interviews to the radiotherapy services and authorities of the services to determine the internal perception on the performance and suitability of these programs.The results of this research have allowed identifying an improvement in the level of compliments of the current legislation on protection and radiation safety in these services through the previous five years; and how internally there is a positive perception of the officials, confirming the suitability of Radiological Protection and Quality Control Programs local. As a result of the analysis of the information gathered, we propose a series of actions and recommendations, that will allow improvements in the System of Institutional Radiation Safety, as the implementation of evaluations type QUATRO and the improvement of the local training programs

Occupational Exposure to Diagnostic Radiology in Workers without Training in Radiation Safety

International Nuclear Information System (INIS)

Gaona, Enrique; Enriquez, Jesus G. Franco

2004-01-01

The physicians, technicians, nurses, and others involved in radiation areas constitute the largest group of workers occupationally exposed to man-made sources of radiation. Personnel radiation exposure must be monitored for safety and regulatory considerations, this assessment may need to be made over a period of one month or several months. The purpose of this study was to carry out an exploratory survey of occupational exposures associated with diagnostic radiology. The personnel dosimeters used in this study were thermoluminescent dosimeters (TLDs). The reported number of monitored workers was 110 of different departments of radiology of the Mexican Republic without education in radiation safety, included general fluoscopic/radiographic imaging, computed tomography and mammography procedures. Physicians and X-ray technologist in diagnostic radiology receive an average annual effective dose of 2.9 mSv with range from 0.18 to 5.64 mSv. The average level of occupational exposures is generally similar to the global average level of natural radiation exposure. The annual global per capita effective dose due to natural radiation sources is 2.4 mSv (UNSCEAR 2000 Report). There is not significant difference between average occupational exposures and natural radiation exposure for p < 0.05

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

Proceedings of the 7th National Congress of the Mexican Society of Radiological Safety C.A

International Nuclear Information System (INIS)

1997-01-01

The Mexican Society of Radiological Safety, celebrates on this time the 100 Anniversary of the radioactivity discovery, phenomenon coined by Marie Curie in 1898 and discover by Henry Beckerel in March 1896, when both were working with natural radioactive isotopes. Subsequently, on the new age of Physics, the use of radioactive isotopes was impulse by the invention of Cyclotron made by Dr. Ernest Orland Lawrence in the United States, which permits the manufacturing of tens of artificial radioactive isotopes which convert its in an indispensable tool in Medicine, Industry, Research, Agriculture and other disciplines, by its wide variety of applications, creating the radiological safety culture by the implicit risk in the use of these materials. From its creation in 1976, our society was removing to promote the radiological safety and two years each celebrates its National Congress removing specialists in this discipline and invite new generations to awake their interest by this useful field. (Author)

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

Evaluation of radiological medical practice during night duty

International Nuclear Information System (INIS)

Tasu, J.P.; Rocher, L.; Miquel, A.; Rondeau, Y.; Blery, M.; Nguyen, D.T.; Spira, A.; Livartowski, J.; Ellrodt, A.

2000-01-01

To evaluate the radiological activity during night duty, in a University Hospital, during 100 days, the radiological activity has been evaluated from examinations requiring radiologist (including US and CT, special X-ray examinations). The urgent nature and the agreement between the suspected disease and the final diagnose have been compared with the level of the clinician (medical student, resident, senior). 981 radiological examinations were performed on an emergency basis. In 39%, the examination was urgent or very urgent and for 61% little urgent or non-urgent. The level of the clinician was correlated with the degree of emergency evaluated by the radiologist and with the agreement between suspected disease and the final diagnose (p<0.0001). During night duty, the medical activity in radiology is not justified only be emergency, but also the continuous hospital activities. Better formation of the physician is required to limit the number of examinations. (authors)

Preparedness and Response for a Nuclear or Radiological Emergency. General Safety Requirements (Arabic Edition)

International Nuclear Information System (INIS)

2016-01-01

This publication, jointly sponsored by the FAO, IAEA, ICAO, ILO, IMO, INTERPOL, OECD/NEA, PAHO, CTBTO, UNEP, OCHA, WHO and WMO, is the new edition establishing the requirements for preparedness and response for a nuclear or radiological emergency which takes into account the latest experience and developments in the area. It supersedes the previous edition of the Safety Requirements for emergency preparedness and response, Safety Standards Series No. GS-R-2, which was published in 2002. This publication establishes the requirements for ensuring an adequate level of preparedness and response for a nuclear or radiological emergency, irrespective of its cause. These Safety Requirements are intended to be used by governments, emergency response organizations, other authorities at the local, regional and national levels, operating organizations and the regulatory body as well as by relevant international organizations at the international level.

Preparedness and Response for a Nuclear or Radiological Emergency. General Safety Requirements (Russian Edition)

International Nuclear Information System (INIS)

2016-01-01

This publication, jointly sponsored by the FAO, IAEA, ICAO, ILO, IMO, INTERPOL, OECD/NEA, PAHO, CTBTO, UNEP, OCHA, WHO and WMO, is the new edition establishing the requirements for preparedness and response for a nuclear or radiological emergency which takes into account the latest experience and developments in the area. It supersedes the previous edition of the Safety Requirements for emergency preparedness and response, Safety Standards Series No. GS-R-2, which was published in 2002. This publication establishes the requirements for ensuring an adequate level of preparedness and response for a nuclear or radiological emergency, irrespective of its cause. These Safety Requirements are intended to be used by governments, emergency response organizations, other authorities at the local, regional and national levels, operating organizations and the regulatory body as well as by relevant international organizations at the international level.

Preparedness and Response for a Nuclear or Radiological Emergency. General Safety Requirements (Chinese Edition)

International Nuclear Information System (INIS)

2016-01-01

This publication, jointly sponsored by the FAO, IAEA, ICAO, ILO, IMO, INTERPOL, OECD/NEA, PAHO, CTBTO, UNEP, OCHA, WHO and WMO, is the new edition establishing the requirements for preparedness and response for a nuclear or radiological emergency which takes into account the latest experience and developments in the area. It supersedes the previous edition of the Safety Requirements for emergency preparedness and response, Safety Standards Series No. GS-R-2, which was published in 2002. This publication establishes the requirements for ensuring an adequate level of preparedness and response for a nuclear or radiological emergency, irrespective of its cause. These Safety Requirements are intended to be used by governments, emergency response organizations, other authorities at the local, regional and national levels, operating organizations and the regulatory body as well as by relevant international organizations at the international level.

Radiological safety and quality paradigms in leadership and innovation

CERN Document Server

Lau, Lawrence

2013-01-01

This book is the product of a unique collaboration by experts from leading international, regional and national agencies and professional organizations discussing on the current 'hot' issue on the judicious use and safety of radiation in radiology. There have been several cases involving radiation overexposure that have received international attention. Strategies and solutions to guide readers how to maximize the benefits and minimize the risks when using radiation in medicine are covered.

The 7 basic tools of quality applied to radiological safety

International Nuclear Information System (INIS)

Gonzalez F, J.A.

1991-01-01

This work seeks to establish a series of correspondences among the search of the quality and the optimization of the doses received by the occupationally exposed personnel. There are treated about the seven basic statistic tools of the quality: the Pareto technique, Cause effect diagrams, Stratification, Verification sheet, Histograms, Dispersion diagrams and Graphics and control frames applied to the Radiological Safety

Standarized radiological hazard analysis for a broad based operational safety program

International Nuclear Information System (INIS)

Wadman, W.W. III; Andrews, L.L.

1992-01-01

The Radiological hazard Analysis (RHA) Manual provides a methodology and detailed guidance for systematic analysis of radiological hazards over a broad spectrum of program functions, housed in a wide variety of facilities. Radiological programs at LANL include: research and experimentation; routine materials operations; production; non-destructive examination or testing; isotope and machine produced radiations; chemistry; and metallurgy. The RHA permits uniform evaluation of hazard types over a range of several orders of magnitude of hazard severity. The results are used to estimate risk, evaluate types and level or resource allocations, identify deficiencies, and plan corrective actions for safe working environments. 2 refs

Standardized radiological hazard analysis for a broad based operational safety program

International Nuclear Information System (INIS)

Wadman, W. III; Andrews, L.

1992-01-01

The Radiological Hazard Analysis (RHA) Manual provides a methodology and detailed guidance for systematic analysis of radiological hazards over a broad spectrum of program functions, housed in a wide variety of facilities. Radiological programs at LANL include: research and experimentation routine materials operations; production; non-destructive examination or testing; isotope and machine produced radiations; chemistry; and metallurgy. The RHA permits uniform evaluation of hazard types over a range of several orders of magnitude of hazard severity. The results are used to estimate risk, evaluate types and level of resource allocations, identify deficiencies, and plan corrective actions for safe working environments. (author)

Radiological health aspects of uranium milling

International Nuclear Information System (INIS)

Fisher, D.R.; Stoetzel, G.A.

1983-05-01

This report describes the operation of conventional and unconventional uranium milling processes, the potential for occupational exposure to ionizing radiation at the mill, methods for radiological safety, methods of evaluating occupational radiation exposures, and current government regulations for protecting workers and ensuring that standards for radiation protection are adhered to. In addition, a survey of current radiological health practices is summarized

Radiological health aspects of uranium milling

Energy Technology Data Exchange (ETDEWEB)

Fisher, D.R.; Stoetzel, G.A.

1983-05-01

This report describes the operation of conventional and unconventional uranium milling processes, the potential for occupational exposure to ionizing radiation at the mill, methods for radiological safety, methods of evaluating occupational radiation exposures, and current government regulations for protecting workers and ensuring that standards for radiation protection are adhered to. In addition, a survey of current radiological health practices is summarized.

Independent Commission for Radiological Protection and Nuclear Safety CIPRSN: Balance, obligations and future prospects

International Nuclear Information System (INIS)

Gieb, M.; Meruje, M. M; Sena Lino, A.

2010-01-01

This article summarizes the historical context of the regulatory situation in Portugal that led to the creation of the technical team of the Independent Commission for Radiological Protection and Nuclear Safety (CIPRSN), recalls its early works, and highlights the current work of some members of the team on the self-assessment of the national regulatory system of radiological protection and nuclear safety. The result of this self-assessment allows a detailed analysis of current problems and makes it possible to outline the future work plan of the technical team. It is hoped that this work may contribute to an improvement of the system, especially in view of new international and European legal instruments which are currently under implementation. (author)

Stockholm Safety Conference. Analysis of the sessions on radiological protection, licensing and risk assessment

International Nuclear Information System (INIS)

Gea, A.

1981-01-01

A summary of the sessions on radiological protection, licensing and risk assessment in the safety conference of Stockholm is presented. It is considered the new point of view of the nuclear safety, probabilistic analysis, components failures probability and accident analysis. They are included conclusions applicable in many cases to development countries. (author)

Evaluating the radiological health compliance of some beach ...

African Journals Online (AJOL)

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

UK legislation on radiological health and safety. Pt. 1

Energy Technology Data Exchange (ETDEWEB)

Evans, H D

1983-02-01

A brief survey is given of current UK legislation on radiological health and safety in areas in which ''Ionising Radiations Regulations 1982'' do not apply. Such areas in which separate Acts or Regulations for ionising radiations operate include: 1) Factories Act Regulations; 2) the disposal of radioactive wastes; 3) the transport of radioactive materials by air, sea, road, rail and post; 4) nuclear reactors and allied plants; 5) schools and further educational establishments and 6) research laboratories.

Automated system for the management of the radiological safety in a radiopharmaceutical and labelled compounds production center; Sistema automatizado para la gestion de la seguridad radiologica un centro de produccion de radiofarmacos y compuestos marcados

Energy Technology Data Exchange (ETDEWEB)

Amador B, Z.H. [Centro de Isotopos, Ave. Monumental y Carretera La Rada, Km. 3, Guanabacoa, Apartado 3415, Ciudad de La Habana (Cuba); Alvarez Builla de Sologuren, E. [Centro de Gestion de Informacion y Desarrollo de la Energia, Cale 20 No. 4111 e/47y 18A, Playa, Ciudad de La Habana (Cuba)]. e-mail: zabalbona@centis.edu.cu

2006-07-01

The establishment in the Center of Isotopes of Cuba of a managerial quality system in matter of radiological safety Y the accumulated operational experience, its constitute the foundations for the development of a system of management of the radiological safety organically structured, with the application of evaluative techniques of it management Y it integration in an automated system. The Visual Basic 5 platform for the programming of the 'SASR' system is used. The functions of each one of the 11 modules that integrate it are described. With this it can be carried out the registration of the data of the training Y the personnel's authorization, the checkup of the radioactive inventory of the installation, the annual upgrade of the registrations of the individual doses of those workers, the analysis of the state of the available equipment for magnitude to control, the radiological situation of the work positions, the public exposure by the gassy discharges, the experiences of the radiological events, the annual consolidation of the costs of the safety Y the evaluation of indicators Y of tendencies. A computer tool that facilitates the effective management of the radiological safety in a radioactive installation is obtained. (Author)

Computer program for storage of historical and routine safety data related to radiologically controlled facilities

International Nuclear Information System (INIS)

Marsh, D.A.; Hall, C.J.

1984-01-01

A method for tracking and quick retrieval of radiological status of radiation and industrial safety systems in an active or inactive facility has been developed. The system uses a mini computer, a graphics plotter, and mass storage devices. Software has been developed which allows input and storage of architectural details, radiological conditions such as exposure rates, current location of safety systems, and routine and historical information on exposure and contamination levels. A blue print size digitizer is used for input. The computer program retains facility floor plans in three dimensional arrays. The software accesses an eight pen color plotter for output. The plotter generates color plots of the floor plans and safety systems on 8 1/2 x 11 or 20 x 30 paper or on overhead transparencies for reports and presentations

Public Health Service Safety Program

Energy Technology Data Exchange (ETDEWEB)

McBride, J R [Southwestern Radiological Health Laboratory, Las Vegas, NV (United States)

1969-07-01

Off-Site Radiological Safety Programs conducted on past Plowshare experimental projects by the Southwestern Radiological Health Laboratory for the AEC will be presented. Emphasis will be placed on the evaluation of the potential radiation hazard to off-site residents, the development of an appropriate safety plan, pre- and post-shot surveillance activities, and the necessity for a comprehensive and continuing community relations program. In consideration of the possible wide use of nuclear explosives in industrial applications, a new approach to off-site radiological safety will be discussed. (author)

Public Health Service Safety Program

International Nuclear Information System (INIS)

McBride, J.R.

1969-01-01

Off-Site Radiological Safety Programs conducted on past Plowshare experimental projects by the Southwestern Radiological Health Laboratory for the AEC will be presented. Emphasis will be placed on the evaluation of the potential radiation hazard to off-site residents, the development of an appropriate safety plan, pre- and post-shot surveillance activities, and the necessity for a comprehensive and continuing community relations program. In consideration of the possible wide use of nuclear explosives in industrial applications, a new approach to off-site radiological safety will be discussed. (author)

The radiological safety in the petroleum industry. The behavior toward the prevention

International Nuclear Information System (INIS)

Adrian T, W.

2006-01-01

Inside the mark of the regulatory control it takes a preponderant place the control of sealed and open radioactive sources, in oil applications. In this task, the handling of the radioactive sources, the demand of the use of written procedures and the training, they are only some examples, of all those that conform the regulatory control. Among these topics they stand out a series of aspects divided in three big groups: operative radiological safety in the base, in the transport and in the task properly said. Given the great quantity of aspects that should be kept in mind, as well as the integration of all the control processes should be included strongly, aspects of safety and quality culture, and to introduce improvements as for the prevention refers, to correct deviations and remoteness that can be produced, avoiding like this, situations of radiological risk, emphasizing aspects of perception of the risk, training in attitudes, the implementation of audits and verifications of the safety level of the installation and the pursuit and control of the tasks that involve the manipulation of radioactive material, which are described in this work. (Author)

Occupational safety and health textbook for radiological personnel employed in structural material testing

International Nuclear Information System (INIS)

Abraham, J.

1981-01-01

The comprehensive textbook for X-ray and radiological testing personnel includes requirements and rules of occupational safety and health on the basis of Hungarian and international (mainly German) literature. In the chapter Fundamentals, X-ray and radioactive radiations, their measurements and biological effects, doses etc are described. In the chapter Occupational safety and health, the jobs representing radiation hazards are listed and safety regulations for them are reported. Finally, information for prevention and first aid is presented. Control questions are added to each part. The Appendix contains safety standards and regulations, information on legal aspects of safety and radiation protection as well as recommendations. (Sz.J.)

Use of the event tree method for evaluate the safety of radioactive facilities

International Nuclear Information System (INIS)

Hernandez S, A.; Cornejo D, N.; Callis F, E.

2006-01-01

The work shows the validity of the use of Trees of Events like a quantitative method appropriate to carry out evaluations of radiological safety. Its were took like base the evaluations of safety of five Radiotherapy Departments, carried out in the mark of the process of authorization of these facilities. The risk values were obtained by means of the combination of the probabilities of occurrence of the events with its consequences. The use of the method allowed to suggest improvements to the existent safety systems, as well as to confirm that the current regulator requirements for this type of facilities to lead to practices with acceptable risk levels. (Author)

Radiological safety status and quality assurance audit of medical X-ray diagnostic installations in India.

Science.gov (United States)

Sonawane, A U; Singh, Meghraj; Sunil Kumar, J V K; Kulkarni, Arti; Shirva, V K; Pradhan, A S

2010-10-01

We conducted a radiological safety and quality assurance (QA) audit of 118 medical X-ray diagnostic machines installed in 45 major hospitals in India. The main objective of the audit was to verify compliance with the regulatory requirements stipulated by the national regulatory body. The audit mainly covered accuracy check of accelerating potential (kVp), linearity of tube current (mA station) and timer, congruence of radiation and optical field, and total filtration; in addition, we also reviewed medical X-ray diagnostic installations with reference to room layout of X-ray machines and conduct of radiological protection survey. A QA kit consisting of a kVp Test-O-Meter (ToM) (Model RAD/FLU-9001), dose Test-O-Meter (ToM) (Model 6001), ionization chamber-based radiation survey meter model Gun Monitor and other standard accessories were used for the required measurements. The important areas where there was noncompliance with the national safety code were: inaccuracy of kVp calibration (23%), lack of congruence of radiation and optical field (23%), nonlinearity of mA station (16%) and timer (9%), improper collimator/diaphragm (19.6%), faulty adjustor knob for alignment of field size (4%), nonavailability of warning light (red light) at the entrance of the X-ray room (29%), and use of mobile protective barriers without lead glass viewing window (14%). The present study on the radiological safety status of diagnostic X-ray installations may be a reasonably good representation of the situation in the country as a whole. The study contributes significantly to the improvement of radiological safety by the way of the steps already taken and by providing a vital feed back to the national regulatory body.

Radiological safety status and quality assurance audit of medical X-ray diagnostic installations in India

International Nuclear Information System (INIS)

Sonawane, A.U.; Singh, Meghraj; Sunil Kumar, J.V.K.; Kulkarni, Arti; Shirva, V.K.; Pradhan, A.S.

2010-01-01

We conducted a radiological safety and quality assurance (QA) audit of 118 medical X-ray diagnostic machines installed in 45 major hospitals in India. The main objective of the audit was to verify compliance with the regulatory requirements stipulated by the national regulatory body. The audit mainly covered accuracy check of accelerating potential (kVp), linearity of tube current (mA station) and timer, congruence of radiation and optical field, and total filtration; in addition, we also reviewed medical X-ray diagnostic installations with reference to room layout of X-ray machines and conduct of radiological protection survey. A QA kit consisting of a kVp Test-O-Meter (ToM) (Model RAD/FLU-9001), dose Test-O-Meter (ToM) (Model 6001), ionization chamber-based radiation survey meter model Gun Monitor and other standard accessories were used for the required measurements. The important areas where there was noncompliance with the national safety code were: inaccuracy of kVp calibration (23%), lack of congruence of radiation and optical field (23%), nonlinearity of mA station (16%) and timer (9%), improper collimator/diaphragm (19.6%), faulty adjustor knob for alignment of field size (4%), nonavailability of warning light (red light) at the entrance of the X-ray room (29%), and use of mobile protective barriers without lead glass viewing window (14%). The present study on the radiological safety status of diagnostic X-ray installations may be a reasonably good representation of the situation in the country as a whole. The study contributes significantly to the improvement of radiological safety by the way of the steps already taken and by providing a vital feed back to the national regulatory body. (author)

Course of radiological protection and safety in the medical diagnostic with X-rays

International Nuclear Information System (INIS)

Dominguez A, C.E.

1997-01-01

The obtention of images of human body to the medical diagnostic is one of the more old and generalized applications for X-ray. Therefore the design and performance of equipment and installations as well as the operation procedures must be oriented toward safety with the purpose to guarantee this radiological practice will bring a net positive benefit to the society. Given that in Mexico only exists the standardization related to source and equipment generators of ionizing radiation in the industrial area and medical therapy, but not so to the medical diagnostic area it is the purpose of this work to present those standards related with this application branch. Also it is presented the preparation of a manual for the course named Formation of teachers in radiological protection and safety in the X-ray medical diagnostic in 1997 which was imparted at ININ. (Author)

Patient exposure evaluation in Romanian radiological departments

International Nuclear Information System (INIS)

Girjoaba, O.; Cucu, A.

2012-01-01

Purpose: A nation-wide evaluation of ionizing radiation exposure of the Romanian population due to the radiological examinations is performed in accordance with European Directive 97/43 EURATOM implemented in national regulations. Method: The study is applied to the collected data from radiological departments from Romanian hospitals during 2010. The radiological examinations were grouped in three categories: conventional diagnostic radiology, interventional radiology and computed tomography. The annual collective dose was determined from the reported data about the mean effective doses and the frequency for each type of radiological examination, in conformity with the national regulations. Regarding the frequency aspects, the results include the age and gender distributions. Major results: More then 6 million radiological examinations were performed in 2010, Romania having a population about of 20.3 million inhabitants. The collective effective dose for 2010 resulted from the study is 152 mSv per 1000 inhabitants. Conclusions: Medical practitioners must select the best medical imaging investigation for each clinical case taking into account the importance of keeping the patient dose as low as possible. Medical physicists should be strongly involved in the establishing of the dosimetry procedures. (author)

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

International Nuclear Information System (INIS)

Baca, T.E.

1983-02-01

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

Study on development of education model and its evaluation system for radiation safety

CERN Document Server

Seo, K W; Nam, Y M

2002-01-01

As one of the detailed action strategy of multi object preparedness for strengthening of radiation safety management by MOST, this project was performed, in order to promote the safety culture for user and radiation worker through effective education program. For the prevention of radiological accident and effective implementation of radiation safety education and training, this project has been carried out the development of education model and its evaluation system on radiation safety. In the development of new education model, education course was classified; new and old radiation worker, temporary worker, lecturer and manager. The education model includes the contents of expanding the education opportunity and workplace training. In the development of evaluation system, the recognition criteria for commission-education institute and inside-education institute which should establish by law were suggested for evaluation program. The recognition criteria contains classification, student, method, facilities, ...

Evidence-based radiology: a new approach to evaluate the clinical practice of radiology

International Nuclear Information System (INIS)

Puig, S.; Felder-Puig, R.

2006-01-01

Over the last several years, the concept and methodology of evidence-based medicine (EBM) have received significant attention in the scientific community. However, compared to therapeutic medical disciplines, EBM-based radiological publications are still underrepresented. This article summarizes the principles of EBM and discusses the possibilities of their application in radiology. The presented topics include the critical appraisal of studies on the basis on EBM principles, the explanation of EBM-relevant statistical outcome parameters (e.g., ''likelihood ratio'' for diagnostic and ''number needed to treat'' for interventional procedures), as well as the problems facing evidence-based radiology. Evidence-based evaluation of radiological procedures does not only address aspects of cost-effectiveness, but is also particularly helpful in identifying patient-specific usefulness. Therefore it should become an integral part of radiologist training. (orig.)

Radiological safety status and quality assurance audit of medical X-ray diagnostic installations in India

Directory of Open Access Journals (Sweden)

Sonawane A

2010-01-01

Full Text Available We conducted a radiological safety and quality assurance (QA audit of 118 medical X-ray diagnostic machines installed in 45 major hospitals in India. The main objective of the audit was to verify compliance with the regulatory requirements stipulated by the national regulatory body. The audit mainly covered accuracy check of accelerating potential (kVp, linearity of tube current (mA station and timer, congruence of radiation and optical field, and total filtration; in addition, we also reviewed medical X-ray diagnostic installations with reference to room layout of X-ray machines and conduct of radiological protection survey. A QA kit consisting of a kVp Test-O-Meter (ToM (Model RAD/FLU-9001, dose Test-O-Meter (ToM (Model 6001, ionization chamber-based radiation survey meter model Gun Monitor and other standard accessories were used for the required measurements. The important areas where there was noncompliance with the national safety code were: inaccuracy of kVp calibration (23%, lack of congruence of radiation and optical field (23%, nonlinearity of mA station (16% and timer (9%, improper collimator/diaphragm (19.6%, faulty adjustor knob for alignment of field size (4%, nonavailability of warning light (red light at the entrance of the X-ray room (29%, and use of mobile protective barriers without lead glass viewing window (14%. The present study on the radiological safety status of diagnostic X-ray installations may be a reasonably good representation of the situation in the country as a whole. The study contributes significantly to the improvement of radiological safety by the way of the steps already taken and by providing a vital feed back to the national regulatory body.

Radiologic evaluation of os odontoideum

Energy Technology Data Exchange (ETDEWEB)

Lee, Eun Ju; Chung, Tae Sub; Suh, Jung Ho; Kim, Dong Ik; Kim, Yong Soo; Park, Hyoung Chun; Oh, Soung Hoon [Yonsei University College of Medicine, Seoul (Korea, Republic of)

1988-10-15

We took an analysis on the clinical and radiologic findings of os odontoideum, which had been regarded as relatively uncommon disease, on 5 patients whom we have recently experienced. Our results were as follows: 1. Os odontoideums were incidentally discovered during the radiologic evaluation of traumatised 4 cases, who had been well being. Another one case of os odontoideum was associated with multiple epiphyseal dysplasia. 2. General radiologic findings of os odontoideum were a round or oval and hypoplastic ossicle separated from the base of odontoid process by wise gap. 3. Alanto-Axial instability was developed in 5 cases of os odontoideum by flexion and extension stress view of lateral cervical spine. 4. Flexion views of lateral cervical spine showed narrowing of anteroposterior diameter of spinal canal which were available at atlantoaxial level on 5 cases of os odontoidum. 5. CT myelogram and cervical myelogram showed anteriorly compressed dural sac and deformed spinal cord by body of axis at the atlanto-axial level.

Proposed risk evaluation guidelines for use by the DOE-AL Nuclear Explosive Safety Division in evaluating proposed shipments of nuclear components

International Nuclear Information System (INIS)

Just, R.A.; Love, A.F.

1997-10-01

The licensing requirements of 10 CFR 71 (US Code of Federal Regulations) are the primary criteria used to license proposed US Department of Energy (DOE) shipments of nuclear components. However, if a shipment cannot meet 10 CFR 71 requirements, a Transportation System Risk Assessment (TSRA) is prepared to document: (1) the degree of compliance of proposed DOE shipments of nuclear components with applicable federal regulations, and (2) the risk associated with the proposed shipments. The Nuclear Explosive Safety Division (NESD) of the Department of Energy, Albuquerque Area Office (DOE-AL) is responsible for evaluating TSRAs and for preparing Safety Evaluation Reports (SERs) to authorize the off-site transport. Hazards associated with the transport may include the presence of fissile material, chemically and radiologically toxic uranium, and ionizing radiation. The Nuclear Regulatory Commission (NRC) has historically considered only radiological hazards in licensing the transport of radiological material because the US Department of Transportation considers licensing requirements of nonradiological (i.e., chemically toxic) hazards. The requirements of 10 CFR 71 are based primarily on consideration of radiological hazards. For completeness, this report provides information for assessing the effects of chemical toxicity. Evaluating the degree of compliance with the requirements of 10 CFR 71 is relatively straightforward. However, there are few precedents associated with developing TSRA risk assessments for packages that do not comply with all of the requirements of 10 CFR 71. The objective of the task is to develop Risk Evaluation Guidelines for DOE-AL to use when evaluating a TSRA. If the TSRA shows that the Risk Evaluation Guidelines are not exceeded, then from a risk perspective the TSRA should be approved if there is evidence that the ALARA (as low as reasonably achievable) principle has been applied

Advance of the National Program of Radiological Protection and Safety for medical diagnostic with X-rays

International Nuclear Information System (INIS)

Verdejo S, M.

1999-01-01

The National Program of Radiological Protection and Safety for medical diagnostic with X-ray (Programa Nacional de Proteccion y Seguridad Radiologica para diagnostico medico con rayos X) was initiated in the General Direction of Environmental Health (Direccion General de Salud Ambiental) in 1995. Task coordinated with different dependences of the Public Sector in collaboration between the Secretary of Health (Secretaria de Salud), the National Commission of Nuclear Safety and Safeguards (Comision Nacional de Seguridad Nuclear y Salvaguardias) and, the National Institute of Nuclear Research (Instituto Nacional de Investigaciones Nucleares). The surveillance to the fulfilment of the standardization in matter of Radiological Protection and Safety in the medical diagnostic with X-rays has been obtained for an important advance in the Public sector and it has been arousing interest in the Private sector. (Author)

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

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

Evaluation of radiological detriment from negative radiological examinations

International Nuclear Information System (INIS)

Frometa Suarez, I.; Jerez Vergueria, S.F.

1997-01-01

The individul doses of radiation due to diagnostic radiology are usually low, though their contribution to the collective dose is very important given the large numbers of people exposed to these. This paper presents an analysis of the number of negative radiologiacl examinations in a major Cuban Hospital, and their contribution to the collective dose, and radiation organ and tissue, effective (expressed as severe hereditary effect and the occurrence of fatal and non fatal cancers) are all evaluated. The negative findings constitute 41 % of all examinations. The total contribution of negative examinations to the collective dose is very important given the large numbers of people exposed to these. This papaer presents an analysis of the number of negative radiological examinations in major Cuban Hospital, and their contribution to the collective dose of radiation. The absorbed dose by irradiation organ and tissue, effective dose equivalent, collective dose, and radiation risk (expressed as severe herditary effect and the occureence of fatal and non fatal cancers) are all evaluated. The negative findings constitute 41% of all examinations. The total contribution of negative examinations. The total contribution of negative examinations to the collective dose are found to make up 52.9 %: 11.35 Sv-man in the studied population

The Radiological Safety Analysis Computer Program (RSAC-5) user's manual

International Nuclear Information System (INIS)

Wenzel, D.R.

1994-02-01

The Radiological Safety Analysis Computer Program (RSAC-5) calculates the consequences of the release of radionuclides to the atmosphere. Using a personal computer, a user can generate a fission product inventory from either reactor operating history or nuclear criticalities. RSAC-5 models the effects of high-efficiency particulate air filters or other cleanup systems and calculates decay and ingrowth during transport through processes, facilities, and the environment. Doses are calculated through the inhalation, immersion, ground surface, and ingestion pathways. RSAC+, a menu-driven companion program to RSAC-5, assists users in creating and running RSAC-5 input files. This user's manual contains the mathematical models and operating instructions for RSAC-5 and RSAC+. Instructions, screens, and examples are provided to guide the user through the functions provided by RSAC-5 and RSAC+. These programs are designed for users who are familiar with radiological dose assessment methods

Chemical Hazards and Safety Issues in Fusion Safety Design

International Nuclear Information System (INIS)

Cadwallader, L.C.

2003-01-01

Radiological inventory releases have dominated accident consequences for fusion; these consequences are important to analyze and are generally the most severe result of a fusion facility accident event. However, the advent of, or plan for, large-scale usage of some toxic materials poses the additional hazard of chemical exposure from an accident event. Examples of toxic chemicals are beryllium for magnetic fusion and fluorine for laser fusion. Therefore, chemical exposure consequences must also be addressed in fusion safety assessment. This paper provides guidance for fusion safety analysis. US Department of Energy (DOE) chemical safety assessment practices for workers and the public are reviewed. The US Environmental Protection Agency (EPA) has published some guidance on public exposure to releases of mixtures of chemicals, this guidance has been used to create an initial guideline for treating mixed radiological and toxicological releases in fusion; for example, tritiated hazardous dust from a tokamak vacuum vessel. There is no convenient means to judge the hazard severity of exposure to mixed materials. The chemical fate of mixed material constituents must be reviewed to determine if there is a separate or combined radiological and toxicological carcinogenesis, or if other health threats exist with radiological carcinogenesis. Recommendations are made for fusion facility chemical safety evaluation and safety guidance for protecting the public from chemical releases, since such levels are not specifically identified in the DOE fusion safety standard

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)

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)

RASCAL 4.l: evaluation system for the analysis of the radiological consequences

International Nuclear Information System (INIS)

Miguel, I. de; Gomez-Arguello, B.

2012-01-01

Recently the Spanish Nuclear Safety Council (CSN) has promoted the replacement of the code used in the Spanish Nuclear Power Plants to estimate potential and actual doses due to atmospheric releases. IRDAM Code (interactive Rapid Dose Assessment Model, 1983) by RASCAL Code version 4.1 (Radiological Assessment System for consequence Analysis). This code was developed by the NRC (Nuclear Regulatory Commission) to evaluate releases from nuclear power plants, spent fuel storage pools and casks, fuel cycle facilities and radioactive material handling facilities. RASCAL was officially requested to the Spanish nuclear power plants in February 1st, 2012, and it can be used for external dose assessment and to evaluate the recommended protective action for the public in a specific situation (sheltering, prophylaxis, evacuation, etc.). (Author)

Specialized consulting in radiological safety to the North Central Hospital of high specialty, PEMEX. V. November of 2001

International Nuclear Information System (INIS)

Angeles C, A.; Vizuet G, J.; Benitez S, J. A.; Garcia A, J.; Rodriguez A, F.

2002-01-01

It is a report of a specialized consulting in radiological safety that to be carried the ININ to PEMEX for the North Central Hospital of High Specialty, to maintain the sanitary license for the use of X ray equipment of medical diagnostic, and guarantee these services with a program of quality assurance. To give fulfilment to that requests it is programmed a technical assistance monthly, with reports of results during the development of the service. In this document it is carried a report of the advances and results in the month of November of the 2001, where the following documents are analyzed: Manual of radiological safety, program of quality assurance, operation procedures, procedure of maintenance team, procedure of medical radiological control of the specialized personnel; also are annotate the obtained results and their observations. (Author)

Specialized consulting in radiological safety to the south central hospital of high specialty, PEMEX. VI. December of 2001

International Nuclear Information System (INIS)

Angeles C, A.; Vizuet G, J.; Benitez S, J.A.; Garcia A, J.; Rodriguez A, F.

2002-01-01

It is a report of a specialized consulting in radiological safety that to be carried the ININ to PEMEX for the South Central Hospital of High Specialty, to maintain the sanitary license for the use of X-ray equipment of medical diagnostic, and guarantee these services with a program of quality assurance. To give fulfilment to that requests it is programmed a technical assistance monthly, with reports of results during the development of the service. In this document it is carried a report of the advances and results in the month of december of the 2001, where the following documents are analyzed: Manual of radiological safety, program of quality assurance, operation procedures, procedure of maintenance team, procedure of medical radiological control of the specialized personnel; also are annotate the obtained results and their observations. (Author)

Safety requirements and radiological protection for ore installations

International Nuclear Information System (INIS)

2003-06-01

This norm establishes the safety and radiological protection requirements for mining installations which manipulates, process and storing ores, raw materials, steriles, slags and wastes containing radionuclides of the uranium and thorium natural series, simultaneously or separated, and which can cause undue exposures to the public and workers, at anytime of the functioning or pos operational stage. This norm applies to the mining installations activities, suspended or which have ceased their activities before the issue date of this norm, destined to the mining, physical, chemical and metallurgical processing, and the industrialization of raw materials and residues containing associated radionuclides from the natural series of uranium and thorium, including the stages of implantation, operation and decommissioning of the installation

Radiological/toxicological sabotage assessments at the Savannah River Site

International Nuclear Information System (INIS)

Johnson, H.D.; Pascal, M.D.; Richardson, D.L.

1995-01-01

This paper describes the methods being employed by Westinghouse Savannah River Company (WSRC) to perform graded assessments of radiological and toxicological sabotage vulnerability at Savannah River Site (SRS) facilities. These assessments are conducted to ensure that effective measures are in place to prevent, mitigate, and respond to a potential sabotage event which may cause an airborne release of radiological/toxicological material, causing an adverse effect on the health and safety of employees, the public, and the environment. Department of Energy (DOE) Notice 5630.3A, open-quotes Protection of Departmental Facilities Against Radiological and Toxicological Sabotage,close quotes and the associated April 1993 DOE-Headquarters guidance provide the requirements and outline an eight-step process for hazardous material evaluation. The process requires the integration of information from a variety of disciplines, including safety, safeguards and security, and emergency preparedness. This paper summarizes WSRC's approach towards implementation of the DOE requirements, and explains the inter-relationships between the Radiological and Toxicological Assessments developed using this process, and facility Hazard Assessment Reports (HAs), Safety Analysis Reports (SARs), and Facility Vulnerability Assessments (VAs)

Toxicological and radiological safety of chicken meat irradiated with 7.5 MeV X-rays

Science.gov (United States)

Song, Beom-Seok; Lee, Yunjong; Park, Jong-Heum; Kim, Jae-Kyung; Park, Ha-Young; Kim, Dong-Ho; Kim, Chang-Jong; Kang, Il-Jun

2018-03-01

This study was conducted to evaluate the toxicological and radiological safety of chicken meat that had been irradiated at 30 kGy with 7.5 MeV X-rays. In a sub-chronic toxicity study, ICR mice were fed X-ray-irradiated chicken meat at 2500 mg/kg body weight daily for 90 days, and no mortality or abnormal clinical signs were observed throughout the study period. However, several hematological and serum biochemical parameters of the ICR mice differed significantly from those in the control group; nevertheless, the observed values were all within the normal range for the respective parameters. In addition, no toxicological effects were determined in male or female mice. Furthermore, no differences in gamma-ray spectrometric patterns were detected between the non-irradiated and irradiated samples, indicating that the radioactivity induced by 7.5 MeV X-ray irradiation was below the detection limit. These results tentatively suggest that chicken meat irradiated with 7.5 MeV X-rays would be safe for human consumption in terms of toxicology and radiology.

Preparation, Conduct and Evaluation of Exercises to Test Preparedness for a Nuclear or Radiological Emergency

International Nuclear Information System (INIS)

2010-01-01

The aim of this publication is to serve as a practical tool for the preparation, conduct and evaluation of exercises to test preparedness for response to a nuclear or radiological emergency. It fulfils in part the functions assigned to the IAEA under Article 5.a(ii) of the Convention on Assistance in Case of a Nuclear Accident or Radiological Emergency (Assistance Convention), namely, to collect and disseminate to States Parties and Member States information concerning the methodologies, techniques and available results of research on such emergencies. To ensure effective response to radiation emergencies when needed, provisions should be made for regular training of emergency response personnel. As stated in Preparedness and Response for a Nuclear or Radiological Emergency (Safety Requirements, Safety Standard Series No. GS-R-2), 'The operator and the response organizations shall make arrangements for the selection of personnel and training to ensure that the personnel have the requisite knowledge, skills, abilities, equipment, procedures and other arrangements to perform their assigned response functions'. A further requirement is that 'Exercise programmes shall be conducted to ensure that all specified functions required to be performed for emergency response and all organizational interfaces for facilities in threat category I, II or III and the national level programmes for threat category IV or V are tested at suitable intervals'. In 2004 the IAEA General Conference, in resolution GC(48)/RES/10 encouraged Member States to 'implement the Safety Requirements for Preparedness and Response to a Nuclear or Radiological Emergency'. This document is published as part of the IAEA Emergency Preparedness and Response Series to assist in meeting these requirements and to fulfil Article 5 of the Assistance Convention. It was developed based on a number of assumptions about national and local capabilities. Therefore, the exercise structure, terms and scenarios must be

Annual Report 1998 concerning the nuclear safety and radiological protection in the Swiss nuclear installations

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-05-01

The report presents detailed information about the nuclear safety and radiological protection in the Swiss nuclear power plants, the central interim storage at Wuerenlingen, the Paul Scherrer Institute (PSI) and other nuclear installations in Switzerland.

Annual Report 1998 concerning the nuclear safety and radiological protection in the Swiss nuclear installations

International Nuclear Information System (INIS)

1999-05-01

The report presents detailed information about the nuclear safety and radiological protection in the Swiss nuclear power plants, the central interim storage at Wuerenlingen, the Paul Scherrer Institute (PSI) and other nuclear installations in Switzerland

Annual Report 1999 concerning the nuclear safety and radiological protection in the Swiss nuclear installations

International Nuclear Information System (INIS)

2000-08-01

The report presents detailed information about the nuclear safety and radiological protection in the Swiss nuclear power plants, the central interim storage at Wuerenlingen, the Paul Scherrer Institute (PSI) and other nuclear installations in Switzerland

Annual Report 1999 concerning the nuclear safety and radiological protection in the Swiss nuclear installations

Energy Technology Data Exchange (ETDEWEB)

NONE

2000-08-15

The report presents detailed information about the nuclear safety and radiological protection in the Swiss nuclear power plants, the central interim storage at Wuerenlingen, the Paul Scherrer Institute (PSI) and other nuclear installations in Switzerland.

Verification of implementation of the radiological safety standards through the regulatory inspections

International Nuclear Information System (INIS)

Perez Gonzalez, Francisco; Fornet Rodriguez, Ofelia M.

2008-01-01

Full text: As an element of the updating process of the legal framework on radiological safety in Cuba, a new rule was put into force; the Radiological Basic Safety Standards (RBSS) in January 2002. Five years after the application of these new safety requirements, it was considered appropriate to assess the effectiveness of its implementation. Therefore, in this work the authors analysed the outcomes of the regulatory inspections conducted in this period upon medical and industrial practices in a sample of facilities representative of those with the highest radiological risks in the territory under supervision of a Territorial Delegation of the Nuclear Regulatory Authority. For better understanding of this presentation, a summary explanation of the structure of the rule is given in its introduction. The work was to identify for each deficiency, or finding, or counter-measure; out of the relevant inspections; the corresponding requirement/Article of the RBSS that shows difficulties in implementation. For each installation an analysis is made with regard to the relevant articles difficult to implement. Finally, the appraisal is shown separately for the medical practice, and for the industrial practice, and also in general for the whole sample of installations under review. The study showed that the implementation of the Standards has been satisfactory and uniform in the practices under review. So far it seems that there have not been major difficulties with the implementation of the Titles; III On Intervention, IV Dose Limits, as well as with the Especial, Final, and Transitory Dispositions. On the other hand, it is shown there is a need for continued work only with regard to the implementation of the requirements in Section IV Verification of Safety and in Section V On the responsibilities with regard to occupational exposure in Chapter III Title I, and correspondingly in Chapter II Occupational Exposure in Title II. It is recommended to conduct this kind of

Radiology education. The evaluation and assessment of clinical competence

International Nuclear Information System (INIS)

Hibbert, Kathryn M.; Van Deven, Teresa; Chhem, Rethy K.; Nagasaki Univ.; Wang, Shih-chang; Royal Australian and New Zealand College of Radiologists, Sydney

2012-01-01

Third volume of a trilogy devoted to radiology education and improvement of medical imaging students' learning, teaching, and scholarship. Reviews the philosophies, theories, and principles that underpin assessment and evaluation in radiology education. Includes a series of rich case studies. Written by an international group of experienced educators and medical professionals. This book reviews the philosophies, theories, and principles that underpin assessment and evaluation in radiology education, highlighting emerging practices and work done in the field. The sometimes conflicting assessment and evaluation needs of accreditation bodies, academic programs, trainees, and patients are carefully considered. The final section of the book examines assessment and evaluation in practice, through the development of rich case studies reflecting the implementation of a variety of approaches. This is the third book in a trilogy devoted to the scholarship of radiology education and is the culmination of an important initiative to improve medical imaging students' learning, teaching, and scholarship by bringing together experienced educators and medical professionals. The previous two books focused on the culture and the learning organizations in which our future radiologists are educated and on the application of educational principles in the education of radiologists. Here, the trilogy comes full circle: attending to the assessment and evaluation of the education of its members has much to offer back to the learning of the organization.

Neutronic Analysis and Radiological Safety of RSG-GAS Reactor on 300 Grams Uranium Silicide Core

International Nuclear Information System (INIS)

Pande Made Udiyani; Lily Suparlina; Rokhmadi

2007-01-01

As starting of usage silicide U 250 g fuel element in the core of RSG-GAS and will be continued with usage of silicide U 300 g fuel element, hence done beforehand neutronic analyse and radiological safety of RSG-GAS. Calculation done by ORIGEN2.1 code to calculate source term, and also by PC-COSYMA code to calculate radiological safety of radioactive dispersion from RSG-GAS. Calculation of radioactive dispersion done at condition of reactor is postulated be happened an accident of LOCA causing one fuel element to melt. Neutronic analysis indicate that silicide U 250 g full core shall to be operated beforehand during 625 MWD before converted to silicide U 300 g core. During operation of transition core with mixture of silicide U 250 g and 300 g, all parameter fulfill criterion of safety Designed Balance core of silicide U 300 g will be reached at the time of fifth full core. Result of calculation indicate that through mixture core of silicide U 250 and 300 g proposed can form silicide U 300 g balance core of reactor RSG-GAS safely. Calculation of radiology safety by deterministic for silicide U 300 g balance core, and accident postulation which is equal to core of silicide U 250 g yield output in the form of radiation activity (radionuclide concentration in the air and deposition on the ground), radiation dose (collective and individual), radiation effect (short- and long-range), which accepted by society in each perceived sector. Result of calculation indicated that dose accepted by society is not pass permitted boundary for public society if happened accident. (author)

Space nuclear reactor safety

International Nuclear Information System (INIS)

Damon, D.; Temme, M.; Brown, N.

1990-01-01

Definition of safety requirements and design features of the SP-100 space reactor power system has been guided by a mission risk analysis. The analysis quantifies risk from accidental radiological consequences for a reference mission. Results show that the radiological risk from a space reactor can be made very low. The total mission risk from radiological consequences for a shuttle-launched, earth orbit SP-100 mission is estimated to be 0.05 Person-REM (expected values) based on a 1 mREM/yr de Minimus dose. Results are given for each mission phase. The safety benefits of specific design features are evaluated through risk sensitivity analyses

Annual report 1996 concerning the nuclear safety and radiological protection in the Swiss nuclear installations

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-05-01

The report presents detailed information about the nuclear safety and radiological protection in the Swiss nuclear power plants, the central interim storage at Wuerenlingen, the Paul Scherrer Institute (PSI) and other nuclear installations in Switzerland. figs., tabs., refs.

Annual report 1996 concerning the nuclear safety and radiological protection in the Swiss nuclear installations

International Nuclear Information System (INIS)

1997-05-01

The report presents detailed information about the nuclear safety and radiological protection in the Swiss nuclear power plants, the central interim storage at Wuerenlingen, the Paul Scherrer Institute (PSI) and other nuclear installations in Switzerland. figs., tabs., refs

Report of radiological safety for a micro PET

International Nuclear Information System (INIS)

Gallegos M, R.; Ruiz T, C. G.; Martinez D, A.; Rodriguez V, M.

2010-09-01

Considering one of the guides emitted by the National Commission of Nuclear Security and Safeguards, was realized the report of radiological safety for a micro tomography by positrons emission that is part of Bimodal System of Images developed in their entirety for personnel of the Physics Institute of UNAM. With this system is sought to obtain tomography images of small animals using non destructive methods, such as computerized micro tomography and micro tomography by positrons emission. In this work each one of the report points is enumerated and only it is described, to big features on that consist, due to the great extension of each one of them. The report has two parts; the first is denominated -Of the installation and the Organization- and is given to know the interior and external characteristics of the installation, besides how and under which authority the activities will be executed inside the laboratory. The second part is called -of the Radiological Protection- and has for objective to describe the radiation sources that will be used, as well as the measures of radiological protection foreseen inside the laboratory. The most important part in the report consists on the description of the three radionuclides to use: 18 F, 11 C and 13 N, as well as the methods for the shielding calculation and for the estimate of the dose equivalent during the normal operation of the equipment. These methods were applied three times, because the calculation was made for each radionuclide. The results of these calculations show that: 1) it not is necessary to have a structural shielding, due to the activity sources very reduced, and 2) the dose limit per year (according to the ICRP-60) it will not be surpassed neither in the case of the occupationally exposed personnel, neither on the public in general. (Author

Radiological protection, safety and security issues in the industrial and medical applications of radiation sources

International Nuclear Information System (INIS)

Vaz, Pedro

2015-01-01

The use of radiation sources, namely radioactive sealed or unsealed sources and particle accelerators and beams is ubiquitous in the industrial and medical applications of ionizing radiation. Besides radiological protection of the workers, members of the public and patients in routine situations, the use of radiation sources involves several aspects associated to the mitigation of radiological or nuclear accidents and associated emergency situations. On the other hand, during the last decade security issues became burning issues due to the potential malevolent uses of radioactive sources for the perpetration of terrorist acts using RDD (Radiological Dispersal Devices), RED (Radiation Exposure Devices) or IND (Improvised Nuclear Devices). A stringent set of international legally and non-legally binding instruments, regulations, conventions and treaties regulate nowadays the use of radioactive sources. In this paper, a review of the radiological protection issues associated to the use of radiation sources in the industrial and medical applications of ionizing radiation is performed. The associated radiation safety issues and the prevention and mitigation of incidents and accidents are discussed. A comprehensive discussion of the security issues associated to the global use of radiation sources for the aforementioned applications and the inherent radiation detection requirements will be presented. Scientific, technical, legal, ethical, socio-economic issues are put forward and discussed. - Highlights: • The hazards associated to the use of radioactive sources must be taken into account. • Security issues are of paramount importance in the use of radioactive sources. • Radiation sources can be used to perpetrate terrorist acts (RDDs, INDs, REDs). • DSRS and orphan sources trigger radiological protection, safety and security concerns. • Regulatory control, from cradle to grave, of radioactive sources is mandatory.

Proceedings of the 4. National Congress of the Mexican Society of Radiological Safety C.A

International Nuclear Information System (INIS)

1991-01-01

In these sessions it had the participation of personalities of diverse internationally grateful organizations, with exhibitions about the situation of the nuclear industry of power, the applications of the radiations and the radiological safety in the international context. Also its were presented works about Emergency plans in Nuclear facilities and plants, Nuclear medicine, Food processing, Thermal neutrons, Neutron dosimetry, Charged particles, Thermoluminescence, Industrial radiography, Radiation monitoring, all of them with the participation of specialists with international prestige. The 41 works that are presented in the technical sessions come from Spanish, Brazilian, Greek and Mexican grateful institutions. All they are a sample of the intense activity in investigation and development in the areas of the nuclear industry as of the radiological safety. This congress reveals the impulse that the nuclear community grants to the formation of human resources

Preclosure radiological safety analysis for accident conditions of the potential Yucca Mountain Repository: Underground facilities

International Nuclear Information System (INIS)

Ma, C.W.; Sit, R.C.; Zavoshy, S.J.; Jardine, L.J.; Laub, T.W.

1992-06-01

This preliminary preclosure radiological safety analysis assesses the scenarios, probabilities, and potential radiological consequences associated with postulated accidents in the underground facility of the potential Yucca Mountain repository. The analysis follows a probabilistic-risk-assessment approach. Twenty-one event trees resulting in 129 accident scenarios are developed. Most of the scenarios have estimated annual probabilities ranging from 10 -11 /yr to 10 -5 /yr. The study identifies 33 scenarios that could result in offsite doses over 50 mrem and that have annual probabilities greater than 10 -9 /yr. The largest offsite dose is calculated to be 220 mrem, which is less than the 500 mrem value used to define items important to safety in 10 CFR 60. The study does not address an estimate of uncertainties, therefore conclusions or decisions made as a result of this report should be made with caution

Radiological safety in extraction of rare earths in India: regulatory control

International Nuclear Information System (INIS)

Sinha, S.; Bhattacharya, R.

2011-01-01

The term 'rare earths' refers to a group of f-block elements in the periodic table including those with atomic numbers 57 (Lanthanum) to 71 (Lutetium), as well as the transition metals Yttrium (39) and Scandium (21). Economically extractable concentrations of rare earths are found in minerals such as monazite, bastnaesite, cerites, xenotime etc. Of these, monazite forms the main source for rare earths in India, which along with other heavy minerals is found abundantly in the coastal beach sands. However, in addition to rare earths, monazite also contains 0.35% U 3 O 8 and 8-9% ThO 2 . Hence, extraction of rare earths involves chemical separation of the rare earths from thorium and uranium which are radioactive. The processing and extraction of rare earths from monazite therefore invariably results in occupational radiation exposure to the workers involved in these operations. In addition, in the process of removal of radioactivity from rare earths, radioactive solid waste gets generated which has 2 2 8Ra concentration in the range 2000-5000 Bq/g. Unregulated disposal of such high active waste would not only result in contamination of the soil but the radionuclides would eventually enter the food chain and lead to internal exposure of the general public. Therefore such facilities involved in recovery of rare earths from monazite attract the provisions of radiological safety regulations. Atomic Energy Regulatory Board of India has been enforcing the provisions of The Atomic Energy (Radiation Protection) Rules, 2004 and The Atomic Energy (Safe Disposal of Radioactive Waste) Rules, 1987 in these facilities. This paper shall discuss the associated radiological hazard involved in recovery of rare earths from monazite. It shall also highlight the regulatory requirements for controlling the occupational exposure of workers during design stage such as requirements on lay out of the building, ventilation, containment of radioactivity, etc and also the during operational

Present status of education for radiation safety during clinical examinations and the role of the radiological technologist

International Nuclear Information System (INIS)

Satou, Yukimitsu

1988-01-01

The applications of radiation to the medical field are increasing steadily, along with advances in radiation technology and development of new medical equipment. Medical applications of radiation differ from applications in other fields, because the patient is exposed to radiation during examination and radiotherapy. Consequently, it is important that training courses in radiation safety for radiological technologists, medical doctors and nurses be periodically carried out to ensure a more effective and safe utilization of radiation. Furthermore, it is important that such training be based on a practical education curriculum, including basic knowledge, technical training, and safe habits. In this paper, we discuss the appropriate role and attitudes of the radiological technologist in radiation safety education. (author)

Present status of education for radiation safety during clinical examinations and the role of the radiological technologist

Energy Technology Data Exchange (ETDEWEB)

Satou, Yukimitsu

1988-10-01

The applications of radiation to the medical field are increasing steadily, along with advances in radiation technology and development of new medical equipment. Medical applications of radiation differ from applications in other fields, because the patient is exposed to radiation during examination and radiotherapy. Consequently, it is important that training courses in radiation safety for radiological technologists, medical doctors and nurses be periodically carried out to ensure a more effective and safe utilization of radiation. Furthermore, it is important that such training be based on a practical education curriculum, including basic knowledge, technical training, and safe habits. In this paper, we discuss the appropriate role and attitudes of the radiological technologist in radiation safety education.

New U.K. safety legislation and its effects on the control of radiological hazards

International Nuclear Information System (INIS)

Bell, B.H.J.; Luxon, S.G.

1977-01-01

This paper explains the objectives of the Health and Safety at Work etc Act 1974 and refers in particular to its effects on the control of hazards at nuclear installations and, more widely, on the control of radiological hazards generally. It deals also with the changes resulting from the setting up of the Health and Safety Commission and its Executive under the new Act, and the effects of these changes on the work of the Nuclear Installations Inspectorate. (auth.) [fr

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)

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)

Evaluation of medical radiation exposure in pediatric interventional radiology procedures

Energy Technology Data Exchange (ETDEWEB)

Navarro, Valeria Coelho Costa; Navarro, Marcus Vinicius Teixeira; Oliveira, Aline da Silva Pacheco, E-mail: vccnavarro@gmail.com [Instituto Federal de Educacao, Ciencia e Tecnologia da Bahia (IFBA), Salvador, BA (Brazil); Maia, Ana Figueiredo [Universidade Federal de Sergipe (UFS), Aracaju, SE (Brazil); Oliveira, Adriano Dias Dourado [Sociedade Brasileira de Hemodinamica e Cardiologia Intervencionista, Salvador, BA (Brazil)

2012-07-15

Objective: To evaluate pediatric radiation exposure in procedures of interventional radiology in two hospitals in the Bahia state, aiming at contributing to delineate the scenario at the state and national levels. The knowledge of exposure levels will allow an evaluation of the necessity of doses optimization, considering that peculiarities of radiology and pediatrics become even more significant in interventional radiology procedures which involve exposure to higher radiation doses. Materials and Methods: A total of 32 procedures were evaluated in four rooms of the two main hospitals performing pediatric interventional radiology procedures in the Bahia state. Air kerma rate and kerma-area product were evaluated in 27 interventional cardiac and 5 interventional brain procedures. Results: Maximum values for air kerma rate and kerma-area product and air kerma obtained in cardiac procedures were, respectively, 129.9 Gy.cm{sup 2} and 947.0 mGy; and, for brain procedures were 83.3 Gy.cm{sup 2} and 961.0 mGy. Conclusion: The present study results showed exposure values up to 14 times higher than those found in other foreign studies, and approximating those found for procedures in adults. Such results demonstrate excessive exposure to radiation, indicating the need for constant procedures optimization and evaluation of exposure rates. (author)

Evaluation of repository safety

Energy Technology Data Exchange (ETDEWEB)

Sagar, B.; Patrick, W.; Dasgupta, B.; Mohanty, S. [Center for Nuclear Waste Regulatory Analyses, San Antonio (United States)

2002-07-01

The United States high-level waste program requires evaluation of radiological safety during two distinct time intervals. The first interval, commonly referred to as the preclosure period, deals with receipt of waste at the site, transfer into disposal containers, if needed, emplacement in the underground openings, monitoring and maintenance activities, backfill and closure of the underground openings, and decontamination and decommissioning of the surface facilities of the geologic repository. The preclosure period may extend from a few tens of years to as long as a few hundred of years, depending on repository design and societal norms regarding a final decision to permanently seal the repository. During the preclosure or operational period, performance confirmation studies are conducted to provide a basis for updating and reevaluating estimates of postclosure performance and, finally, to provide a basis for a closure decision. The postclosure period during which expected repository performance must meet certain standards may range from ten thousands years, as it does in the United States, to millions of years, as it does in some European nations. Waste handling operations in the preclosure period are to be evaluated in relation to their potential effect on workers, members of general public, and the general environment. During this period, releases of radioactivity are to be monitored and appropriate actions taken whenever established limits are approached or exceeded. Preclosure safety is highly dependent on facility design, operational hardware and automated systems, operational sequences, and reliability of humans involved in operations. Preclosure safety analyses conducted before operations begin play a major role in the design process, selection of equipment, and development of operational procedures. Because of the complexity, duration, and spatial scales of the operations, analyses are conducted using mathematical models implemented in computer codes

Evaluation of repository safety

International Nuclear Information System (INIS)

Sagar, B.; Patrick, W.; Dasgupta, B.; Mohanty, S.

2002-01-01

The United States high-level waste program requires evaluation of radiological safety during two distinct time intervals. The first interval, commonly referred to as the preclosure period, deals with receipt of waste at the site, transfer into disposal containers, if needed, emplacement in the underground openings, monitoring and maintenance activities, backfill and closure of the underground openings, and decontamination and decommissioning of the surface facilities of the geologic repository. The preclosure period may extend from a few tens of years to as long as a few hundred of years, depending on repository design and societal norms regarding a final decision to permanently seal the repository. During the preclosure or operational period, performance confirmation studies are conducted to provide a basis for updating and reevaluating estimates of postclosure performance and, finally, to provide a basis for a closure decision. The postclosure period during which expected repository performance must meet certain standards may range from ten thousands years, as it does in the United States, to millions of years, as it does in some European nations. Waste handling operations in the preclosure period are to be evaluated in relation to their potential effect on workers, members of general public, and the general environment. During this period, releases of radioactivity are to be monitored and appropriate actions taken whenever established limits are approached or exceeded. Preclosure safety is highly dependent on facility design, operational hardware and automated systems, operational sequences, and reliability of humans involved in operations. Preclosure safety analyses conducted before operations begin play a major role in the design process, selection of equipment, and development of operational procedures. Because of the complexity, duration, and spatial scales of the operations, analyses are conducted using mathematical models implemented in computer codes

Radiologic evaluation of the myelomeningocele patient

International Nuclear Information System (INIS)

Byrd, S.E.; Radkowski, M.A.; McLone, D.G.; Storrs, B.B.

1988-01-01

The only radiologic procedure that is useful in the newborn with a fresh myelomeningocele is US or CT of the head to evaluate ventricular size. The imaging procedures become extremely important in the evaluation of the postoperative patient with myelomeningocele. US and/or CT is used to evaluate for hydrocephalus. MR is used to evaluate the spinal axis to determine the position of the cervicomedullary kink, hydromyelia, arachnoid cyst, inclusion epidermoids, and tethering of the spinal cord. US and myelography with CT are needed in subtle cases of tethering, diastematomyelia, arachnoid cyst, and severe scoliosis

Radiological evaluation of failed total hip replacement

International Nuclear Information System (INIS)

Raspa, V.; Aldrovandi, S.; Pompei, G.

1988-01-01

The retrospective study of 50 operated cases of cemented total hip replacement and a review of the literature enabled the authors to define the radiological features of the above-mentioned condition. These features include one or more of the following signs: calcar reabsorption, lacunar erosions, modified relatioships between the prosthesis components, sepsis and loosening, periarticular calcifications dislocation and fracture of prosthesis components. Careful evaluation of these radiological features is extremely important for both an early diagnosis of failed total hip replacement and the choice of an adequate surgical treatment

Nuclear and radiological safety nuclear power nuclear fuel cycle and waste management

International Nuclear Information System (INIS)

1997-05-01

This catalogue lists all sales publications of the International Atomic Energy Agency dealing with Nuclear and Radiological Safety, Nuclear Power and Nuclear Fuel Cycle and Waste Management and issued during the period of 1995-1996. Most publications are in English. Proceedings of conferences, symposia and panels of experts may contain some papers in languages other than English (Arabic, Chinese, French, Russian or Spanish), but all these papers have abstracts in English

Radiological evaluation of swallowing and clinical patterns of systemic sclerosis

International Nuclear Information System (INIS)

Montesi, A.; Pesaresi, A.; Cavalli, M.L.; Serri, L.; Salmistraro, D.; Candela, M.; Gabrielli, A.

1990-01-01

Fifty-one patients with systemic sclerosis (scleroderma) were studied by means of videofluoroscopy in order to evaluate the abnormalities in the oral-pharyngeal and esophageal phases of deglutition and to correlate the radiological patterns with the clinical features of the disease. Thirteen patients (25.5%) exhibited swallowing disorders such as oral leakage, retention, penetration, mild or moderate aspiration and abnormal upper esophageal sphincter behavior. These dysfunctions were more evident in patients with esophageal motility abnormalities. A normal radiological pattern in the esophagus was not associated with swallowing alterations. Remarkably, patients with oral-pharyngeal disorders had a higher incidence of lung diseases. Forty-five patients (88%) exhibited disorders of the esophageal phase of deglutition, such as mild or severe motility abnormalities or hiatal hernia, gastro-esophageal reflux, reflux esophagitis, and stricture. Radiological findings in the esophagus can be abnormal in the early stages of the disease. On the other hand, the radiological pattern of esophageal motility can be occasionally negative in advanced or extensive disease. This indicates a discrepancy between clinical symptoms and radiological picture of the esophagus. The radiological examination of the oral-pharyngeal and esophageal phases of deglutition is important in patients with scleroderma in order to evaluate visceral involvement, motility disorders, and risk of aspiration. Such radiological information can be useful in preventing esophagitis and pulmonary complications

Radiological evaluation of the response to chemotherapy for osteosarcoma

International Nuclear Information System (INIS)

Miwa, Shinji; Taki, Junichi; Yamamoto, Norio

2011-01-01

Sixty-one patients with osteosarcoma were examined by radiographs, angiograms, MRI, 201 Tl and 99m Tc-methoxyisobutyl-isonitrile (MIBI) scintigram to evaluate their response to preoperative chemotherapy. All patients were classified as either responders or non-responder according based on the imaging findings. The radiographs were evaluated according to the degree of sclerotic change and cortical recovery, and the angiograms were evaluated according to the degree of vascular change. MR images were evaluated according to the rate of extraskeletal mass reduction. The 201 Tl and 99m Tc-MIBI scans were evaluated by the percentage reduction of the uptake ratio. All patients were evaluated on the basis of a pathological examination of the resected specimens. We also devised a combined radiological scoring system according to the predictive power of each type of diagnostic image and investigated the correlation between the radiological evaluation and the pathological evaluation. Sensitivity, specificity, and accuracy were 81.0%, 19.0%, and 60.3%, respectively for the radiographs; 77.1%, 20.0%, and 60.0%, respectively, for angiograms; 82.1%, 69.0%, and 75.4%, respectively for MRI; 81.5%, 68.0%, and 75.0%, respectively, for 201 Tl scans; 76.7%, 70.6%, and 74.5% for 99m Tc-MIBI scans; and 88.9%, 84.0%, and 86.9%, respectively, for the combined radiological evaluation. (author)

Radiological assistance program: Region I. Part I

International Nuclear Information System (INIS)

Musolino, S.V.; Kuehner, A.V.; Hull, A.P.

1985-01-01

The purpose of the Radiological Assistance Program (RAP) is to make DOE resources available and provide emergency assistance to state and local agencies in order to control radiological hazards, protect the public health and safety, and minimize the loss of property. This plan is an integral part of a nationwide program of radiological assistance established by the US DOE, and is implemented on a regional basis. The Brookhaven Area Office (BHO) Radiological Assistance Program is applicable to DOE Region I, which consists of the New England States, New York, New Jersey, Pennsylvania, Delaware, Maryland and the District of Columbia. The BHO RAP-1 has been developed to: (a) ensure the availability of an effective radiological assistance capability to ensure the protection of persons and property; (b) provide guidelines to RAP-1 Team personnel for the evaluation of radiological incidents and implementation of corrective actions; (c) maintain liaison with other DOE installations, Federal, State and local organizations which may become involved in radiological assistance operations in Region I; and (d) encourage development of a local capability to cope with radiological incidents

Radiological protection for medical exposure to ionizing radiation. Safety guide

International Nuclear Information System (INIS)

2002-01-01

radiotherapy owing to an ageing population. In addition, further growth in medical radiology can be expected in developing States, where at present facilities and services are often lacking. The risks associated with these expected increases in medical exposures should be outweighed by the benefits. For the purposes of radiation protection, ionizing radiation exposures are divided into three types: Medical exposure, which is mainly the exposure of patients as part of their diagnosis or treatment (see below); Occupational exposure, which is the exposure of workers incurred in the course of their work, with some specific exclusions; and Public exposure, which comprises all other exposures of members of the public that are susceptible to human control. Medical exposure is defined in the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources (BSS, the Standards) as: 'Exposure incurred by patients as part of their own medical or dental diagnosis or treatment; by persons, other than those occupationally exposed, knowingly while voluntarily helping in the support and comfort of patients; and by volunteers in a programme of biomedical research involving their exposure.' This Safety Guide covers all of the medical exposures defined above, with emphasis on the radiological protection of patients, but does not cover exposures of workers or the public derived from the application of medical radiation sources. Guidance relating to these exposures can be found in the Safety Guide on Occupational Radiation Protection. In addition to the IAEA, several intergovernmental and international organizations, among them the European Commission, the International Commission on Radiological Protection (ICRP), the Pan American Health Organization (PAHO) and the World Health Organization (WHO), have already published numerous recommendations, guides and codes of practice relevant to this subject area. National authorities should therefore

Radiological protection for medical exposure to ionizing radiation. Safety guide

International Nuclear Information System (INIS)

2005-01-01

radiotherapy owing to an ageing population. In addition, further growth in medical radiology can be expected in developing States, where at present facilities and services are often lacking. The risks associated with these expected increases in medical exposures should be outweighed by the benefits. For the purposes of radiation protection, ionizing radiation exposures are divided into three types: Medical exposure, which is mainly the exposure of patients as part of their diagnosis or treatment (see below). Occupational exposure, which is the exposure of workers incurred in the course of their work, with some specific exclusions. And Public exposure, which comprises all other exposures of members of the public that are susceptible to human control. Medical exposure is defined in the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources (BSS, the Standards) as: 'Exposure incurred by patients as part of their own medical or dental diagnosis or treatment. By persons, other than those occupationally exposed, knowingly while voluntarily helping in the support and comfort of patients. And by volunteers in a programme of biomedical research involving their exposure.' This Safety Guide covers all of the medical exposures defined above, with emphasis on the radiological protection of patients, but does not cover exposures of workers or the public derived from the application of medical radiation sources. Guidance relating to these exposures can be found in the Safety Guide on Occupational Radiation Protection. In addition to the IAEA, several intergovernmental and international organizations, among them the European Commission, the International Commission on Radiological Protection (ICRP), the Pan American Health Organization (PAHO) and the World Health Organization (WHO), have already published numerous recommendations, guides and codes of practice relevant to this subject area. National authorities should therefore

Planning and preparedness for radiological emergencies at nuclear power stations

International Nuclear Information System (INIS)

Thomson, R.; Muzzarelli, J.

1996-01-01

The Radiological Emergency Preparedness (REP) Program was created after the March 1979 accident at the Three Mile Island nuclear power station. The Federal Emergency Management Agency (FEMA) assists state and local governments in reviewing and evaluating state and local REP plans and preparedness for accidents at nuclear power plants, in partnership with the US Nuclear Regulatory Commission (NRC), which evaluates safety and emergency preparedness at the power stations themselves. Argonne National Laboratory provides support and technical assistance to FEMA in evaluating nuclear power plant emergency response exercises, radiological emergency plans, and preparedness

Radiological safety programs in the petroleum and petrochemistry industry of Venezuela

International Nuclear Information System (INIS)

Romero M, C.

1996-01-01

A diagnosis carried out five years ago showed that in Petroleos de Venezuela (PDVSA) and its subsidiaries, exist about 530 radioactive sources. Also, about 1500 workers were also occupationally exposed, during operations such as industrial radiography and well logging. The same study determined the occurrence of some non-reported accidents and incidents with the overexposure of workers, specially contractors. Most of these problems were the result of the bad application of the radiological protection practices, and on the other hand, the disregarding of the governmental authorities in applying the regulatory standards. In order to solve this situation, PDVSA settled the safety guide for working with ionizing radiation, in which guidelines and technical advice are stablished to perform a safer work with radioactive elements. A radiological protection program was also organized in all the company operational areas. The paper includes the programs, practices and procedures implemented by PDVSA and its subsidiaries. Besides, the result of applying this comprehensive radiation protection program will be showed. (author). 1 ref

Work procedures and risk factors for high rdiation exposure among radiologic technologists in South Korea

Energy Technology Data Exchange (ETDEWEB)

Kim, Jae Young; Choi, Yeong Chull [Dept. of Preventive Medicine, Keimyung University College of Medicine, Daegu (Korea, Republic of); Lee, Won Jin; Cha, Eun Shil [Dept. of Preventive Medicine, Korea University College of Medicine, Seoul (Korea, Republic of)

2016-12-15

Radiologic technologists currently consist of 31.5% among diagnostic radiation workers in South Korea. Among diagnostic radiation workers, radiologic technologists receive the highest annual and collective doses in South Korea. Comprehensive assessment of the work practices and associated radiation doses from diagnostic radiology procedures should be undertaken for effective prevention for radiologic technologists. Using the national survey, this study aimed (1) to explore the distribution of the work procedures performed by gender, (2) to evaluate occupational radiation exposure by work characteristics and safety compliance, (3) to identify the primary factors influencing high radiation exposure among radiologic technologists in South Korea. This study provided detailed information on work practices, number of procedures performed on weekly basis, and occupational radiation doses among radiologic technologists in South Korea. Average radiation dose for radiologic technologists is higher than other countries, and type of facility, work safety, and wearing lead apron explained quite a portion of increased risk in the association between radiology procedures and radiation exposure among radiologic technologists.

Work procedures and risk factors for high rdiation exposure among radiologic technologists in South Korea

International Nuclear Information System (INIS)

Kim, Jae Young; Choi, Yeong Chull; Lee, Won Jin; Cha, Eun Shil

2016-01-01

Radiologic technologists currently consist of 31.5% among diagnostic radiation workers in South Korea. Among diagnostic radiation workers, radiologic technologists receive the highest annual and collective doses in South Korea. Comprehensive assessment of the work practices and associated radiation doses from diagnostic radiology procedures should be undertaken for effective prevention for radiologic technologists. Using the national survey, this study aimed (1) to explore the distribution of the work procedures performed by gender, (2) to evaluate occupational radiation exposure by work characteristics and safety compliance, (3) to identify the primary factors influencing high radiation exposure among radiologic technologists in South Korea. This study provided detailed information on work practices, number of procedures performed on weekly basis, and occupational radiation doses among radiologic technologists in South Korea. Average radiation dose for radiologic technologists is higher than other countries, and type of facility, work safety, and wearing lead apron explained quite a portion of increased risk in the association between radiology procedures and radiation exposure among radiologic technologists.

Test objects for evaluating the performance of radiological imaging systems. Leeds radiological test objects

International Nuclear Information System (INIS)

Cowen, A.R.; Clarke, O.F.; Haywood, J.M.; Parker, R.P.

1985-01-01

A range of test objects has been developed to assess the imaging performance of conventional and digital radiological imaging systems. These test objects have arisen as a result of involvement in both the laboratory evaluation of radiological imaging systems and the routine maintenance of such equipment in a large diagnostic radiology department. The philosophy behind the design and application of the test objects is briefly described. Particular attention is paid to the advantages of using the threshold-contrast detail-detectability technique to assess overall imaging performance. The great importance of ensuring optimum imaging performance prior to clinical acceptance is stressed. A strategy for implementing the test objects in a clinical department is present. The diagnostic information content of the clinical images which result measures the success of the quality control procedure adopted. (author)

Solid bolus swallowing in the radiologic evaluation of dysphagia

International Nuclear Information System (INIS)

Westen, D. van; Ekberg, O.

1993-01-01

Patients with dysphagia, heartburn and chest pain are regularly referred for radiologic evaluation of swallowing. The liquid barium swallow has been of great value for the biphasic evaluation of the pharynx and esophagus. Though many patients complain of dysphagia specifically for solids, solid bolus swallow is ususally not part of the evaluation. For the present study we therefore included the use of a solid bolus with a diameter of 13 mm and interviewed the patients carefully for any symptoms during this tablet swallow. Of 200 patients examined, the tablet passed through the esophagus without delay in 102. In the 98 patients with delayed passage, the solid bolus arrest occurred in the pharynx in 5 and in the esophagus in 93. Arrest in the esophagus was due to esophageal dysmotility in 48 patients. Twenty of these were symptomatic during the tablet swallow. A narrowing was the cause in 45, of whom 9 had symptoms. In 18 patients (9%) the solid bolus added key information to the radiologic evaluation. We therefore recommend that the solid bolus is included in the routine radiologic work-up of patients with dysphagia. Careful attention to symptoms during the tablet swallow is important. (orig.)

Solid bolus swallowing in the radiologic evaluation of dysphagia

Energy Technology Data Exchange (ETDEWEB)

Westen, D. van (Dept. of Diagnostic Radiology, Malmoe General Hospital, Univ. Lund (Sweden)); Ekberg, O. (Dept. of Diagnostic Radiology, Malmoe General Hospital, Univ. Lund (Sweden))

1993-07-01

Patients with dysphagia, heartburn and chest pain are regularly referred for radiologic evaluation of swallowing. The liquid barium swallow has been of great value for the biphasic evaluation of the pharynx and esophagus. Though many patients complain of dysphagia specifically for solids, solid bolus swallow is ususally not part of the evaluation. For the present study we therefore included the use of a solid bolus with a diameter of 13 mm and interviewed the patients carefully for any symptoms during this tablet swallow. Of 200 patients examined, the tablet passed through the esophagus without delay in 102. In the 98 patients with delayed passage, the solid bolus arrest occurred in the pharynx in 5 and in the esophagus in 93. Arrest in the esophagus was due to esophageal dysmotility in 48 patients. Twenty of these were symptomatic during the tablet swallow. A narrowing was the cause in 45, of whom 9 had symptoms. In 18 patients (9%) the solid bolus added key information to the radiologic evaluation. We therefore recommend that the solid bolus is included in the routine radiologic work-up of patients with dysphagia. Careful attention to symptoms during the tablet swallow is important. (orig.).

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

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

Overview of Generation IV (Gen IV) Reactor Designs - Safety and Radiological Protection Considerations. Published on September 24, 2012

International Nuclear Information System (INIS)

Couturier, Jean; Bruna, Giovanni; Baudrand, Olivier; Blanc, Daniel; Ivanov, Evgeny; Bonneville, Herve; Clement, Bernard; Kissane, Martin; Meignen, Renaud; Monhardt, Daniel; Nicaise, Gregory; Bourgois, Thierry; Hache, Georges

2012-01-01

The purpose of this document is to provide an updated overview of specific safety and radiological protection issues for all the reactor concepts adopted by the GIF (Generation IV International Forum), independent of their advantages or disadvantages in terms of resource optimization or long-lived-waste reduction. In particular, this new document attempts to bring out the advantages and disadvantages of each concept in terms of safety, taking into account the Western European Nuclear Regulators' Association (WENRA) statement concerning safety objectives for new nuclear power plants. Using an identical framework for each reactor concept (sodium-cooled fast reactors or SFR, high / very-high temperature helium-cooled reactors of V/HTR, gas-cooled fast reactors or GFR, lead-or lead / bismuth-cooled fast reactors or LFR, molten salt reactors or MSR, and supercritical-water-cooled reactors or SCWR), this summary report provides some general conclusions regarding their safety and radiological protection issues, inspired by WENRA's safety objectives and on the basis of available information. Initial lessons drawn from the events at the Fukushima-Daiichi nuclear power plant in March 2011 have also been taken into account in IRSN's analysis of each reactor concept

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

International Nuclear Information System (INIS)

Domenech Nieves, H.; Callis Fernandez, E.

1998-01-01

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

Challenges in ensuring radiological safety and nuclear forensic for malicious acts involving nuclear and other radioactive material

International Nuclear Information System (INIS)

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

2010-01-01

Nuclear and other radioactive materials may get smuggled into the country aimed at malicious acts. Radioactive material detected accidentally or during inspection at the entry points/national borders may indicate illicit trafficking for the purpose of nuclear/radiological terrorism. As country requires prevention and preparedness for response to these malicious acts, nuclear forensic techniques are to be developed incorporating radiological safety aspects. Nuclear forensics helps in determining the origin, intended use, legal owner and the smuggled route etc. by using fingerprinting as well as comparison with reference data. The suggested sequence of methods for analysis of radioactive material/samples will be radiological assessment, physical characterization, traditional forensic analysis, isotope analysis along with elemental/chemical analysis

Survey of radiological safety in dental practice

Energy Technology Data Exchange (ETDEWEB)

Gill, J R [UKAEA Health and Safety Branch, London; Hudson, A P

1977-01-01

A pilot survey of radiological protection in dental practice in Great Britain has been requested by the Health and Safety Executive and is now in progress. The survey should provide more precise data on the use of X-ray equipment. There are approximately 13,000 dentists in Great Britain using X-ray apparatus, and some 600 of these have been selected, on a statistical basis, to be invited to make use of a postal survey over a six month period. The postal survey technique to be used has already been developed as a service following requests from individual dentists. The dentist receives a questionnaire and three initial films to test the timer, then two special cassettes incorporating film and filters. Film badges are worn over a 12 week period by the dentist and by any staff who assist in radiography. Follow-up visits to discuss the survey will be made to one in ten of the selected dentists. The results will give the individual dentists, without cost, assurance of the efficient functioning of their equipment, and advice, should any remedial measures be necessary. Concurrently, the resulting statistics will give an indication of how many, if any, practices fall short of the recommendations of the Code of Practice for the Protection of Persons against Ionizing Radiations arising from Medical and Dental Use. Further action in respect of the Health and Safety at Work Act will be determined in the light of the survey.

Radiology

International Nuclear Information System (INIS)

Sykora, A.

2006-01-01

In this text-book basic knowledge about radiology, biomedical diagnostic methods (radiography, computer tomography), nuclear medicine and safety and radiation protection of personnel on the radiodiagnostic place of work are presented

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)

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)

Federal Radiological Monitoring and Assessment Center Health and Safety Manual

Energy Technology Data Exchange (ETDEWEB)

FRMAC Health and Safety Working Group

2012-03-20

This manual is a tool to provide information to all responders and emergency planners and is suggested as a starting point for all organizations that provide personnel/assets for radiological emergency response. It defines the safety requirements for the protection of all emergency responders. The intent is to comply with appropriate regulations or provide an equal level of protection when the situation makes it necessary to deviate. In the event a situation arises which is not addressed in the manual, an appropriate management-level expert will define alternate requirements based on the specifics of the emergency situation. This manual is not intended to pertain to the general public.

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)

Quantitative Evaluation of Iranian Radiology Papers and Its Comparison with Selected Countries

International Nuclear Information System (INIS)

Ghafoori, Mahyar; Emami, Hasan; Sedaghat, Abdolrasoul; Ghiasi, Mohammad; Shakiba, Madjid; Alavi, Manijeh

2014-01-01

Recent technological developments in medicine, including modern radiology have promoted the impact of scientific researches on social life. The scientific outputs such as article and patents are products that show the scientists’ attempt to access these achievements. In the current study, we evaluate the current situation of Iranian scientists in the field of radiology and compare it with the selected countries in terms of scientific papers. For this purpose, we used scientometric tools to quantitatively assess the scientific papers in the field of radiology. Radiology papers were evaluated in the context of medical field audit using retrospective model. We used the related databases of biomedical sciences for extraction of articles related to radiology. In the next step, the situation of radiology scientific products of the country were determined with respect to the under study regional countries. Results of the current study showed a ratio of 0.19% for Iranian papers in PubMed database published in 2009. In addition, in 2009, Iranian papers constituted 0.29% of the Scopus scientific database. The proportion of Iranian papers in the understudy region was 7.6%. To diminish the gap between Iranian scientific radiology papers and other competitor countries in the region and achievement of document 2025 goals, multifold effort of the society of radiology is necessary

Innovations in macroscopic evaluation of pancreatic specimens and radiologic correlation

International Nuclear Information System (INIS)

Triantopoulou, Charikleia; Papaparaskeva, Kleo; Agalianos, Christos; Dervenis, Christos

2016-01-01

•The axial slicing technique offers many advantages in accurate estimation of tumors extend and staging.•Cross-sectional axial imaging is the best technique for accurate radiologic-pathologic correlation.•Correlation may explain any discrepancies between radiological and histopathological findings.•Pathology correlation may offer a better understanding of the missed findings by imaging or pitfalls The axial slicing technique offers many advantages in accurate estimation of tumors extend and staging. Cross-sectional axial imaging is the best technique for accurate radiologic-pathologic correlation. Correlation may explain any discrepancies between radiological and histopathological findings. Pathology correlation may offer a better understanding of the missed findings by imaging or pitfalls The purpose of this study was to evaluate the feasibility of a novel dissection technique of surgical specimens in different cases of pancreatic tumors and provide a radiologic pathologic correlation. In our hospital, that is a referral center for pancreatic diseases, the macroscopic evaluation of the pancreatectomy specimens is performed by the pathologists using the axial slicing technique (instead of the traditional procedure with longitudinal opening of the main pancreatic and/or common bile duct and slicing along the plane defined by both ducts). The specimen is sliced in an axial plane that is perpendicular to the longitudinal axis of the descending duodenum. The procedure results in a large number of thin slices (3–4 mm). This plane is identical to that of CT or MRI and correlation between pathology and imaging is straightforward. We studied 70 cases of suspected different solid and cystic pancreatic tumors and we correlated the tumor size and location, the structure—consistency (areas of necrosis—hemorrhage—fibrosis—inflammation), the degree of vessels’ infiltration, the size of pancreatic and common bile duct and the distance from resection margins

Key Performance Indicators in the Evaluation of the Quality of Radiation Safety Programs.

Science.gov (United States)

Schultz, Cheryl Culver; Shaffer, Sheila; Fink-Bennett, Darlene; Winokur, Kay

2016-08-01

Beaumont is a multiple hospital health care system with a centralized radiation safety department. The health system operates under a broad scope Nuclear Regulatory Commission license but also maintains several other limited use NRC licenses in off-site facilities and clinics. The hospital-based program is expansive including diagnostic radiology and nuclear medicine (molecular imaging), interventional radiology, a comprehensive cardiovascular program, multiple forms of radiation therapy (low dose rate brachytherapy, high dose rate brachytherapy, external beam radiotherapy, and gamma knife), and the Research Institute (including basic bench top, human and animal). Each year, in the annual report, data is analyzed and then tracked and trended. While any summary report will, by nature, include items such as the number of pieces of equipment, inspections performed, staff monitored and educated and other similar parameters, not all include an objective review of the quality and effectiveness of the program. Through objective numerical data Beaumont adopted seven key performance indicators. The assertion made is that key performance indicators can be used to establish benchmarks for evaluation and comparison of the effectiveness and quality of radiation safety programs. Based on over a decade of data collection, and adoption of key performance indicators, this paper demonstrates one way to establish objective benchmarking for radiation safety programs in the health care environment.

Diagnosis of radiological security of installations

International Nuclear Information System (INIS)

Herrera V, L.

1991-01-01

The objective of this work is to discuss the diagnosis of the radiological safety of nuclear or radioactive facilities. It was concluded that the one diagnoses like discipline of the radiological safety is susceptible of being represented, taught and programmable in computer and useful systems as preventive tool and of inspection

Evaluation criteria for emergency response plans in radiological transportation

International Nuclear Information System (INIS)

Lindell, M.K.; Perry, R.W.

1980-01-01

This paper identifies a set of general criteria which can be used as guides for evaluating emergency response plans prepared in connection with the transportation of radiological materials. The development of criteria takes the form of examining the meaning and role of emergency plans in general, reviewing the process as it is used in connection with natural disasters and other nonnuclear disasters, and explicitly considering unique aspects of the radiological transportation setting. Eight areas of critical importance for such response plans are isolated: notification procedures; accident assessment; public information; protection of the public at risk; other protective responses; radiological exposure control; responsibility for planning and operations; and emergency response training and exercises. (Auth.)

Radiological safety aspects in the fabrication of mixed oxide fuel elements

International Nuclear Information System (INIS)

Krishnamurthi, T.N.; Janardhanan, S.; Soman, S.D.

1981-01-01

The problems of radiological safety in the fabrication of (U, Pu)O 2 fuel assemblies for fast reactors utilising high exposure plutonium are discussed. Derived working limits for plutonium as a function of the burn-up of RAPS (Rajasthan Atomic Power Station) fuel, external gamma and neutron exposures from feed product batches, finished fuel pins and assemblies are presented. Shielding requirements for the various glove box operations are also indicated. In general, high exposure plutonium handling calls for remote fabrication and automation at various stages would play a key role in minimising exposures to personnel in a large production plant. (author)

Safety evaluations required in the safety regulations for Monju and the validity confirmation of safety evaluation methods

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-08-15

The purposes of this study are to perform the safety evaluations of the fast breeder reactor 'Monju' and to confirm the validity of the safety evaluation methods. In JFY 2012, the following results were obtained. As for the development of safety evaluation methods needed in the safety examination achieved for the reactor establishment permission, development of the analysis codes, such as a core damage analysis code, were carried out according to the plan. As for the development of the safety evaluation method needed for the risk informed safety regulation, the quantification technique of the event tree using the Continuous Markov chain Monte Carlo method (CMMC method) were studied. (author)

Importance of the lower limit of detection in radiological safety

International Nuclear Information System (INIS)

Rafael Terol T.; Hermenegildo Maldonado M.

1991-01-01

The concept of the Lower Limit of Detection (LLD) it contributes in the solution of some problems related with the radiological safety, such as the realization of the tests of flight of the sealed radioactive sources; the determination of radioisotopes in environmental samples; the estimate of present radionuclides in polluted foods; in general, the detection of small quantities of radioactive materials present in materials of use or consumption by part of the man in his daily life; as the one Lower Limit of Detection is related with topics of statistics, in this work a small review of them is made, it was superficially discussed the mensuration problems related with the establishment of the Lower Limit of Detection

About the necessity to update the Radiological safety and protection regulations of the National Institute of Nuclear Research (ININ)

International Nuclear Information System (INIS)

Alvarez R, J.T.

1997-01-01

It is argued the necessity to update the Radiological safety and Protection regulations (Review 3) of ININ, with the purpose that it implements the ICRU operative magnitudes system. Such a system used with radiological protection purposes. The objective of this system is to do an estimation of the effective equivalent dose H E and/or the Effective dose E, proposed in the ICRP 26 and ICRU 60 dose limits systems respectively. (Author)

Evaluation of use of e-Learning in undergraduate radiology education: a review.

Science.gov (United States)

Zafar, Saad; Safdar, Saima; Zafar, Aasma N

2014-12-01

The aim of this review is to investigate the evaluative outcomes present in the literature according to Kirkpatrick's learning model and to examine the nature and characteristics of the e-Learning interventions in radiology education at undergraduate level. Four databases (PubMed, MEDLINE, Embase, Eric) are searched for publications related to the application of e-Learning in undergraduate radiology education. The search strategy is a combination of e-Learning and Mesh and non Mesh radiology and undergraduate related terms. These search strategies are established in relation to experts of respective domains. The full text of thirty pertinent articles is reviewed. Author's country and study location data is extracted to identify the most active regions and year's are extracted to know the existing trend. Data regarding radiology subfields and undergraduate year of radiology education is extracted along with e-Learning technologies to identify the most prevalent or suitable technologies or tools with respect to radiology contents. Kirkpatricks learning evaluation model is used to categorize the evaluative outcomes reported in the identified studies. The results of this analysis reveal emergence of highly interactive games, audience response systems and designing of wide range of customized tools according to learner needs assessment in radiology education at undergraduate level. All these initiatives are leading toward highly interactive self directed learning environments to support the idea of life-long independent learners. Moreover, majority of the studies in literature regarding e-Learning in radiology at undergraduate level are based on participant satisfaction followed by participant results or outcomes either before or after an intervention or both. There was no research particularly demonstrating performance change in clinical practice or patient outcome as they may be difficult to measure in medical education. Thus clinical competences and performances are

Radioactive waste disposal system for Cuba. Safety assessment for the long term

International Nuclear Information System (INIS)

Peralta Vital, J.L.; Gil Castillo, R.; Mirta Torrez, B.

1998-01-01

The present work is performed within the frame of evaluating the radiological impact of the post-closure stage of the facility for disposal of the radioactive wastes generated in Cuba, including a description of the waste disposal systems defined in the country, and taking account of significant elements of their long term safety. The Methodology for Safety Assessment includes: the definition of possible scenarios for evaluation, the identification of principal present uncertainties, the model simulating the release of the radionuclides of the facility, their transport through the geosphere, and their final access to man, evaluating ultimately the radiological impact of the disposal system considering the dose for a critical group. The results obtained allow to demonstrate the radiological safety of the nominative barrier in the design of the system for the particular conditions of Cuba. (author)

Rassyn: National radiological safety data management system

International Nuclear Information System (INIS)

Domenech Nieves, Haydee; Valdez Ramso, Maryzury; Jova Sed, Luis; De la Fuente, Andres

1996-01-01

The paper describes the menu, screens data files, programs and classifications of the systems, for keeping a record of their institutions, inspection and authorization, the personal register of incidents and accidents, and the national inventory of radiation protection sources and equipment. By making use of it, a comparison can be made of existing data of a practice with its requirements and a questionnaire of the inspection, (Checking list), the development and results of the inspection can be reported on, the program and notification of the inspection can be prepared and the information on the radiological situation- whether at a national or at a territorial level- can be evaluated

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)

'On line' course for the periodical training in radiological safety of the workers of a radioactive facility; Cuso 'on line' para la capacitacion periodica en seguridad radiologica de los trabajadores de una instalacion radiactiva

Energy Technology Data Exchange (ETDEWEB)

Amador B, Z.H.; Ayra P, F.E.; Torres B, M.B. [Centro de Isotopos, Ave. Monumental y Carretera La Rada, Km. 3, Guanabacoa, Apartado 3415, Ciudad de La Habana (Cuba)]. e-mail: dsr@centis.edu.cu

2006-07-01

The results of an 'on line' course for the periodical training in radiological safety of the workers of a radioactive installation are presented. The course is developed for own specialists. The following topics are approached: the state of the art of the studies on the biological effects of the ionizing radiations, the new national regulations, the analysis of the behavior of the occupational exposure, of the obtained experiences of the radiological events, of the results of the radiological surveillance of the work positions, of the detected violations and of the behavior of the outstanding systems and the optimization. The study of the acquired experiences in the packing and the transportation of radioactive materials and the administration of the radioactive waste are included. The study of the course by one month is organized and then two convocations of theoretical exams are executed and one for the evaluation practices of the instructions and procedures. To evaluate the effectiveness of the course a survey it is applied and the later behavior of indicators of the radiological safety of the plant is analyzed. The results that are obtained show a positive balance. (Author)

Development of a management system of radiological safety with application to hospitals; Desarrollo de un sistema de gestion de seguridad radiologica con aplicacion a hospitales

Energy Technology Data Exchange (ETDEWEB)

Velazquez M, J.D.; Rivera M, T. [CICATA, IPN, Av. Legaria 694, 11500 Mexico D.F. (Mexico); Santos R, J.R. [SEPI, ESIME, IPN, 07738 Mexico D.F. (Mexico)

2008-07-01

The medicine is the area that more it has benefited with the implementation of the radiation. However, a great number of incidents/accidents they have happened in hospitals in recent years. The above-mentioned stands out the necessity to improve the acting of the radiological safety management systems in Hospitals. This work presents a Management System of Radiological Safety (SGSR). The SGSR has as fundamental objective the one of maintaining the radiological risks inside acceptable levels. The SGSR is generic and it can be applied in the nuclear medicine, radiodiagnostic, radiotherapy, and in other areas of the health sector where it is required to prevent accidents or incidents that affect the health or the well-being of the worker or user. Also it was diagnosed a Specialties Hospital of the Mexico City using some characteristics of the SGSR. The obtained results show that the SGSR can contribute significantly in the improvement of the quality of the service in the attention to the patients and in the radiological safety. (Author)

Preparation, conduct and evaluation of exercises to test preparedness for a nuclear or radiological emergency. Emergency preparedness and response

International Nuclear Information System (INIS)

2005-04-01

The aim of this publication is to serve as a practical tool for the preparation, conduct and evaluation of exercises to test preparedness for response to a nuclear or radiological emergency. It fulfils in part the functions assigned to the IAEA under Article 5.a(ii) of the Convention on Assistance in Case of a Nuclear Accident or Radiological Emergency (Assistance Convention), namely, to collect and disseminate to States Parties and Member States information concerning the methodologies, techniques and available results of research on such emergencies. To ensure effective response to radiation emergencies when needed, provisions should be made for regular training of emergency response personnel. As stated in Preparedness and Response for a Nuclear or Radiological Emergency (Safety Requirements, Safety Standard Series No. GS-R-2), 'The operator and the response organizations shall make arrangements for the selection of personnel and training to ensure that the personnel have the requisite knowledge, skills, abilities, equipment, procedures and other arrangements to perform their assigned response functions'. A further requirement is that 'Exercise programmes shall be conducted to ensure that all specified functions required to be performed for emergency response and all organizational interfaces for facilities in threat category I, II or III and the national level programmes for threat category IV or V are tested at suitable intervals'. In 2004 the IAEA General Conference, in resolution GC(48)/RES/10 encouraged Member States to 'implement the Safety Requirements for Preparedness and Response to a Nuclear or Radiological Emergency'. This document is published as part of the IAEA Emergency Preparedness and Response Series to assist in meeting these requirements and to fulfil Article 5 of the Assistance Convention. It was developed based on a number of assumptions about national and local capabilities. Therefore, the exercise structure, terms and scenarios must be

Iliopsoas compartment lesions: a radiologic evaluation

International Nuclear Information System (INIS)

Leao, Alberto Ribeiro de Souza; Amaral, Raquel Portugal Guimaraes; Abud, Thiago Giansante; Demarchi, Guilherme Tadeu Sauaia; Freire Filho, Edison de Oliveira; Novack, Paulo Rogerio; Campos, Flavio do Amaral; Shigueoka, David Carlos; Fernandes, Artur da Rocha Correa; Szejnfeld, Jacob; D'Ippolito, Giuseppe

2007-01-01

The iliopsoas compartment, a posterior boundary of the retroperitoneum, is comprised of the psoas major, psoas minor and iliac muscles. The symptoms picture in patients presenting with pathological involvement of this compartment may show a wide range of nonspecific clinical presentations that may lead to delayed diagnosis. However, in the search of an etiological diagnosis, it is already known that inflammation, tumors, and hemorrhages account for almost all the lesions affecting the iliopsoas compartment. By means of a retrospective analysis of radiological studies in patients with iliopsoas compartment lesions whose diagnosis was confirmed by anatomopathological evaluation or clinical follow-up, we have reviewed its anatomy as well as the main forms of involvement, with the purpose of identifying radiological signs that may help to narrow down the potential differential diagnoses. As each lesion is approached we will discuss the main radiological findings such as presence of gas in pyogenic abscesses, bone destruction and other bone changes of vertebral bodies in lesions secondary to tuberculosis, involvement of fascial planes in cases of neoplasms, and differences in signal density and intensity of hematomas secondary to hemoglobin degradation, among others. So, we have tried to present cases depicting the most frequent lesions involving the iliopsoas compartment, with emphasis on those signs that can lead us to a more specific etiological diagnosis. (author)

Iliopsoas compartment lesions: a radiologic evaluation

Energy Technology Data Exchange (ETDEWEB)

Leao, Alberto Ribeiro de Souza; Amaral, Raquel Portugal Guimaraes; Abud, Thiago Giansante; Demarchi, Guilherme Tadeu Sauaia; Freire Filho, Edison de Oliveira; Novack, Paulo Rogerio; Campos, Flavio do Amaral; Shigueoka, David Carlos; Fernandes, Artur da Rocha Correa; Szejnfeld, Jacob; D' Ippolito, Giuseppe [Universidade Federal de Sao Paulo (UNIFESP-EPM), Sao Paulo, SP (Brazil). Dept. de Diagnostico por Imagem]. E-mail: ar.leao@uol.com.br; Santos, Jose Eduardo Mourao [Universidade Federal de Sao Paulo (UNIFESP-EPM), Sao Paulo, SP (Brazil)

2007-07-15

The iliopsoas compartment, a posterior boundary of the retroperitoneum, is comprised of the psoas major, psoas minor and iliac muscles. The symptoms picture in patients presenting with pathological involvement of this compartment may show a wide range of nonspecific clinical presentations that may lead to delayed diagnosis. However, in the search of an etiological diagnosis, it is already known that inflammation, tumors, and hemorrhages account for almost all the lesions affecting the iliopsoas compartment. By means of a retrospective analysis of radiological studies in patients with iliopsoas compartment lesions whose diagnosis was confirmed by anatomopathological evaluation or clinical follow-up, we have reviewed its anatomy as well as the main forms of involvement, with the purpose of identifying radiological signs that may help to narrow down the potential differential diagnoses. As each lesion is approached we will discuss the main radiological findings such as presence of gas in pyogenic abscesses, bone destruction and other bone changes of vertebral bodies in lesions secondary to tuberculosis, involvement of fascial planes in cases of neoplasms, and differences in signal density and intensity of hematomas secondary to hemoglobin degradation, among others. So, we have tried to present cases depicting the most frequent lesions involving the iliopsoas compartment, with emphasis on those signs that can lead us to a more specific etiological diagnosis. (author)

Radiological protection, safety and security issues in the industrial and medical applications of radiation sources

Science.gov (United States)

Vaz, Pedro

2015-11-01

The use of radiation sources, namely radioactive sealed or unsealed sources and particle accelerators and beams is ubiquitous in the industrial and medical applications of ionizing radiation. Besides radiological protection of the workers, members of the public and patients in routine situations, the use of radiation sources involves several aspects associated to the mitigation of radiological or nuclear accidents and associated emergency situations. On the other hand, during the last decade security issues became burning issues due to the potential malevolent uses of radioactive sources for the perpetration of terrorist acts using RDD (Radiological Dispersal Devices), RED (Radiation Exposure Devices) or IND (Improvised Nuclear Devices). A stringent set of international legally and non-legally binding instruments, regulations, conventions and treaties regulate nowadays the use of radioactive sources. In this paper, a review of the radiological protection issues associated to the use of radiation sources in the industrial and medical applications of ionizing radiation is performed. The associated radiation safety issues and the prevention and mitigation of incidents and accidents are discussed. A comprehensive discussion of the security issues associated to the global use of radiation sources for the aforementioned applications and the inherent radiation detection requirements will be presented. Scientific, technical, legal, ethical, socio-economic issues are put forward and discussed.

Post-deployment usability evaluation of a radiology workstation

NARCIS (Netherlands)

Jorritsma, Wiard; Cnossen, Fokie; Dierckx, Rudi A.; Oudkerk, Matthijs; Van Ooijen, Peter M. A.

Objectives: To determine the number, nature and severity of usability issues radiologists encounter while using a commercially available radiology workstation in clinical practice, and to assess how well the results of a pre-deployment usability evaluation of this workstation generalize to clinical

Preliminary report of radiological safety to hydrology 1993 campaign; Informe preliminar de seguridad radiologica para la campana de hidrologia 1993

Energy Technology Data Exchange (ETDEWEB)

Badano, A; Suarez Antola, R; Dellepere, A; Barreiro, M [MIEM, Direccion Nacional de Tecnologia Nuclear, Montevideo (Uruguay)

1993-07-01

This report has been prepared based on the interaction between project managers and division radiological Protection and Nuclear Safety. In seeking to establish a basis for approval from the point of view of radiation safety practices . The idea for the audit has been provided at all times because the interest was the exchange of ideas and the use of common sense to improve the safety of radioactive substances, security of operators and public safety and environment.The above shows that in the planned radiation safety condition described in this report,the practice can be carried out according to the criteria of safety accepted .

Operation Praetorian onsite radiological safety report, October 1981-September 1982

International Nuclear Information System (INIS)

Mullen, O.W.; Eubank, B.F.

1983-09-01

PRAETORIAN was the name assigned to the series of underground nuclear experiments conducted at the Nevada Test Site from October 1, 1981 through September 30, 1982. Remote radiation measurements were taken during and after each nuclear experiment by a telemetry system. Monitors with portable radiation detection instruments surveyed reentry routes into ground zeros before other planned entries were made. Continuous surveillance was provided while personnel were in radiation areas and appropriate precautions were taken to protect persons from unnecessary exposure to radiation and toxic gases. Protective clothing and equipment were issued as needed. Complete radiological safety and industrial hygiene coverage was provided during drilling and mineback operations. Telemetered and portable radiation detector measurements are listed. Detection instrumentation used is described and specific operational procedures are defined

Operation QUICKSILVER. Onsite radiological safety report, October 1978-September 1979

International Nuclear Information System (INIS)

Mullen, O.W.; Eubank, B.F.

1980-02-01

QUICKSILVER was the name assigned to the series of underground nuclear experiments conducted at the Nevada Test Site from October 1, 1978 to September 30, 1979. Remote radiation measurements were taken during and after each nuclear experiment by a telemetry system. Monitors with portable radiation detection instruments surveyed reentry routes into ground zeroes before other planned entries were made. Continuous surveillance was provided while personnel were in radiation areas and appropriate precautions were taken to protect persons from unnecessary exposure to radiation and toxic gases. Protective clothing and equipment were issued as needed. Complete radiological safety and industrial hygiene coverage was provided during drilling and mineback operations. Telemetered and portable radiation detector measurements are listed. Detection instrumentation used is described and specific optional procedures are defined

Operation CRESSET: onsite radiological safety report, October 1977--September 1978

International Nuclear Information System (INIS)

Mullen, O.W.; Eubank, B.F.

1979-06-01

CRESSET was the name assigned to the series of underground nuclear experiments conducted at the Nevada Test Site from October 1, 1977 to September 30, 1978. Remote radiation measurements were taken during and after each nuclear experiment by a telemetry system. Monitors with portable radiation detection instruments surveyed reentry routes into ground zeroes before other planned entries were made. Continuous surveillance was provided while personnel were in radiation areas and appropriate precautions were taken to protect persons from unnecessary exposure to radiation and toxic gases. Protective clothing and equipment were issued as needed. Complete radiological safety and industrial hygiene coverage was provided during drilling and mineback operations. Telemetered and portable radiation detector measurements are listed. Detection instrumentation used is described and specific operational procedures are defined

Operation FULCRUM: onsite radiological safety report, October 1976--September 1977

International Nuclear Information System (INIS)

Mullen, O.W.; Eubank, B.F.

1978-03-01

FULCRUM was the name assigned to the series of underground nuclear experiments conducted at the Nevada Test Site from October 1, 1976 to September 30, 1977. Remote radiation measurements were taken during and after each nuclear experiment by a telemetry system. Monitors with portable radiation detection instruments surveyed reentry routes into ground zeroes before other planned entries were made. Continuous surveillance was provided while personnel were in radiation areas and appropriate precautions were taken to protect persons from unnecessary exposure to radiation and toxic gases. Protective clothing and equipment were issued as needed. Complete radiological safety and industrial hygiene coverage was provided during drilling and mineback operations. Telemetered and portable radiation detector measurements are listed. Detection instrumentation used is described and specific operational procedures are defined

Operation GUARDIAN onsite radiological safety report, October 1980-September 1981

International Nuclear Information System (INIS)

Mullen, O.W.; Eubank, B.F.

1983-02-01

GUARDIAN was the name assigned to the series of underground nuclear experiments conducted at the Nevada Test Site from October 1, 1980 to September 30, 1981. Remote radiation measurements were taken during and after each nuclear experiment by a telemetry system. Monitors with portable radiation detection intruments surveyed reentry routes into ground zeroes before other planned entries were made. Continuous surveillance was provided while personnel were in radiation areas and appropriate precautions were taken to protect persons from unnecessary exposure to radiation and toxic gases. Protective clothing and equipment were issued as needed. Complete radiological safety and industrial hygiene coverage was provided during drilling and mineback operations. Telemetered and portable radiation detector measurements are listed. Detection instrumentation used is described and specific operational procedures are defined

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

Science.gov (United States)

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

2004-12-01

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

Evaluation of use of e-Learning in undergraduate radiology education: A review

Energy Technology Data Exchange (ETDEWEB)

Zafar, Saad, E-mail: saad.zafar@riphah.edu.pk [Riphah International University, Islamabad (Pakistan); Safdar, Saima, E-mail: saima.safdar@riphah.edu.pk [Riphah International University, Islamabad (Pakistan); Zafar, Aasma N., E-mail: aasmarad@gmail.com [Radiology Department, Senior Registrar Shifa College of Medicine and Assistant Consultant Shifa International Hospital, Islamabad (Pakistan)

2014-12-15

Highlights: • We have systematically reviewed the literature on use of e-Learning in Radiology at the undergraduate level. • Kirkpatrick's Learning Model is used to evaluate the learning outcomes of the reported studies. • There is an increase in positive response for learning management systems used in blended learning environments. • There are wide range of technologies being used for e-Learning including use of audio response system and customized PAC solutions. • There is a clear trend toward highly interactive, self directed learning environment to support the concept of life long independent learners. - Abstract: Purpose: The aim of this review is to investigate the evaluative outcomes present in the literature according to Kirkpatrick's learning model and to examine the nature and characteristics of the e-Learning interventions in radiology education at undergraduate level. Materials and methods: Four databases (PubMed, MEDLINE, Embase, Eric) are searched for publications related to the application of e-Learning in undergraduate radiology education. The search strategy is a combination of e-Learning and Mesh and non Mesh radiology and undergraduate related terms. These search strategies are established in relation to experts of respective domains. The full text of thirty pertinent articles is reviewed. Author's country and study location data is extracted to identify the most active regions and year's are extracted to know the existing trend. Data regarding radiology subfields and undergraduate year of radiology education is extracted along with e-Learning technologies to identify the most prevalent or suitable technologies or tools with respect to radiology contents. Kirkpatricks learning evaluation model is used to categorize the evaluative outcomes reported in the identified studies. Results: The results of this analysis reveal emergence of highly interactive games, audience response systems and designing of wide range of

Evaluation of use of e-Learning in undergraduate radiology education: A review

International Nuclear Information System (INIS)

Zafar, Saad; Safdar, Saima; Zafar, Aasma N.

2014-01-01

Highlights: • We have systematically reviewed the literature on use of e-Learning in Radiology at the undergraduate level. • Kirkpatrick's Learning Model is used to evaluate the learning outcomes of the reported studies. • There is an increase in positive response for learning management systems used in blended learning environments. • There are wide range of technologies being used for e-Learning including use of audio response system and customized PAC solutions. • There is a clear trend toward highly interactive, self directed learning environment to support the concept of life long independent learners. - Abstract: Purpose: The aim of this review is to investigate the evaluative outcomes present in the literature according to Kirkpatrick's learning model and to examine the nature and characteristics of the e-Learning interventions in radiology education at undergraduate level. Materials and methods: Four databases (PubMed, MEDLINE, Embase, Eric) are searched for publications related to the application of e-Learning in undergraduate radiology education. The search strategy is a combination of e-Learning and Mesh and non Mesh radiology and undergraduate related terms. These search strategies are established in relation to experts of respective domains. The full text of thirty pertinent articles is reviewed. Author's country and study location data is extracted to identify the most active regions and year's are extracted to know the existing trend. Data regarding radiology subfields and undergraduate year of radiology education is extracted along with e-Learning technologies to identify the most prevalent or suitable technologies or tools with respect to radiology contents. Kirkpatricks learning evaluation model is used to categorize the evaluative outcomes reported in the identified studies. Results: The results of this analysis reveal emergence of highly interactive games, audience response systems and designing of wide range of

Safety evaluation of the nuclear power plant at Cattenom

International Nuclear Information System (INIS)

Anon.

1987-01-01

This is a systematic compilation of the material which was dealt with at the level of the German-French Commission (on questions of the safety of nuclear installations) in this discussions about the nuclear power plant at Cattenom. As a supplement to the report published already in 1982, the Commission has officially released its deliberation results on the subjects constructive safety measures, radiological effects, and precautions in case of an emergency. The allegations according to which the installation is wanting in safety are countered by the joint statement of the chairmen of GPR (Permanent Group on Reactors) and RSK (German Commission on Reactor Safety) of August 29, 1986. (HSCH) [de

The assessment of the safety and the radiological risks associated with the transport of radioactive wastes in Romania

International Nuclear Information System (INIS)

Vieru, G.

2000-01-01

Problems related to the handling, treatment, packaging, storage, transportation, and disposal of radioactive wastes (radwastes) are very important and the responsibility for the safe management of radioactive wastes for the protection of human health and the environment has long been recognized. Safety and public welfare are to be considered within the radioactive waste management, particularly in the field of transportation because of the potential risk that it could pose to the public and to the environment. The IAEA regulations ensure safety in the transport of Radioactive Materials (RAM) by laying down detailed requirements, appropriate to the degree of hazard represented by the respective material, taking into account its form and quantity. Risk assessment provides a basis for routing radwastes and developing mitigation plans, prioritizing initiatives and enacting legislation to protect human beings and the environment. Factors such as shipment cost, distance, population exposed, environmental impacts or sensitivity, time in transit and infrastructure related issues, could be included in the terms of safety and risk. The paper presents risk assessment activities aimed to evaluate risk categories and the radiological consequences that may arise during normal (accident free) transport and those resulting from transport accidents involving waste shipments in Romania. (author)

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)

[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).

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.)

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.)

Radiological evaluation of the cervical spinal trauma

Energy Technology Data Exchange (ETDEWEB)

Bae, W. K.; Koh, B. H.; Hahm, C. K.; Kim, J. J. [School of Medicine, Hanyang University, Seoul (Korea, Republic of)

1983-03-15

Acute injuries of the cervical spine are the most common causes of severe disability following trauma, yet the diagnosis of these injuries are often delayed and the treatment, inadequate. Traumatic injuries of the cervical spine are diagnosed by radiological examinations. And complete evaluations of bony structures and soft tissue changes on conventional radiograms are very important for determining the therapeutic plans and prognoses of the injuries patients. During the period of 5 years from June 1976 to May 1981, the radiological and clinical evaluation had been made on 38 patients suffered from acute cervical spinal injuries which were confirmed by the radiological examinations. The results were as follows. 1. Age distribution of total 38 patients was broad ranging from 19 years to 72 years. 2. The most common cause of injury was traffic accident, next fall down, other accident respectively. 3. Levels of the cervical spinal injuries were as follows: Upper cervical spine in 15.8%, lower cervical spine in 84.2%, and the most common injuries level was C 5. Most of the lower cervical spinal injuries were located in the vertebral body and spinous process. 4. Anatomical sites of the cervical spinal injuries were as follows; vertebral body in 55.5%, spinous process in 23.7%, neural arch in 15.8%, and locked facet in 18.4%, etc. 5. Most of the patients with severe mental changes were injuries in upper cervical spine rather than lower. And most of the patients with quadriplegia or paraplegia were shown marked disruption of spinal canal.

Radiological evaluation of the cervical spinal trauma

International Nuclear Information System (INIS)

Bae, W. K.; Koh, B. H.; Hahm, C. K.; Kim, J. J.

1983-01-01

Acute injuries of the cervical spine are the most common causes of severe disability following trauma, yet the diagnosis of these injuries are often delayed and the treatment, inadequate. Traumatic injuries of the cervical spine are diagnosed by radiological examinations. And complete evaluations of bony structures and soft tissue changes on conventional radiograms are very important for determining the therapeutic plans and prognoses of the injuries patients. During the period of 5 years from June 1976 to May 1981, the radiological and clinical evaluation had been made on 38 patients suffered from acute cervical spinal injuries which were confirmed by the radiological examinations. The results were as follows. 1. Age distribution of total 38 patients was broad ranging from 19 years to 72 years. 2. The most common cause of injury was traffic accident, next fall down, other accident respectively. 3. Levels of the cervical spinal injuries were as follows: Upper cervical spine in 15.8%, lower cervical spine in 84.2%, and the most common injuries level was C 5. Most of the lower cervical spinal injuries were located in the vertebral body and spinous process. 4. Anatomical sites of the cervical spinal injuries were as follows; vertebral body in 55.5%, spinous process in 23.7%, neural arch in 15.8%, and locked facet in 18.4%, etc. 5. Most of the patients with severe mental changes were injuries in upper cervical spine rather than lower. And most of the patients with quadriplegia or paraplegia were shown marked disruption of spinal canal

IAEA Perspectives on Radiological Characterisation

International Nuclear Information System (INIS)

O'Sullivan, Patrick; Ljubenov, Vladan

2012-01-01

Requirements for characterization of radiological and other hazards in nuclear facilities are reflected in the IAEA Safety Standards. WS-R-5, Safety Requirements for Decommissioning of Facilities using Radioactive Material, includes a requirement that 'During the preparation of the final decommissioning plan, the extent and type of radioactive material (irradiated and contaminated structures and components) at the facility shall be determined by means of a detailed characterization survey and on the basis of records collected during the operational period'. The subsidiary Safety Guide WS-G-2.1, Decommissioning of Nuclear Power Plants and Research Reactors, further elaborates that 'A survey of radiological and non-radiological hazards provides an important input for the safety assessment and for implementing a safe approach during the work'. Although the characterisation requirements addressed in the Safety Standards relate primarily to the detailed survey activities undertaken following the shutdown of the facility, it is evident that radiological characterization is of relevance to all major phases of the lifetime of a nuclear facility, including: - the siting phase - baseline surveys are undertaken to determine background radiation levels; - the construction phase - construction materials are retained to support future calculations of radioactivity distributions; - the operational phase - surveys are done regularly, with additional surveys being required following incidents involving plant contamination; - the transition phase - detailed radiological surveys are required to support the development of the final decommissioning plan; and - the closure phase - a final survey of the site and any remaining structures will be needed to support an application for release of the site from regulatory control. In the case of facilities that are already shut down, the main purpose of radiological characterisation is to provide a reliable database of information on the

Radiological impacts analysis with use of new endpoint as complementary safety indicators

International Nuclear Information System (INIS)

Peralta Vital, J.L.; Gil Castillo, R.; Fleitas Estevez, G.G.; Olivera Acosta, J.

2015-01-01

The paper shows the new safety indicators on risk assessment (safety assessment) to radioactive waste environmental management implementation (concentrations and fluxes of naturally occurring radioactive materials (NORM)). The endpoint obtained, allow the best analysis of the radiological impact associated to radioactive waste isolation system. The common safety indicators for safety assessment purpose, dose and risk, are very time dependent, increasing the uncertainties in the results for long term assessment. The complementary and new proposed endpoints are more stable and they are not affected by changes in the critical group, pathways, etc. The NORM values on facility site were obtained as result of national surveys, the natural concentrations of U, Ra, Th, K has been associated with the variation of the lithologies in 3 geographical areas of the Country (Occidental, Central and Oriental). The results obtained are related with the safety assessment topics and allowed to apply the new complementary safety indicators, by comparisons between the natural concentrations and fluxes on site and its calculated values for the conceptual repository design. In order to normalize the concentration results, the analysis was realized adopting the criteria of the Repository Equivalent Rock Volume (RERV). The preliminary comparison showed that the calculated concentrations and fluxes in the Cuban conceptual radioactive waste repository are not higher than the natural values in the host rock. According to the application of new safety indicators, the reference disposal facility does not increase the natural activity concentration and fluxes in the environment. In order to implement these new safety indicator it has been used the current 226 Ra inventory of the Repository and the 226 Ra as natural concentration on the site. (authors)

IAEA safety requirements for safety assessment of fuel cycle facilities and activities

International Nuclear Information System (INIS)

Jones, G.

2013-01-01

The IAEA's Statute authorises the Agency to establish standards of safety for protection of health and minimisation of danger to life and property. In that respect, the IAEA has established a Safety Fundamentals publication which contains ten safety principles for ensuring the protection of workers, the public and the environment from the harmful effects of ionising radiation. A number of these principles require safety assessments to be carried out as a means of evaluating compliance with safety requirements for all nuclear facilities and activities and to determine the measures that need to be taken to ensure safety. The safety assessments are required to be carried out and documented by the organisation responsible for operating the facility or conducting the activity, are to be independently verified and are to be submitted to the regulatory body as part of the licensing or authorisation process. In addition to the principles of the Safety Fundamentals, the IAEA establishes requirements that must be met to ensure the protection of people and the environment and which are governed by the principles in the Safety Fundamentals. The IAEA's Safety Requirements publication 'Safety Assessment for Facilities and Activities', establishes the safety requirements that need to be fulfilled in conducting and maintaining safety assessments for the lifetime of facilities and activities, with specific attention to defence in depth and the requirement for a graded approach to the application of these safety requirements across the wide range of fuel cycle facilities and activities. Requirements for independent verification of the safety assessment that needs to be carried out by the operating organisation, including the requirement for the safety assessment to be periodically reviewed and updated are also covered. For many fuel cycle facilities and activities, environmental impact assessments and non-radiological risk assessments will be required. The

Review of IAEA documentation on Nuclear and radiological emergency

International Nuclear Information System (INIS)

Mukhono, P. M.

2014-10-01

The project focuses on the review of IAEA documentation on nuclear or radiological emergencies with main focus on methodology for developing and arrangement for nuclear and radiological emergencies. The main objective of this work is to identify limitations in IAEA documentation on emergency preparedness and response (EPR) and provide recommendation on the main actions needed to fill the gaps identified thus aiding in improvement of emergency preparedness and response to nuclear and radiological accidents. The review of IAEA documentation on nuclear and radiological emergency has been carried out by evaluating various emergency response elements. Several elements for EPR were highlighted covering the safety fundamentals, general safety requirements and EPR methods for development of an effective emergence response capability for nuclear or radiological emergencies. From these issues, the limitations of IAEA documentation on EPR were drawn and recommendations suggested as a means of improving EPR methods. Among them was the need for IAEA consider establishment of follow up and inspection programmes to facilitate implementation of EPR requirements in most developing countries, establishment of programmes that provide platforms for the countries to be motivated to update their system in line with the current status of emergency preparedness, review of the international information exchange aspects of nuclear emergencies in order to improve capabilities to communicate reliable data, information and decisions quickly and effectively among national authorities and their emergency and emergency response centres. (au)

Report on nuclear and radiological safety in 1994; Porocilo o jedrski in radioloski varnosti v letu 1994

Energy Technology Data Exchange (ETDEWEB)

Lovincic, D [Slovenian Nuclear Safety Administration, Ljubljana (Slovenia)

1995-07-01

The Slovenian Nuclear Safety Administration (SNSA) in cooperation with the Health Inspectorate, prepared the Report on Nuclear and Radiological Safety in the Republic of Slovenia for 1994 as part of its regular practice of reporting on its activities to the Government and the Parliament of the Republic of Slovenia. The report is divided into seven thematic chapters covering the activities of the SNSA, the operation of nuclear facilities in Slovenia, the activities of the Agency for Radwaste Management (ARAO), the activities of international safety missions in Slovenia, environmental radioactivity monitoring in Slovenia, ionizing radiation sources control by Slovenian Health Inspectorate and review of the operation of nuclear facilities around the world.

Modeling and Analysis on Radiological Safety Assessment of Low- and Intermediate Level Radioactive Waste Repository

Energy Technology Data Exchange (ETDEWEB)

Lee, Youn Myoung; Jung, Jong Tae; Kang, Chul Hyung (and others)

2008-04-15

Modeling study and analysis for technical support for the safety and performance assessment of the low- and intermediate level (LILW) repository partially needed for radiological environmental impact reporting which is essential for the licenses for construction and operation of LILW has been fulfilled. Throughout this study such essential area for technical support for safety and performance assessment of the LILW repository and its licensing as gas generation and migration in and around the repository, risk analysis and environmental impact during transportation of LILW, biosphere modeling and assessment for the flux-to-dose conversion factors for human exposure as well as regional and global groundwater modeling and analysis has been carried out.

Modeling and Analysis on Radiological Safety Assessment of Low- and Intermediate Level Radioactive Waste Repository

International Nuclear Information System (INIS)

Lee, Youn Myoung; Jung, Jong Tae; Kang, Chul Hyung

2008-04-01

Modeling study and analysis for technical support for the safety and performance assessment of the low- and intermediate level (LILW) repository partially needed for radiological environmental impact reporting which is essential for the licenses for construction and operation of LILW has been fulfilled. Throughout this study such essential area for technical support for safety and performance assessment of the LILW repository and its licensing as gas generation and migration in and around the repository, risk analysis and environmental impact during transportation of LILW, biosphere modeling and assessment for the flux-to-dose conversion factors for human exposure as well as regional and global groundwater modeling and analysis has been carried out

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.

Innovations in macroscopic evaluation of pancreatic specimens and radiologic correlation

Directory of Open Access Journals (Sweden)

Charikleia Triantopoulou

2016-01-01

Full Text Available The purpose of this study was to evaluate the feasibility of a novel dissection technique of surgical specimens in different cases of pancreatic tumors and provide a radiologic pathologic correlation. In our hospital, that is a referral center for pancreatic diseases, the macroscopic evaluation of the pancreatectomy specimens is performed by the pathologists using the axial slicing technique (instead of the traditional procedure with longitudinal opening of the main pancreatic and/or common bile duct and slicing along the plane defined by both ducts. The specimen is sliced in an axial plane that is perpendicular to the longitudinal axis of the descending duodenum. The procedure results in a large number of thin slices (3–4 mm. This plane is identical to that of CT or MRI and correlation between pathology and imaging is straightforward. We studied 70 cases of suspected different solid and cystic pancreatic tumors and we correlated the tumor size and location, the structure—consistency (areas of necrosis—hemorrhage—fibrosis—inflammation, the degree of vessels’ infiltration, the size of pancreatic and common bile duct and the distance from resection margins. Missed findings by imaging or pitfalls were recorded and we tried to explain all discrepancies between radiology evaluation and the histopathological findings. Radiologic-pathologic correlation is extremely important, adding crucial information on imaging limitations and enabling quality assessment of surgical specimens. The deep knowledge of different pancreatic tumors’ consistency and way of extension helps to improve radiologists’ diagnostic accuracy and minimize the radiological-surgical mismatching, preventing patients from unnecessary surgery.

Radiologic evaluation of colorectal cancer

International Nuclear Information System (INIS)

Lee, Young Joong; Kang, Hee Tae; Kim, Jong Deok; Rhee, Hak Song

1984-01-01

The incidence of colorectal cancer of Korea is much lower than that of Western countries, but has shown a tendency to a slight increase recently. Barium enema is the most valuable, noninvasive and inexpensive method available to evaluate the size, shape and site of colorectal cancer. The authors reviewed and radiologically classified barium enema studies of 232 cases of colorectal cancer from Aug. 1967 to July 1982 at Presbyterian Medical Center, Jeonju, Confirmed clinically, operatively and pathologically. The results were as follows; 1. The ratio of male and female was 1.3:1, and youngest was 13 year-old and the oldest 86 year-old. 2. The peak incidence occurred from 5th to 7th decades, accounting for 78% of all cases (181/232), and there was a relatively high incidence of the disease in patients below 30 years of age at 7.8% (18/232). 3. Rectum and rectosigmoid region are the most frequently involved regions (127/232:54.8%). 4. The positivity of barium enema examination was 4.0% (232/5807), and its accuracy was 96.5% (224/232). 5. The radiologic findings were classified into 4 groups, and they were annular encircling 62.9% (146/232). polypoid fungating 26.8% (62/232), infiltrating 8.6% (20/232), and primary ulcerating 1.7% (4/232) in order of frequency. 6. The linear length of the cancer ranged from 1.5 Cm to 15 Cm, and the average length was 5.5 Cm. 7. There was no statistical correlation between the length of lesion, the site, and the radiologic findings, and stages of the lesion (P:0.750-0.250). 8. The majority of colorectal cancers was adenocarcinoma (217/232:93.6%)

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

Energy Technology Data Exchange (ETDEWEB)

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

1995-07-01

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

Feminist theoretical perspectives on ethics in radiology

International Nuclear Information System (INIS)

Condren, M.

2009-01-01

The substantive safety of radiological and other medical procedures can be radically reduced by unconscious factors governing scientific thought. In addition, the historical exclusion of women from these disciplines has possibly skewed their development in directions that now need to be addressed. This paper focuses on three such factors: gendered libidos that privilege risk taking over prevention, fragmented forms of knowledge that encourage displaced forms of responsibility and group dynamics that discourage critique of accepted practices and limit the definition of one's group. The substantive safety of the practice and scientific contribution of radiologists might be considerably enhanced were the focus to switch from radiology to diagnosis. Such enlargement might redefine the brief of radiologists towards preventing as well as curing; evaluating some non-invasive and low-tech options, adopting some inclusive paradigms of clinical ecology and enlarging group identities to include those currently excluded through geography or social class from participating in the benefits of science. (authors)

Feminist theoretical perspectives on ethics in radiology.

Science.gov (United States)

Condren, Mary

2009-07-01

The substantive safety of radiological and other medical procedures can be radically reduced by unconscious factors governing scientific thought. In addition, the historical exclusion of women from these disciplines has possibly skewed their development in directions that now need to be addressed. This paper focuses on three such factors: gendered libidos that privilege risk taking over prevention, fragmented forms of knowledge that encourage displaced forms of responsibility and group dynamics that discourage critique of accepted practices and limit the definition of one's group. The substantive safety of the practice and scientific contribution of radiologists might be considerably enhanced were the focus to switch from radiology to diagnosis. Such enlargement might redefine the brief of radiologists towards preventing as well as curing; evaluating some non-invasive and low-tech options, adopting some inclusive paradigms of clinical ecology and enlarging group identities to include those currently excluded through geography or social class from participating in the benefits of science.

Radioactive wastes. Safety of storage facilities

International Nuclear Information System (INIS)

Devillers, Ch.

2001-01-01

A radioactive waste storage facility is designed in a way that ensures the isolation of wastes with respect to the biosphere. This function comprises the damping of the gamma and neutron radiations from the wastes, and the confinement of the radionuclides content of the wastes. The safety approach is based on two time scales: the safety of the insulation system during the main phase of radioactive decay, and the assessment of the radiological risks following this phase. The safety of a surface storage facility is based on a three-barrier concept (container, storage structures, site). The confidence in the safety of the facility is based on the quality assurance of the barriers and on their surveillance and maintenance. The safety of a deep repository will be based on the site quality, on the design and construction of structures and on the quality of the safety demonstration. This article deals with the safety approach and principles of storage facilities: 1 - recall of the different types of storage facilities; 2 - different phases of the life of a storage facility and regulatory steps; 3 - safety and radiation protection goals (time scales, radiation protection goals); 4 - safety approach and principles of storage facilities: safety of the isolation system (confinement system, safety analysis, scenarios, radiological consequences, safety principles), assessment of the radiation risks after the main phase of decay; 5 - safety of surface storage facilities: safety analysis of the confinement system of the Aube plant (barriers, scenarios, modeling, efficiency), evaluation of radiological risks after the main phase of decay; experience feedback of the Manche plant; variants of surface storage facilities in France and abroad (very low activity wastes, mine wastes, short living wastes with low and average activity); 6 - safety of deep geological disposal facilities: legal framework of the French research; international context; safety analysis of the confinement system

Radiological and scintigraphic evaluation of hip prostheses

International Nuclear Information System (INIS)

Bessler, W.; Schaub, W.

1979-01-01

The radiological findings following the introduction of hip prostheses are often equivocal. Additional bone scintigrams often provide important information for the evaluation of the prostheses. 1. An unstable hip prosthesis is characterised by abnormal uptake in bone, due to static and mechanical stress. 2. A positive scintigram does not necessarily indicate instability of the prosthesis. Increased uptake may also be due to inflammatory bone changes, healing, bone replacement, abnormal local stresses or soft tissue calcification. 3. In evaluating the scintigram one must take account not only of the intensity of isotope uptake, but also its distribution and exact localisation. 4. It is essential to compare the scintigram with the radiograph. Radiological features of possible instability become diagnostic if they correspond with appropriate increased radioactivity. If the latter is absent, the of instability remains doubtful. 5. In some cases early loosening of the stem of the prosthesis can be diagnosed while the radiograph is still negative. Increased radioactivity in the acetabulum is frequently seen in the presence of a stable acetabular prosthesis and must be interpreted with caution as a sign of loosening of the prosthesis. (orig.) [de

Preparedness and response for a nuclear or radiological emergency. Safety requirements

International Nuclear Information System (INIS)

2004-01-01

This Safety Requirements publication establishes the requirements for an adequate level of preparedness and response for a nuclear or radiological emergency in any State. Their implementation is intended to minimize the consequences for people, property and the environment of any nuclear or radiological emergency. The fulfilment of these requirements will also contribute to the harmonization of arrangements in the event of a transnational emergency. These requirements are intended to be applied by authorities at the national level by means of adopting legislation, establishing regulations and assigning responsibilities. The requirements apply to all those practices and sources that have the potential for causing radiation exposure or environmental radioactive contamination warranting an emergency intervention and that are: (a) Used in a State that chooses to adopt the requirements or that requests any of the sponsoring organizations to provide for the application of the requirements. (B) Used by States with the assistance of the FAO, IAEA, ILO, PAHO, OCHA or WHO in compliance with applicable national rules and regulations. (C) Used by the IAEA or which involve the use of materials, services, equipment, facilities and non-published information made available by the IAEA or at its request or under its control or supervision. Or (d) Used under any bilateral or multilateral arrangement whereby the parties request the IAEA to provide for the application of the requirements. The requirements also apply to the off-site jurisdictions that may need to make an emergency intervention in a State that adopts the requirements. The types of practices and sources covered by these requirements include: fixed and mobile nuclear reactors. Facilities for the mining and processing of radioactive ores. Facilities for fuel reprocessing and other fuel cycle facilities. Facilities for the management of radioactive waste. The transport of radioactive material. Sources of radiation used in

Study contribution to the new international philosophy of the radiological safety system on chemical processing of the natural uranium

International Nuclear Information System (INIS)

Silva, T.M. da.

1988-01-01

The objective of the work is to adapt the radiological Safety System in the facilities concerned to the chemical treatment of the uranium concentrated (yellow-cake) until conversion in uranium hexafluoride in the pilot plant of IPEN-CNEN/SP, to the new international philosophy adopted by the International Commission Radiological on Protection ICPR publication 22(1973), 26(1977), 30(1978) and the International Atomic Energy Agency IAEA publication 9(1982). The new philosophy changes fully the Radiological Protection concepts of preceding philosophy, changes, also, the concept of the work place and individual monitoring as well as the classification of the working areas. These new concepts are applied in each phase of the natural uranium treatment chemical process in conversion facility. (author)

Assumptions used for evaluating the potential radiological consequences of a less of coolant accident for pressurized water reactors - June 1974

International Nuclear Information System (INIS)

Anon.

1974-01-01

Section 50.34 of 10 CFR Part 50 requires that each applicant for a construction permit or operating license provide an analysis and evaluation of the design and performance of structures, systems, and components of the facility with the objective of assessing the risk to public health and safety resulting from operation of the facility. The design basis loss of coolant accident is one of the postulated accidents used to evaluate the adequacy of these structures, systems, and components with respect to the public health and safety. This guide gives acceptable assumptions that may be used in evaluating the radiological consequences of this accident for a pressurized water reactor. In some cases, unusual site characteristics, plant design features, or other factors may require different assumptions which will be considered on an individual case basis. The Advisory Committee on Reactor Safeguards has been consulted concerning this guide and has concurred in the regulatory position

Assumptions used for evaluating the potential radiological consequences of a loss of coolant accident for boiling water reactors - June 1974

International Nuclear Information System (INIS)

Anon.

1974-01-01

Section 50.34 of 10 CFR Part 50 requires that each applicant for a construction permit or operating license provide an analysis and evaluation of the design and performance of structures, systems, and components of the facility with the objective of assessing the risk to public health and safety resulting from operation of the facility. The design basis loss of coolant accident is one of the postulated accidents used to evaluate the adequacy of these structures, systems, and components with respect to the public health and safety. This guide gives acceptable assumptions that may be used in evaluating the radiological consequences of this accident for a pressurized water reactor. In some cases, unusual site characteristics, plant design features, or other factors may require different assumptions which will be considered on an individual case basis. The Advisory Committee on Reactor Safeguards has been consulted concerning this guide and has concurred in the regulatory position

Radiological optimization

International Nuclear Information System (INIS)

Zeevaert, T.

1998-01-01

Radiological optimization is one of the basic principles in each radiation-protection system and it is a basic requirement in the safety standards for radiation protection in the European Communities. The objectives of the research, performed in this field at the Belgian Nuclear Research Centre SCK-CEN, are: (1) to implement the ALARA principles in activities with radiological consequences; (2) to develop methodologies for optimization techniques in decision-aiding; (3) to optimize radiological assessment models by validation and intercomparison; (4) to improve methods to assess in real time the radiological hazards in the environment in case of an accident; (5) to develop methods and programmes to assist decision-makers during a nuclear emergency; (6) to support the policy of radioactive waste management authorities in the field of radiation protection; (7) to investigate existing software programmes in the domain of multi criteria analysis. The main achievements for 1997 are given

Radiological safety training for uranium facilities

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-02-01

This handbook contains recommended training materials consistent with DOE standardized core radiological training material. These materials consist of a program management guide, instructor`s guide, student guide, and overhead transparencies.

Evaluation of Current Computer Models Applied in the DOE Complex for SAR Analysis of Radiological Dispersion & Consequences

Energy Technology Data Exchange (ETDEWEB)

O' Kula, K. R. [Savannah River Site (SRS), Aiken, SC (United States); East, J. M. [Savannah River Site (SRS), Aiken, SC (United States); Weber, A. H. [Savannah River Site (SRS), Aiken, SC (United States); Savino, A. V. [Savannah River Site (SRS), Aiken, SC (United States); Mazzola, C. A. [Savannah River Site (SRS), Aiken, SC (United States)

2003-01-01

The evaluation of atmospheric dispersion/ radiological dose analysis codes included fifteen models identified in authorization basis safety analysis at DOE facilities, or from regulatory and research agencies where past or current work warranted inclusion of a computer model. All computer codes examined were reviewed using general and specific evaluation criteria developed by the Working Group. The criteria were based on DOE Orders and other regulatory standards and guidance for performing bounding and conservative dose calculations. Included were three categories of criteria: (1) Software Quality/User Interface; (2) Technical Model Adequacy; and (3) Application/Source Term Environment. A consensus-based limited quantitative ranking process was used to base an order of model preference as both an overall conclusion, and under specific conditions.

Occupational exposure in interventional radiology

International Nuclear Information System (INIS)

Oh, H.J.; Lee, K.Y.; Cha, S.H.; Kang, Y.K.; Kim, H.J.; Oh, H.J.

2003-01-01

This study was conducted to survey of radiation safety control and to measure occupational radiation exposure dose of staff in interventional radiology in Korea. Interventioanl radiology requires the operator and assisting personnel to remain close to the patient, and thus close to primary beams of radiation. Therefore exposure doses of these personnel are significant from a radiological protection point of view. We surveyed the status of radiation safety on interventional radiology of 72 hospitals. The result were that 119 radiation equipments are using in interventional radiology and 744 staffs are composed of 307 radiologists, 116 residents of radiology, 5 general physicians, 171 radiologic technologists and 145 nurses. 81.4% and 20.2 % of operating physicians are using neck collar protector and goggle respectively. The average radiation dose was measured 0.46±0.15 mSv/10 hours fluoroscopy inside examination room in radiation protection facilities. Occupational radiation exposure data on the staff were assessed in interventional radiology procedures from 8 interventional radiology equipments of 6 university hospitals. The dose measurements were made by placing a thermoluminesent dosimeter(TLD) on various body surface of operation and assistant staff during actual interventional radiology. The measured points were the corner of the eyes, neck(on the thyroid) , wrists, chest(outside and inside of the protector), and back. Average radiation equivalent dose of the corner of left eye and left wrist of operating physicians were 1.19 mSv(0.11∼4.13 mSv)/100 minutes fluoroscopy and 4.32 mSv(0.16∼11.0 mSv)/100 minutes fluoroscopy respectively. Average exposure dose may vary depending on the type of procedure, personal skills and the quality of equipment. These results will be contributed to prepare the guide line in interventional radiology in Korea

General principles of nuclear safety management related to research reactor decommissioning

International Nuclear Information System (INIS)

Banciu, Ortenzia; Vladescu, Gabriela

2003-01-01

The paper contents the general principles applicable to the decommissioning of research reactors to ensure a proper nuclear safety management, during both decommissioning activities and post decommissioning period. The main objective of decommissioning is to ensure the protection of workers, population and environment against all radiological and non-radiological hazards that could result after a reactor shutdown and dismantling. In the same time, it is necessary, by some proper provisions, to limit the effect of decommissioning for the future generation, according to the new Romanian, IAEA and EU Norms and Regulations. Assurance of nuclear safety during decommissioning process involves, in the first step, to establish of some safety principles and requirements to be taken into account during whole process. In the same time, it is necessary to perform a series of analyses to ensure that the whole process is conducted in a planned and safe manner. The general principles proposed for a proper management of safety during research reactor decommissioning are as follows: - Set-up of all operations included in a Decommissioning Plan; - Set-up and qualitative evaluation of safety problems, which could appear during normal decommissioning process, both radiological and nonradiological risks for workers and public; - Set-up of accident list related to decommissioning process the events that could appear both due to some abnormal working conditions and to some on-site and off-site events like fires, explosions, flooding, earthquake, etc.); - Development and qualitative/ quantitative evaluation of scenarios for each incidents; - Development (and evaluation) of safety indicator system. The safety indicators are the most important tools used to assess the level of nuclear safety during decommissioning process, to discover the weak points and to establish safety measures. The paper contains also, a safety case evaluation (description of facility according to the decommissioning

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)

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.

[Evaluation of patient doses in interventional radiology].

Science.gov (United States)

Ropolo, R; Rampado, O; Isoardi, P; Gandini, G; Rabbia, C; Righi, D

2001-01-01

To verify the suitability of indicative quantities to evaluate the risk related to patient exposure, in abdominal and vascular interventional radiology, by the study of correlations between dosimetric quantities and other indicators. We performed in vivo measurements of entrance skin dose (ESD) and dose area product (DAP) during 48 procedures to evaluate the correlation among dosimetric quantities, and an estimation of spatial distribution of exposure and effective dose (E). To measure DAP we used a transmission ionization chamber and to evaluate ESD and its spatial distribution we used radiographic film packed in a single envelope and placed near the patient's skin. E was estimated by a calculation software using data from film digitalisation. From the data derived for measurements in 27 interventional procedures on 48 patients we obtained a DAP to E conversion factor of 0.15 mSv / Gy cm2, with an excellent correlation (r=.99). We also found a good correlation between DAP and exposure parameters such as fluoroscopy time and number of images. The greatest effective dose was evaluated for a multiple procedure in the hepatic region, with a DAP value of 425 Gy cm2. The greatest ESD was about 550 mGy. For groups of patients undergoing similar interventional procedures the correlation between ESD and DAP had conversion factors from 6 to 12 mGy Gy-1 cm-2. The evaluation of ESD and E by slow films represents a valid method for patient dosimetry in interventional radiology. The good correlation between DAP and fluoroscopy time and number of images confirm the suitability of these indicators as basic dosimetric information. All the ESD values found are lower than threshold doses for deterministic effects.

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)

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

Safety of light water reactors. Risks of nuclear technology

International Nuclear Information System (INIS)

Veser, Anke; Schlueter, Franz-Hermann; Raskob, Wolfgang; Landman, Claudia; Paesler-Sauer, Juergen; Kessler, Guenter

2012-01-01

The book on the safety of light-water reactors includes the following chapters: Part I: Physical and technical safety concept of actual German and future European light-water reactors: (1) Worldwide operated nuclear power plants in 2011, (2) Some reactor physical fundamentals. (3) Nuclear power plants in Germany. (4) Radioactive exposure due to nuclear power plants. (5) Safety concept of light-water reactors. (6) Probabilistic analyses and risk studies. (7) Design of light-water reactors against external incidents. (8) Risk comparison of nuclear power plants and other energy systems. (9) Evaluation of risk studies using the improved (new) safety concept for LWR. (19) The severe reactor accidents of Three Mile Island, Chernobyl and Fukushima. Part II: Safety of German LWR in case of a postulated aircraft impact. (11) Literature. (12) Review of requirements and actual design. (13) Incident scenarios. (14) Load approach for aircraft impact. (15) Demonstration of the structural behavior in case of aircraft impact. (16) Special considerations. (17) Evaluation of the safety state of German and foreign nuclear power plants. Part III: ROSOS as example for a computer-based decision making support system for the severe accident management. (19) Literature. (20) Radiological fundamentals, accident management, modeling of the radiological situation. (21) The decision making support system RODOS. (22) RODOS and the Fukushima accident. (23) Recent developments in the radiological emergency management in the European frame.

Radiation dose evaluation in patients submitted to conventional radiological examinations

International Nuclear Information System (INIS)

Tilly Junior, Joao G.

1997-01-01

This work presents the results of the evaluation of radiation dose delivered to the patients undergoing conventional radiological procedures. Based in the realized measurement some indicators are settled to quantitative appraisal of the radiological protection conditions offered to the population. Data assessment was done in the county of Curitiba, in Parana State, Brazil, from 12/95 to 04/96, in ten rooms of three different institutions, under 101 patients, adults with 70 ± 10 kg, during real examinations of chest PA, chest LAT and abdomen AP. (author)

Safety and effectiveness of moderate sedation for radiologic non-vascular intervention

International Nuclear Information System (INIS)

Kim, Tae-Hoon

2006-01-01

The purpose of this study was to prospectively characterize the safety and effectiveness of moderate sedation/analgesia for performing radiologic non-vascular abdominal intervention. During a 3-month period, a total of 63 adult patients with a mean age of 64 years (range:27-82) underwent moderate sedation for 72 radiologic non-vascular interventional procedures. A combination of fentanyl citrate and midazolam hydrochloride, based on the patient's body weight, was intravenously administered until the patient was drowsy and tranquil. The adverse events associated with this moderate sedation were assessed. The visual analog scale format was used to measure the subjective feelings of the patient's pre-pro- cedural anxiety and intraprocedural pain. The mean total dose per kilogram of body weight of fentanyl used in PTBD was 1.148 μg. The mean total dose per kilogram of body weight of midazolam was 0.035 mg in PTBD, PTGBD, AD, PCN, DJS, GS and FRA, 0.039 mg in TDC, and 0.043 mg in BS. A temporary reduction of systolic blood pressure to less than 80 mmHg was observed during 5 procedures (6.9%), whereas a temporary elevation of systolic blood pressure above 150 mmHg was observed during 10 procedures (13.8%). A reduction of arterial oxygen saturation to less than 90% was observed during 14 procedures (19.4%). None of the patients required pharmacologic reversal agents or cardiopulmonary resuscitation. The mean anxiety score recorded before all procedures was 5.2 (distressing). The mean pain score during the procedure, which was recorded after all procedures, was 2.9 (mild). Moderate sedation allows performance of safe and effective radiologic non-vascular intervention, and it is also easy for an interventional radiologist to use. The patients should be continuously monitored to check their vital signs and arterial oxygen saturation during the procedures

Safety and effectiveness of moderate sedation for radiologic non-vascular intervention

Energy Technology Data Exchange (ETDEWEB)

Kim, Tae-Hoon [Dankook University Hospital, Chungju (Korea, Republic of)

2006-06-15

The purpose of this study was to prospectively characterize the safety and effectiveness of moderate sedation/analgesia for performing radiologic non-vascular abdominal intervention. During a 3-month period, a total of 63 adult patients with a mean age of 64 years (range:27-82) underwent moderate sedation for 72 radiologic non-vascular interventional procedures. A combination of fentanyl citrate and midazolam hydrochloride, based on the patient's body weight, was intravenously administered until the patient was drowsy and tranquil. The adverse events associated with this moderate sedation were assessed. The visual analog scale format was used to measure the subjective feelings of the patient's pre-pro- cedural anxiety and intraprocedural pain. The mean total dose per kilogram of body weight of fentanyl used in PTBD was 1.148 {mu}g. The mean total dose per kilogram of body weight of midazolam was 0.035 mg in PTBD, PTGBD, AD, PCN, DJS, GS and FRA, 0.039 mg in TDC, and 0.043 mg in BS. A temporary reduction of systolic blood pressure to less than 80 mmHg was observed during 5 procedures (6.9%), whereas a temporary elevation of systolic blood pressure above 150 mmHg was observed during 10 procedures (13.8%). A reduction of arterial oxygen saturation to less than 90% was observed during 14 procedures (19.4%). None of the patients required pharmacologic reversal agents or cardiopulmonary resuscitation. The mean anxiety score recorded before all procedures was 5.2 (distressing). The mean pain score during the procedure, which was recorded after all procedures, was 2.9 (mild). Moderate sedation allows performance of safe and effective radiologic non-vascular intervention, and it is also easy for an interventional radiologist to use. The patients should be continuously monitored to check their vital signs and arterial oxygen saturation during the procedures.

Radioactive Waste Management Complex low-level waste radiological performance assessment

Energy Technology Data Exchange (ETDEWEB)

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

1994-04-01

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

Radioactive Waste Management Complex low-level waste radiological performance assessment

International Nuclear Information System (INIS)

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

1994-04-01

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

Radiological error: analysis, standard setting, targeted instruction and teamworking

International Nuclear Information System (INIS)

FitzGerald, Richard

2005-01-01

Diagnostic radiology does not have objective benchmarks for acceptable levels of missed diagnoses [1]. Until now, data collection of radiological discrepancies has been very time consuming. The culture within the specialty did not encourage it. However, public concern about patient safety is increasing. There have been recent innovations in compiling radiological interpretive discrepancy rates which may facilitate radiological standard setting. However standard setting alone will not optimise radiologists' performance or patient safety. We must use these new techniques in radiological discrepancy detection to stimulate greater knowledge sharing, targeted instruction and teamworking among radiologists. Not all radiological discrepancies are errors. Radiological discrepancy programmes must not be abused as an instrument for discrediting individual radiologists. Discrepancy rates must not be distorted as a weapon in turf battles. Radiological errors may be due to many causes and are often multifactorial. A systems approach to radiological error is required. Meaningful analysis of radiological discrepancies and errors is challenging. Valid standard setting will take time. Meanwhile, we need to develop top-up training, mentoring and rehabilitation programmes. (orig.)

Changes in compliance rates of evaluation criteria after health care accreditation: Mainly on radiologic technologists working at University Hospitals in Daejeon area

International Nuclear Information System (INIS)

Ko, Eun Ju; Kim, Hyun Joo; Lee, Jin Yong; Bae, Seok Hwan

2013-01-01

This study aimed to assess whether the changes in compliance rates of evaluation criteria after healthcare accreditation among radiologic technologists working at four university hospitals which had acquired healthcare accreditation in Daejeon metropolitan area. In this study, the evaluation criteria of healthcare accreditation were reclassified and reevaluated to three areas which include patient safety, staff safety, and environmental safety. Each area has eight, three, and five questions, respectively. Each compliance rate was quantitatively measured on a scale of 0 to 10 before and after in this study. The result shows that the overall compliance rates were decreased on all areas compared to the time healthcare accreditation was obtained. The compliance rate of hand hygiene was drastically reduced. To maintain the compliance rates, not only individuals but healthcare organizations should simultaneously endeavor. In particular, healthcare organizations should make an effort to provide continuous education opportunity to their workers and supervise the compliance regularly

Determination of action zone in the nuclear / radiology handling process

International Nuclear Information System (INIS)

Ade Awalludin

2013-01-01

Assessment has been conducted on determination of action zone in nuclear or radiological emergency. The assessment is taken into account radiological risk level in nuclear or radiological emergency management process outside nuclear installation. Managing of nuclear emergency is same as that one of other emergency by adding the principles of radiation protection. This study aims to provide guidance in making of safety and security perimeter outside the nuclear installation for first responders during nuclear/radiological emergency based on dose rate, contamination level or distance from the scene. Separation of working zone is important for first responder safety that works in radiological environment in the event of nuclear or radiation emergency without violating their standard operating procedure. Value limit of safety and security perimeter has been made according to the conditions in Indonesia and considering the applicability in practical. (author)

Implementation of a radiological safety management system in a hospital of Mexico City; Implementacion de un sistema de gestion de seguridad radiologica en un hospital de la Ciudad de Mexico

Energy Technology Data Exchange (ETDEWEB)

Martinez V, D.; Rivera M, T. [CICATA-IPN, 11500 Mexico D.F. (Mexico); Velez D, V. [INER, 14000 Mexico D.F. (Mexico)

2007-07-01

Full text: The reflection of this work is based in some radiological accidents that its have happened in some hospital centers or of research. The over exposure of some people is due to the pursuit of the procedures, the lack of quality assurance of the equipment or the inappropriate actions of the technicians. In Mexico one has seen in several hospitals the lack of existence of a Quality Assurance Program to prevent the accidents, the execution of the same ones and those good practices and the lack of Safety Culture makes that the hospital radiological safety it is faulty. The objective of the present work is the implementation of a radiological safety management in a hospital of Mexico City. (Author)

Radiological safety research of food irradiation with 7.5 MeV X-rays

International Nuclear Information System (INIS)

Yang Bin; Tang Weidong; Zhang Yue; Xu Tao; Jin Jianqiao; Ye Mingyang

2012-01-01

China and America both have 7.5 MeV high energy X-ray accelerator. The radiological safety of food irradiated with 7.5 MeV X-rays (bremsstrahlung) has been investigated. Samples of meat and meat ash were located in a large volume of fresh meat at the position of the highest photoneutron fluence and irradiated to an X-ray dose of 15 kGy, twice the maximum dose allowed by the US FDA for meat irradiation. An evaluation of the corresponding radiation exposure from ingestion of the irradiated product has been compared to natural background radiation. The paper concludes that the risk to individuals from intake of food irradiated with X-rays from 7.5 MeV electrons, even with a broad energy spectrum, would be trivial. The common target materials are Au, Ta and W. The U.S, requires only Au and Ta can be used as food irradiation target materials and China has not yet relevant provisions. The first 7.5 MeV accelerator for food irradiation in China is under built, and will do the explore research for the choice of target material. (authors)

The radiological risks associated with the thorium fuelled HTGR fuel cycle. A comparative risk evaluation

International Nuclear Information System (INIS)

Dodd, D.H.; Hienen, J.F.A. van.

1995-10-01

This report presents the results of task B.3 of the 'Technology Assessment of the High Temperature Reactor' project. The objective of task B.3 was to evaluate the radiological risks to the general public associated with the sustainable HTGR cycle. Since the technologies to be used at several stages of this fuel cycle are still in the design phase and since a detailed specification of this fuel cycle has not yet been developed, the emphasis was on obtaining a global impression of the risk associated with a generic thorium-based HTGR fuel cycle. This impression was obtained by performing a comparative risk analysis on the basis of data given in the literature. As reference for the comparison a generic uranium fuelled LWR cycle was used. The major benefit with respect to the radiological rsiks of basing the fuel cycle around modular HTGR technology instead of the LWR technology is the increase in reactor safety. The design of the modular HTGR is expected to prevent the release of a significant amount of radioactive material to the environment, and hence early deaths in the surrounding population, during accident conditions. This implies that there is no group risk as defined in the Dutch risk management policy. The major benefit of thorium based fuel cycles over uranium based fuel cycles is the reduction in the radiological risks from unraium mining and milling. The other stages of the nuclear fuel cycle which make a significant contribution to the radiological risks are electricity generation, reprocessing and final disposal. The risks associated with the electricity generation stage are dominated by the risks from fission products, activated corrosion products and the activation products tritium and carbon-14. The risks associated with the reprocessing stage are determined by fission and activation products (including actinides). (orig./WL)

The radiological risks associated with the thorium fuelled HTGR fuel cycle. A comparative risk evaluation

Energy Technology Data Exchange (ETDEWEB)

Dodd, D.H.; Hienen, J.F.A. van

1995-10-01

This report presents the results of task B.3 of the `Technology Assessment of the High Temperature Reactor` project. The objective of task B.3 was to evaluate the radiological risks to the general public associated with the sustainable HTGR cycle. Since the technologies to be used at several stages of this fuel cycle are still in the design phase and since a detailed specification of this fuel cycle has not yet been developed, the emphasis was on obtaining a global impression of the risk associated with a generic thorium-based HTGR fuel cycle. This impression was obtained by performing a comparative risk analysis on the basis of data given in the literature. As reference for the comparison a generic uranium fuelled LWR cycle was used. The major benefit with respect to the radiological rsiks of basing the fuel cycle around modular HTGR technology instead of the LWR technology is the increase in reactor safety. The design of the modular HTGR is expected to prevent the release of a significant amount of radioactive material to the environment, and hence early deaths in the surrounding population, during accident conditions. This implies that there is no group risk as defined in the Dutch risk management policy. The major benefit of thorium based fuel cycles over uranium based fuel cycles is the reduction in the radiological risks from unraium mining and milling. The other stages of the nuclear fuel cycle which make a significant contribution to the radiological risks are electricity generation, reprocessing and final disposal. The risks associated with the electricity generation stage are dominated by the risks from fission products, activated corrosion products and the activation products tritium and carbon-14. The risks associated with the reprocessing stage are determined by fission and activation products (including actinides). (orig./WL).

Training Programs on Radiological Safety for users of Ionizing Radiations in Peru; Programas de formacion en proteccion radiologica para usuarios de radiaciones ionizantes en el Peru

Energy Technology Data Exchange (ETDEWEB)

Medina Gironzini, E.

2003-07-01

In Peru, people who work with ionizing radiations must have an authorization (Individual License) as established in the Radiological Safety Regulations, which are the mandatory rules. The Technical Office of the National Authority (OTAN), which is the technical organ of the Peruvian Institute of Nuclear Energy (IPEN) in charge of controlling radiations within the country, grants the authorization after the candidate demonstrates that he/she knows the specific use of the technique using radiations, as well as the aspects related to safety and radiological protection. Since it was created in 1972, the Superior Center of Nuclear Studies (VSEN) from IPEN has carried out different training courses so that people can work safety with ionizing radiations in medicine, industry and investigation. The analysis of the radiological safety programs carried out by CSEN during the last 30 years, which allowed the training of more than 2200 people in the country and, at the same time, made possible the securing of the respective Individual License, is presented in this work. The courses, nuclear medicine, radiotherapy, industrial radiography, nuclear gauges gamma irradiator, etc..., are part of the continuous education program of CSEN. (Author)

Safety analysis and risk assessment handbook

International Nuclear Information System (INIS)

Peterson, V.L.; Colwell, R.G.; Dickey, R.L.

1997-01-01

This Safety Analysis and Risk Assessment Handbook (SARAH) provides guidance to the safety analyst at the Rocky Flats Environmental Technology Site (RFETS) in the preparation of safety analyses and risk assessments. Although the older guidance (the Rocky Flats Risk Assessment Guide) continues to be used for updating the Final Safety Analysis Reports developed in the mid-1980s, this new guidance is used with all new authorization basis documents. With the mission change at RFETS came the need to establish new authorization basis documents for its facilities, whose functions had changed. The methodology and databases for performing the evaluations that support the new authorization basis documents had to be standardized, to avoid the use of different approaches and/or databases for similar accidents in different facilities. This handbook presents this new standardized approach. The handbook begins with a discussion of the requirements of the different types of authorization basis documents and how to choose the one appropriate for the facility to be evaluated. It then walks the analyst through the process of identifying all the potential hazards in the facility, classifying them, and choosing the ones that need to be analyzed further. It then discusses the methods for evaluating accident initiation and progression and covers the basic steps in a safety analysis, including consequence and frequency binning and risk ranking. The handbook lays out standardized approaches for determining the source terms of the various accidents (including airborne release fractions, leakpath factors, etc.), the atmospheric dispersion factors appropriate for Rocky Flats, and the methods for radiological and chemical consequence assessments. The radiological assessments use a radiological open-quotes templateclose quotes, a spreadsheet that incorporates the standard values of parameters, whereas the chemical assessments use the standard codes ARCHIE and ALOHA

Preliminary report in radiological safety for 1993 hydrology campaign

International Nuclear Information System (INIS)

Badano, A.; Suraez, R.; Dellepere, A.; Barreiro, M.

1993-01-01

The purpose of this report is to provide a study about industrial effluents influence on water pollution of Montevideo coastal beaches. The methods which have been considered are nuclear tracer techniques with a special attention in the radioprotection supervision. Three points are considered as evaluation: handling of radioactive tracers and safety, radiation protection workers, environment and public safety. tabs

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

International Nuclear Information System (INIS)

Chen Xiaoqiu; Yue Huiguo

2006-01-01

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

Advancing radiology through informed leadership: summary of the proceedings of the Seventh Biannual Symposium of the International Society for Strategic Studies in Radiology (IS3R), 23-25 August 2007

International Nuclear Information System (INIS)

Muellner, Ada; Hricak, Hedvig; Glazer, Gary M.; Reiser, Maximilian F.; Bradley, William G.; Krestin, Gabriel P.; Thrall, James H.

2009-01-01

The International Society for Strategic Studies in Radiology (IS 3 R) brings together thought leaders from academia and industry from around the world to share ideas, points of view and new knowledge. This article summarizes the main concepts presented at the 2007 IS 3 R symposium, providing a window onto trends shaping the future of radiology. Topics addressed include new opportunities and challenges in the field of interventional radiology; emerging techniques for evaluating and improving quality and safety in radiology; and factors impeding progress in molecular imaging and nanotechnology and possible ways to overcome them. Regulatory hurdles to technical innovation and drug development are also discussed more broadly, along with proposals for addressing regulators' concerns and streamlining the regulatory process. (orig.)

Evaluation of PC-based diagnostic radiology workstations

International Nuclear Information System (INIS)

Pollack, T.; Brueggenwerth, G.; Kaulfuss, K.; Niederlag, W.

2000-01-01

Material and Methods: During February 1999 and September 1999 medical users at the hospital Dresden-Friedrichstadt Germany had tested 7 types of radiology diagnostic workstations. Two types of test methods were used: In test type 1 ergonomic and handling functions were evaluated impartial according to 78 selected user requirements. In test type 2 radiologists and radiographers (3+4) performed 23 work flow steps with a subjectively evaluation. Results: By using a progressive rating no product could fully meet the user requirements. As a result of the summary evaluation for test 1 and test 2 the following compliance rating was calculated for the different products: Rad Works (66%), Magic View (63%), ID-Report (58%), Impax 3000 (53%), Medical Workstation (52%), Pathspeed (46%) and Autorad (39%). (orig.) [de

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

International Nuclear Information System (INIS)

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

2006-01-01

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

Computational evaluation of a pencil ionization chamber in a standard diagnostic radiology beam

International Nuclear Information System (INIS)

Mendonca, Dalila Souza Costa; Neves, Lucio Pereira; Perini, Ana Paula; Belinato, Walmir

2016-01-01

In this work a pencil ionization chamber was evaluated. This evaluation consisted in the determination of the influence of the ionization chamber components in its response. For this purpose, the Monte Carlo simulations and the spectrum of the standard diagnostic radiology beam (RQR5) were utilized. The results obtained, showed that the influence of the ionization chamber components presented no significant influence on the chamber response. Therefore, this ionization chamber is a good alternative for dosimetry in diagnostic radiology. (author)

NATO Advanced Research Workshop on Preparedness for Nuclear and Radiological Threats

CERN Document Server

Diamond, David

2015-01-01

The nuclear crisis in Fukushima and growing threats of nuclear terrorism must serve as a wake-up call, prompting greater action to prepare ourselves for nuclear and radiological disasters. Our strategy to prepare for these threats is multi-layered and the events of these past years have proved the necessity to re-evaluate the national and international preparedness goals on a scale never before considered. The programme of NATO Advanced Research Workshop on “Preparedness for Nuclear and Radiological Threats” has been focused on science and technology challenges associated with our need to improve the national and international capacity and capability to prevent, protect against, mitigate the effects of, respond to, and recover from the nuclear and radiological disasters, including nuclear and radiological accident, terrorist attack by Improvised Nuclear Device (IND) or by “Dirty Bomb”-Radiological Dispersal Device (RDD), that pose the greatest risk to the national and international security and safety...

Preclosure radiological safety analysis for accident conditions of the potential Yucca Mountain Repository: Underground facilities; Yucca Mountain Site Characterization Project

Energy Technology Data Exchange (ETDEWEB)

Ma, C.W.; Sit, R.C.; Zavoshy, S.J.; Jardine, L.J. [Bechtel National, Inc., San Francisco, CA (United States); Laub, T.W. [Sandia National Labs., Albuquerque, NM (United States)

1992-06-01

This preliminary preclosure radiological safety analysis assesses the scenarios, probabilities, and potential radiological consequences associated with postulated accidents in the underground facility of the potential Yucca Mountain repository. The analysis follows a probabilistic-risk-assessment approach. Twenty-one event trees resulting in 129 accident scenarios are developed. Most of the scenarios have estimated annual probabilities ranging from 10{sup {minus}11}/yr to 10{sup {minus}5}/yr. The study identifies 33 scenarios that could result in offsite doses over 50 mrem and that have annual probabilities greater than 10{sup {minus}9}/yr. The largest offsite dose is calculated to be 220 mrem, which is less than the 500 mrem value used to define items important to safety in 10 CFR 60. The study does not address an estimate of uncertainties, therefore conclusions or decisions made as a result of this report should be made with caution.

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)

Advancing radiology through informed leadership: summary of the proceedings of the Seventh Biannual Symposium of the International Society for Strategic Studies in Radiology (IS{sup 3}R), 23-25 August 2007

Energy Technology Data Exchange (ETDEWEB)

Muellner, Ada; Hricak, Hedvig [Memorial Sloan-Kettering Cancer Center, Department of Radiology, New York, NY (United States); Glazer, Gary M. [Stanford University School of Medicine, Department of Radiology, Palo Alto, CA (United States); Reiser, Maximilian F. [Ludwig Maximilian University, Department of Clinical Radiology, Munich (Germany); Bradley, William G. [UCSD Medical Center, Department of Radiology, San Diego, CA (United States); Krestin, Gabriel P. [Erasmus University Medical Center, Department of Radiology, Rotterdam (Netherlands); Thrall, James H. [Massachusetts General Hospital, Boston, MA (United States)

2009-08-15

The International Society for Strategic Studies in Radiology (IS{sup 3}R) brings together thought leaders from academia and industry from around the world to share ideas, points of view and new knowledge. This article summarizes the main concepts presented at the 2007 IS{sup 3}R symposium, providing a window onto trends shaping the future of radiology. Topics addressed include new opportunities and challenges in the field of interventional radiology; emerging techniques for evaluating and improving quality and safety in radiology; and factors impeding progress in molecular imaging and nanotechnology and possible ways to overcome them. Regulatory hurdles to technical innovation and drug development are also discussed more broadly, along with proposals for addressing regulators' concerns and streamlining the regulatory process. (orig.)

Introductory lecture series for first-year radiology residents: implementation, investment and assessment.

Science.gov (United States)

Chapman, Teresa; Chew, Felix S

2013-03-01

A lecture series aimed at providing new radiology residents a rapid course on the fundamental concepts of professionalism, safety, and interpretation of diagnostic imaging was established. Evaluation of the course's educational value was attempted through surveys. Twenty-six live 45-minute lectures presented by 16 or 17 faculty members were organized exclusively for the first class of radiology residents, held over a 2-month period at the beginning of certain weekdays. Online surveys were conducted after the course to gather feedback from residents. Average resident rotation evaluation scores were measured over the first semester for the two classes before and after this new course implementation. The lecture series was successfully organized and implemented. A total of 33 residents sat through the course over three summers. Faculty reported a reasonable number of preparation hours, and 100% of residents indicated they valued the course. Comparison of class average evaluation scores before and after the existence of this 2-month course did not significantly change. This collection of introductory lectures on professionalism, safety, and diagnostic imaging, delivered early in the first year of the radiology residency, requires a reasonable number of invested preparation hours by the faculty but results in a universal increase in resident confidence. However, we were unable to demonstrate an objective improvement in resident performance on clinical rotations. Copyright © 2013 AUR. Published by Elsevier Inc. All rights reserved.

Diagnosis of cystocele--the correlation between clinical and radiological evaluation.

Science.gov (United States)

Altman, Daniel; Mellgren, Anders; Kierkegaard, Jonas; Zetterström, Jan; Falconer, Christian; López, Annika

2004-01-01

In patients with genital prolapse involving several compartments simultaneously, radiologic investigation can be used to complement the clinical assessment. Contrast medium in the urinary bladder enables visualization of the bladder base at cystodefecoperitoneography (CDP). The aim of the present study was to evaluate the correlation between clinical examination using the Pelvic Organ Prolapse Quantification system (POP-Q) and CDP. Thirty-three women underwent clinical assessment and CDP. Statistical analysis using Pearson's correlation coefficient ( r) demonstrated a wide variability between the current definition of cystocele at CDP and POP-Q ( r=0.67). An attempt to provide an alternative definition of cystocele at CDP had a similar outcome ( r=0.63). The present study demonstrates a moderate correlation between clinical and radiologic findings in patients with anterior vaginal wall prolapse. It does not support the use of bladder contrast at radiologic investigation in the routine preoperative assessment of patients with genital prolapse.

10CFR50.59 safety evaluations

International Nuclear Information System (INIS)

Grime, L.; Page, E.

1987-01-01

As a plant changes from the design phase to the operational phase, new regulations and standards apply. One such regulation is 10CFR50.59 on safety evaluations. Once an operating license is issued, it is mandatory to submit all applicable changes, tests, and experiments to the safety evaluation process. As preparation for this transition, Detroit Edison had procedures in place and conducted personnel training. Reviews of the safety engineering were conducted by the on-site review board. The off-site board delegated detailed reviews of most safety evaluations to the independent safety evaluation group (ISEG). The on-site group review included presentation of complete design packages by engineers. The ISEG and off-site review group's activity focused on safety evaluation. This paper addresses industry trends that were studied, Detroit Edison's recent actions, and industry issues related to 10CFR50.59 safety evaluations

Radiologic safety program for ionizing radiation facilities in Parana, Brazil; Programa de seguridad radiologica para las oficinas de salud en Parana, Brasil

Energy Technology Data Exchange (ETDEWEB)

Schmidt, M.F.S.; Tilly Junior, J.G. [Secretaria de Saude do Estado do Parana, Curitiba, PR (Brazil)

1997-12-31

A radiologic safety program for inspection, licensing and control of the use of ionizing radiation in medical, industrial and research facilities in Parana, Brazil is presented. The program includes stages such as: 1- division into implementation phases considering the activity development for each area; 2-use of the existing structure to implement and to improve services. The development of the program will permit to evaluate the improvement reached and to correct operational strategic. As a result, a quality enhancement at the services performed, a reduction for radiation dose exposure and a faster response for emergency situations will be expected 2 refs., 1 fig., 2 tabs.

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

Standards of diagnostic radiological safety

International Nuclear Information System (INIS)

Yacovenco, A.; Ferreira, R.

1996-01-01

Brazil as well as many other countries are characterized for the access differentiated from the society to the products of the development. The lacking in specifications tolerance and mainly requirements of security and they of protection have induced to the inadequate utilization of the procedures technical and products in the area of radiology. We in this context are proposing a new mode of relationships between the diverse levels of intervention and responsibility

Nuclear and radiological regulation in Moldova

International Nuclear Information System (INIS)

Buzdugan, Artur

2013-01-01

The nuclear security and safety legal framework in Moldova has changed significantly over the last 6 years. This has mainly been the result of implementation of IAEA nuclear safety and nuclear security standards, European directives, which are based on new data and evolving concepts at the international level, on adopted in May 2006 of the Law no. 111 On safe deployment of nuclear and radiological activities and establishing on established on March 2007 of a sole regulatory authority - the National Agency for the Regulation of Nuclear and Radiological Activities. (author)

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)

Critical review of the reactor-safety study radiological health effects model. Final report

Energy Technology Data Exchange (ETDEWEB)

Cooper, D.W.; Evans, J.S.; Jacob, N.; Kase, K.R.; Maletskos, C.J.; Robertson, J.B.; Smith, D.G.

1983-03-01

This review of the radiological health effects models originally presented in the Reactor Safety Study (RSS) and currently used by the US Nuclear Regulatory Commission (NRC) was undertaken to assist the NRC in determining whether or not to revise the models and to aid in the revision, if undertaken. The models as presented in the RSS and as implemented in the CRAC (Calculations of Reactor Accident Consequences) Code are described and critiqued. The major elements analyzed are those concerning dosimetry, early effects, and late effects. The published comments on the models are summarized, as are the important findings since the publication of the RSS.

Critical review of the reactor-safety study radiological health effects model. Final report

International Nuclear Information System (INIS)

Cooper, D.W.; Evans, J.S.; Jacob, N.; Kase, K.R.; Maletskos, C.J.; Robertson, J.B.; Smith, D.G.

1983-03-01

This review of the radiological health effects models originally presented in the Reactor Safety Study (RSS) and currently used by the US Nuclear Regulatory Commission (NRC) was undertaken to assist the NRC in determining whether or not to revise the models and to aid in the revision, if undertaken. The models as presented in the RSS and as implemented in the CRAC (Calculations of Reactor Accident Consequences) Code are described and critiqued. The major elements analyzed are those concerning dosimetry, early effects, and late effects. The published comments on the models are summarized, as are the important findings since the publication of the RSS

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

Ambulatory phlebectomy at radiologic outpatient clinic

International Nuclear Information System (INIS)

Yoon, Chang Jin; Kang, Sung Gwon; Choi, Sang Il; Lee, Whal; Chung, Jin Wook; Park, Jae Hyung

2007-01-01

To evaluate safety, efficacy, and patient's satisfaction of an ambulatory phlebectomy, performed at a radiology outpatient clinic. Between 2003 and 2006, an ambulatory phlebectomy was performed in 12 patients. Endovenous radiofrequency ablation was performed through a venotomy. The venotomy was ligated after RF ablation, and the ambulatory phlebectomy was performed. The patients visited the radiology outpatient clinic one day, one week, and 2 months after the procedure. The improvement in the clinical symptoms, cosmetic change in varicosity, and the procedure related complications were evaluated. The patient's satisfaction was evaluated using a 5-grade scale. RF ablation through a venotomy was performed successfully in all 12 patients. On average, 4.5 incisions were made, and 12.5 cm of varicosity had been removed. The mean procedure time was one hour and forty minutes. The complications of the ambulatory phlebectomy were bruising in one patient, and skin pigmentation in another. The complications associated with RF ablation were a hard palpable vein in 7 patients, numbness in 7 patients, and skin pigmentation along the vein in 2 patients. Follow-up duplex sonography was performed at 2 months after the procedure, showed complete occlusion in all 12 patients. The clinical symptoms had improved in 11 patients, and the varicosity disappeared cosmetically in 11 patients. An ambulatory phlebectomy, combined with RF ablation of the greater saphenous vein, can be performed safely and effectively at a radiology outpatient clinic

Ambulatory phlebectomy at radiologic outpatient clinic

Energy Technology Data Exchange (ETDEWEB)

Yoon, Chang Jin; Kang, Sung Gwon; Choi, Sang Il [Seoul National University Bundang Hospital, Seongnam (Korea, Republic of); Lee, Whal; Chung, Jin Wook; Park, Jae Hyung [Seoul National University, Medical College, Seoul (Korea, Republic of)

2007-03-15

To evaluate safety, efficacy, and patient's satisfaction of an ambulatory phlebectomy, performed at a radiology outpatient clinic. Between 2003 and 2006, an ambulatory phlebectomy was performed in 12 patients. Endovenous radiofrequency ablation was performed through a venotomy. The venotomy was ligated after RF ablation, and the ambulatory phlebectomy was performed. The patients visited the radiology outpatient clinic one day, one week, and 2 months after the procedure. The improvement in the clinical symptoms, cosmetic change in varicosity, and the procedure related complications were evaluated. The patient's satisfaction was evaluated using a 5-grade scale. RF ablation through a venotomy was performed successfully in all 12 patients. On average, 4.5 incisions were made, and 12.5 cm of varicosity had been removed. The mean procedure time was one hour and forty minutes. The complications of the ambulatory phlebectomy were bruising in one patient, and skin pigmentation in another. The complications associated with RF ablation were a hard palpable vein in 7 patients, numbness in 7 patients, and skin pigmentation along the vein in 2 patients. Follow-up duplex sonography was performed at 2 months after the procedure, showed complete occlusion in all 12 patients. The clinical symptoms had improved in 11 patients, and the varicosity disappeared cosmetically in 11 patients. An ambulatory phlebectomy, combined with RF ablation of the greater saphenous vein, can be performed safely and effectively at a radiology outpatient clinic.

Safety of Conscious Sedation In Interventional Radiology

International Nuclear Information System (INIS)

Arepally, Aravind; Oechsle, Denise; Kirkwood, Sharon; Savader, Scott J.

2001-01-01

Purpose: To identify rates of adverse events associated with the use of conscious sedation in interventional radiology.Methods: In a 5-month period, prospective data were collected on patients undergoing conscious sedation for interventional radiology procedures (n = 594). Adverse events were categorized as respiratory, sedative, or major adverse events. Respiratory adverse events were those that required oral airway placement, ambu bag, or jaw thrust. Sedation adverse events were unresponsiveness, oxygen saturation less than 90%, use of flumazenil/naloxone, or agitation. Major adverse events were hypotension, intubation, CPR, or cardiac arrest. The frequency of adverse events for the five most common radiology procedures were determined.Results: The five most common procedures (total n = 541) were biliary tube placement/exchange (n = 182), tunneled catheter placement (n 135), diagnostic arteriography (n = 125), vascular interventions (n = 52), and other catheter insertions (n = 46). Rates for respiratory, sedation, and major adverse events were 4.7%, 4.2%, and 2.0%, respectively. The most frequent major adverse event was hypotension (2.0%). Biliary procedures had the highest rate of total adverse events (p < .05) and respiratory adverse events (p < .05).Conclusion: The frequency of adverse events is low with the use of conscious sedation during interventional procedures. The highest rates occurred during biliary interventions

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

International Nuclear Information System (INIS)

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

2016-01-01

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

Use of digital dosemeters for supporting staff radiation safety in paediatric interventional radiology suites

International Nuclear Information System (INIS)

McNeil, S. M.; Lai, P.; Connolly, B. L.; Gordon, C. L.

2013-01-01

Modern-day interventional radiology (IR) procedures impart a wide range of occupational radiation doses to team members. Unlike thermoluminescent badges, digital dosemeters provide real-time dose readings, making them ideal for identifying different components during IR procedures, which influence staff radiation safety. This study focused solely on paediatric IR (PIR) cases. Digital dosemeters measured the impact of imaging modality, shielding, patient and operator specific factors, on the radiation dose received during various simulated and real live PIR procedures. They recorded potential dose reductions of 10-to 100-fold to each staff member with appropriate use of shielding, choice of imaging method, staff position in the room and complex interplay of other factors. The digital dosemeters were well tolerated by staff. Results highlight some unique radiation safety challenges in PIR that arise from dose increases with magnification use and close proximity of staff to the X-ray beam. (authors)

Use of digital dosemeters for supporting staff radiation safety in paediatric interventional radiology suites.

Science.gov (United States)

McNeil, Sarah M; Lai, Priscilla; Connolly, Bairbre L; Gordon, Christopher L

2013-12-01

Modern-day interventional radiology (IR) procedures impart a wide range of occupational radiation doses to team members. Unlike thermoluminescent badges, digital dosemeters provide real-time dose readings, making them ideal for identifying different components during IR procedures, which influence staff radiation safety. This study focused solely on paediatric IR (PIR) cases. Digital dosemeters measured the impact of imaging modality, shielding, patient and operator specific factors, on the radiation dose received during various simulated and real live PIR procedures. They recorded potential dose reductions of 10- to 100-fold to each staff member with appropriate use of shielding, choice of imaging method, staff position in the room and complex interplay of other factors. The digital dosemeters were well tolerated by staff. Results highlight some unique radiation safety challenges in PIR that arise from dose increases with magnification use and close proximity of staff to the X-ray beam.

Radiological, health, and safety, and occurrence reporting system audit report, Rifle, Colorado

International Nuclear Information System (INIS)

1993-11-01

This paper describes an audit dated September 14--16, 1993. The performance of the contractors and subcontractors responsible for remedial action work at the former uranium ore processing site at Rifle, Colorado, and the uranium tailings disposal cell at Estes Gulch (Colorado) was reviewed during an audit conducted September 14 through 16, 1993. MK-Ferguson Company (MK-F) is the Remedial Action Contractor (RAC) responsible for engineering and construction management of the Rifle operations. The audit focused on radiological issues, occupational safety and health (OS ampersand H) issues, and the Occurrence Reporting and Processing System (ORPS). The close-out meeting was held on September 16, 1993, which was attended by representatives of MK-F, the US Department of Energy (DOE), and the Technical Assistance Contractor (TAC)

PWR reload safety evaluation methodology

International Nuclear Information System (INIS)

Doshi, P.K.; Chapin, D.L.; Love, D.S.

1993-01-01

The current practice for WWER safety analysis is to prepare the plant Safety Analysis Report (SAR) for initial plant operation. However, the existing safety analysis is typically not evaluated for reload cycles to confirm that all safety limits are met. In addition, there is no systematic reanalysis or reevaluation of the safety analyses after there have been changes made to the plant. The Westinghouse process is discussed which is in contrast to this and in which the SAR conclusions are re-validated through evaluation and/or analysis of each reload cycle. (Z.S.)

The responsible by the radiological safety in the industry. Among the labour environment and the today technology

International Nuclear Information System (INIS)

Adrian T, W.

2006-01-01

Inside the industrial applications of the sealed radioactive sources, there are clearly exist two defined branches for which these materials are used: radioactive sources used in fixed equipment and in mobile ones. These devices are used in a countless of applications and every time with more advanced technological systems. This requires a permanent improvement inside the training of the responsible one and in turn it introduces an obligatory change to other intervention groups during the useful life of the device. The accident risks to those that are associate the use of these equipment, they are errors during the operation, undue use, maintenance carried out by personal without knowledge, flaws of human type or negligence and incidents happened during the transport. All these 'risks' its are surrounded of different groups of factors that influence during the safe use of the radioactive material, inside the installation of one way or another. Then it stands out the importance of implanting aspects of 'Safety Culture', evaluations of aptitude of the responsible one for the radiological safety, introduction of improvements in aspects of quality and communication of risks, chord to what indicates the normative of the Argentine Republic and the international requirements, which will be approached in the present work. (Author)

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

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

Case-oriented computer-based-training in radiology: concept, implementation and evaluation

Science.gov (United States)

Dugas, Martin; Trumm, Christoph; Stäbler, Axel; Pander, Ernst; Hundt, Walter; Scheidler, Jurgen; Brüning, Roland; Helmberger, Thomas; Waggershauser, Tobias; Matzko, Matthias; Reiser, Maximillian

2001-01-01

Background Providing high-quality clinical cases is important for teaching radiology. We developed, implemented and evaluated a program for a university hospital to support this task. Methods The system was built with Intranet technology and connected to the Picture Archiving and Communications System (PACS). It contains cases for every user group from students to attendants and is structured according to the ACR-code (American College of Radiology) [2]. Each department member was given an individual account, could gather his teaching cases and put the completed cases into the common database. Results During 18 months 583 cases containing 4136 images involving all radiological techniques were compiled and 350 cases put into the common case repository. Workflow integration as well as individual interest influenced the personal efforts to participate but an increasing number of cases and minor modifications of the program improved user acceptance continuously. 101 students went through an evaluation which showed a high level of acceptance and a special interest in elaborate documentation. Conclusion Electronic access to reference cases for all department members anytime anywhere is feasible. Critical success factors are workflow integration, reliability, efficient retrieval strategies and incentives for case authoring. PMID:11686856

Case-oriented computer-based-training in radiology: concept, implementation and evaluation

Directory of Open Access Journals (Sweden)

Helmberger Thomas

2001-10-01

Full Text Available Abstract Background Providing high-quality clinical cases is important for teaching radiology. We developed, implemented and evaluated a program for a university hospital to support this task. Methods The system was built with Intranet technology and connected to the Picture Archiving and Communications System (PACS. It contains cases for every user group from students to attendants and is structured according to the ACR-code (American College of Radiology 2. Each department member was given an individual account, could gather his teaching cases and put the completed cases into the common database. Results During 18 months 583 cases containing 4136 images involving all radiological techniques were compiled and 350 cases put into the common case repository. Workflow integration as well as individual interest influenced the personal efforts to participate but an increasing number of cases and minor modifications of the program improved user acceptance continuously. 101 students went through an evaluation which showed a high level of acceptance and a special interest in elaborate documentation. Conclusion Electronic access to reference cases for all department members anytime anywhere is feasible. Critical success factors are workflow integration, reliability, efficient retrieval strategies and incentives for case authoring.

Radiological safety at Argonne National Laboratory's heavy ion research facility

International Nuclear Information System (INIS)

Cooke, R.H.; Wynveen, R.A.

1985-01-01

This paper discusses the radiological safety system to be employed at the Argonne tandem-linac accelerator system (ATLAS). The design parameters of ATLAS that affect safety have remained unchanged since ATLAS construction began in 1982. This paper will present the details of the hardware, the administrative controls, and the radiation monitoring that will be in effect when beam is produced in April 1985. The experimental hall utilizing the maximum energy beam (proportional27 MeV per nucleon) from the completed ATLAS has been partitioned with shielding blocks into its final configuration. Because scientists want access to some of the partitioned-off areas while beam is present in other areas, an interlock and logic system allowing such occupancy has been designed. The rationale and hardware of the system will be discussed. Since one of the potential radiation hazards is high-energy forward-directed neutrons from any location where the beam impinges (such as collimators, bending and focussing systems, experimental targets, and beam stops), radiation surveys and hazard assessments are necessary for the administrative controls that allow occupancy of various areas. Because of the various uses of ATLAS, neutrons (the dominant beam hazard) will be non-existent in some experiments and will be of energies > or approx.10 MeV for a few experiments. These conditions may exist at specific locations during beam preparation but may change rapidly when beam is finally delivered to an experimental area. Monitoring and assessing such time varying and geographically changing hazards will be a challenge since little data will be available on source terms until various beams are produced of sufficient intensity and energy to make measurements. How the operating division for ATLAS and the Argonne safety division are addressing this aspect through administrative controls will also be discussed. (orig./HSI)

Radiological safety and GMP in the bulk batch manufacturing, formulation and dispensing of radiopharmaceuticals

International Nuclear Information System (INIS)

Thulasidhasan, A.; Tiwary, Bikash; Kumar, Uma Sheri; Kale, Pooja; Tiwary, Richa; Gaurav, Ananad; Shah, B.K.; Topale, P.D.; Prabhakar, G.; Sachdev, S.S.

2010-01-01

Full text: Radiopharmaceutical Program of BRIT is involved in the manufacturing of ready to use radiopharmaceuticals for therapy for the last three decades. Ready to use Radiopharmaceutical products include, 131 I-Sodium iodide solution and capsules for thyroid carcinoma and metastatic lesions, 131 I MIBG injection for diagnosis and therapy of adrenal medullae tumors and their mets, 153 Sm-EDTMP injection and 32 P- Sodium orthophosphate injection for bone pain palliative treatment. BRIT's radiopharmaceutical production facility is a radioisotope laboratory classified as Type-III facility for handling radioisotopes of Group-II, Group-III and Group-IV approved by AERB. This facility meets all the radiological safety requirements as per AERB guidelines. Production of above mentioned radiopharmaceuticals is carried out in Production Plants (PP), β, γ Glove boxes (GB) and Fume hoods (FH). Typical production procedure involves bulk processing, formulation, sterilization and dispensing of doses. Production Plants (PP) are exclusively designed facilities to carry out the production in a radiologically safe manner, at the same time maintaining aseptic conditions required for injectables as per the current GMP. Each production plant has a leak tight Isolator box, made up of high quality SS which has provisions for remote handling devices like, Tongs, dispensing systems, service points for vacuum, gas, compressed air, water and electric power. This Isolator box is shielded from all sides by required amount of lead (2 inch or 4 inch), and has an access port called 'Transport Port Box' with double door transport lock and is equipped with a trolley. Two filter unit systems are fitted at the top of the plant and each unit comprises of activated Charcoal filter and HEPA filter in tandem, this in turn is connected to special exhaust meant for radioactive gases. Similarly, the designs of β, γ Glove boxes (GB) and Fume hoods (FH) also incorporate all radiological safety features

Evaluation of radiological exposure from Plowshare applications, 1967--1975

International Nuclear Information System (INIS)

Barton, C.J.; Kaye, S.V.

1975-08-01

A review of the highlights and accomplishments of the nine-year program, FY 1967-75, at ORNL on the evaluation of the radiological exposure from Plowshare applications is presented. Conclusions based on the studies summarized are given. Chronological lists of presentations, reports and open literature publications on the various investigations of the program are appended to the report. (auth)

Current radiology. Volume 5

International Nuclear Information System (INIS)

Wilson, G.H.; Hanafee, W.N.

1984-01-01

This book contains 10 selections. They are: Nuclear Magnetic Resonance Imaging, Interventional Vascular Radiology, Genitourinary Radiology, Skeletal Radiology, Digital Subtraction Angiography, Neuroradiology, Computed Tomographic Evaluation of Degenerative Diseases of the Lumbar Spine, The Lung, Otolaringology and Opthalmology, and Pediatric Radiology: Cranial, Facial, Cervical, Vertebral, and Appendicular

Qualitative safety analysis in accelerator based systems

International Nuclear Information System (INIS)

Sarkar, P.K.; Chowdhury, Lekha M.

2006-01-01

In recent developments connected to high energy and high current accelerators, the accelerator driven systems (ADS) and the Radioactive Ion Beam (RIB) facilities come in the forefront of application. For medical and industrial applications high current accelerators often need to be located in populated areas. These facilities pose significant radiological hazard during their operation and accidental situations. We have done a qualitative evaluation of radiological safety analysis using the probabilistic safety analysis (PSA) methods for accelerator-based systems. The major contribution to hazard comes from a target rupture scenario in both ADS and RIB facilities. Other significant contributors to hazard in the facilities are also discussed using fault tree and event tree methodologies. (author)

Radiological evaluation of lung volume among Koreans with silicosis

International Nuclear Information System (INIS)

Rhee, Byung Chull

1975-01-01

1. Radiological evaluation of lung volumes was carried out thirty Korean males patients with silicosis, and following results were obtained. 2. The mean radiological lung volume among those patients was 7,587 ml. 3. When compared with the group of normal Korean male adults ranging from 31 to 55 years of age, the mean lung volume was increased by 2,346 ml. 4. The lung volume of these patients was even slightly larger than that of the group of Korean athletes of all ages. 5. On the other hand, the vital capacity in patients with silicosis was markedly diminished, the mean vital capacity being 2,909 ml. 6. The patients with silicosis also revealed emphysematous changes in the lung as well as increased residual volumes. The vital capacity was smallest in the latest stage.

Dose Evaluation and Quality Criteria in Dental Radiology

International Nuclear Information System (INIS)

Gori, C.; Rossi, F.; Stecco, A.; Villari, N.; Zatelli, G.

2000-01-01

Radioprotection in dental radiology is of particular interest in the framework of the Revised Medical Exposure Directive for the great number of examinations involving the adult as well as the paediatric population (Article 9: Special Practice). The present study is intended to find the quality criteria of orthodontic imaging and for evaluating the dose absorbed within the dental and maxillary volume in connection with radiological examinations performed with either spiral CT, dental panoramic tomography or teleradiography. The X ray dose to organs sited in the body, neck, ocular and intracranial area was measured using lithium fluoride dosemeters, positioned in a Rando phantom. Quality criteria have been established by an expert radiologist considering the diagnostic information obtained in the images. The dosimetric data obtained were comparable with other authors', although with some differences due to technical characteristics. These result data are useful for choosing the patient's diagnostic path, considering the radiobiological risk associated with increasing orthodontic imaging. (author)

Model review and evaluation for application in DOE safety basis documentation of chemical accidents - modeling guidance for atmospheric dispersion and consequence assessment

Energy Technology Data Exchange (ETDEWEB)

Lazaro, M. A. [Argonne National Lab. (ANL), Argonne, IL (United States); Woodarad, K. [Argonne National Lab. (ANL), Argonne, IL (United States); Hanna, S. R. [Argonne National Lab. (ANL), Argonne, IL (United States); Hesse, D. J. [Argonne National Lab. (ANL), Argonne, IL (United States); Huang, J. -C. [Argonne National Lab. (ANL), Argonne, IL (United States); Lewis, J. [Argonne National Lab. (ANL), Argonne, IL (United States); Mazzola, C. A. [Argonne National Lab. (ANL), Argonne, IL (United States)

1997-09-01

The U.S. Department of Energy (DOE), through its Defense Programs (DP), Office of Engineering and Operations Suppon, established the Accident Phenomenology and Consequence (AP AC) Methodology Evaluation Program to identify and evaluate methodologies and computer codes to support accident phenomenological and consequence calculations for both radiological and nonradiological materials at DOE facilities and to identify development needs. The program is also intended to define and recommend "best or good engineering/safety analysis practices" to be followed in preparing ''design or beyond design basis" assessments to be included in DOE nuclear and nonnuclear facility safety documents. The AP AC effort is intended to provide scientifically sound and more consistent analytical approaches, by identifying model selection procedures and application methodologies, in order to enhance safety analysis activities throughout the DOE complex.

Proceedings of the 7th National Congress of the Mexican Society of Radiological Safety C.A.; Memorias del 7. Congreso Nacional de Sociedad Mexicana de Seguridad Radiologica A.C.

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-09-01

The Mexican Society of Radiological Safety, celebrates on this time the 100 Anniversary of the radioactivity discovery, phenomenon coined by Marie Curie in 1898 and discover by Henry Beckerel in March 1896, when both were working with natural radioactive isotopes. Subsequently, on the new age of Physics, the use of radioactive isotopes was impulse by the invention of Cyclotron made by Dr. Ernest Orland Lawrence in the United States, which permits the manufacturing of tens of artificial radioactive isotopes which convert its in an indispensable tool in Medicine, Industry, Research, Agriculture and other disciplines, by its wide variety of applications, creating the radiological safety culture by the implicit risk in the use of these materials. From its creation in 1976, our society was removing to promote the radiological safety and two years each celebrates its National Congress removing specialists in this discipline and invite new generations to awake their interest by this useful field. (Author).

Radiological incidents in radiotherapy

International Nuclear Information System (INIS)

Hobzova, L.; Novotny, J.

2008-01-01

In many countries a reporting system of radiological incidents to national regulatory body exists and providers of radiotherapy treatment are obliged to report all major and/or in some countries all incidents occurring in institution. State Office for Nuclear Safety (SONS) is providing a systematic guidance for radiotherapy departments from 1997 by requiring inclusion of radiation safety problems into Quality assurance manual, which is the basic document for obtaining a license of SONS for handling with sources of ionizing radiation. For that purpose SONS also issued the recommendation 'Introduction of QA system for important sources in radiotherapy-radiological incidents' in which the radiological incidents are defined and the basic guidance for their classification (category A, B, C, D), investigation and reporting are given. At regular periods the SONS in co-operation with radiotherapy centers is making a survey of all radiological incidents occurring in institutions and it is presenting obtained information in synoptic communication (2003 Motolske dny, 2005 Novy Jicin). This presentation is another summary report of radiological incidents that occurred in our radiotherapy institutions during last 3 years. Emphasis is given not only to survey and statistics, but also to analysis of reasons of the radiological incidents and to their detection and prevention. Analyses of incidents in radiotherapy have led to a much broader understanding of incident causation. Information about the error should be shared as early as possible during or after investigation by all radiotherapy centers. Learning from incidents, errors and near misses should be a part of improvement of the QA system in institutions. Generally, it is recommended that all radiotherapy facilities should participate in the reporting, analyzing and learning system to facilitate the dissemination of knowledge throughout the whole country to prevent errors in radiotherapy.(authors)

Evaluation of long term radiological impact on population close to remediated uranium mill tailings storages

International Nuclear Information System (INIS)

Kerouanton, David; Delgove, Laure

2008-01-01

A methodology is elaborated in order to evaluate the long term radiological impact of remediated uranium mill tailings storage. Different scenarios are chosen and modelled to cover future evolution of the tailings storages. Radiological impact is evaluated for different population such as adults and children living in the immediate vicinity or directly on the storage, road workers or walkers on the storage. Equation and methods are detailed. (author)

Radiological evaluation of esophageal motility and gastroesophageal reflux disease; Funktionsstoerungen des Oesophagus. Radiologische Diagnostik

Energy Technology Data Exchange (ETDEWEB)

Schima, W. [Abt. Roentgen fuer Konservative Faecher, Universitaetsklinik fuer Radiodiagnostik, Wien (Austria); Pokieser, P. [Abt. Roentgen fuer Chirurgische Faecher, Universitaetsklinik fuer Radiodiagnostik, Wien (Austria); Schober, E. [Abt. Roentgen fuer Konservative Faecher, Universitaetsklinik fuer Radiodiagnostik, Wien (Austria)

1995-10-01

Radiological evaluation of esophageal motility and the lower esophageal sphincter has gained increased attention in recent years. Videofluoroscopic investigation of esophageal motor function is superior to static film radiography, as repeated analysis of the videotaped recordings is possible. With emphasis on radiological techniques, normal esophagel physiology and motility and a variety of esophageal motor disorders are discussed in this review paper. Radiological evaluation of gastroesophageal reflux and reflux esophagitis is described. Clinical and radiological findings in esophageal motility disorders and gastroesophageal reflux disease and the radiological efficacy compared to that of manometry and pH-metry are discussed. (orig.) [Deutsch] Die radiologische Untersuchung des Oesophagus kann nicht nur strukturelle Veraenderungen, sondern auch funktionelle Stoerungen mit einer hohen Treffsicherheit nachweisen. Die Videokinematographie ist hierbei der konventionellen Roentgenuntersuchung aufgrund der Moeglichkeit der wiederholten Analyse ueberlegen. Ziel der vorliegenden Uebersicht ist es, prinzipiell das radiologische Erscheinungsbild der normalen Funktion sowie diagnostische Kriterien fuer verschiedene Motilitaetsstoerungen zu demonstrieren. Weiterhin werden auch die verschiedenen Moeglichkeiten der radiologischen Refluxpruefung zur Untersuchung der Funktion des gastrooesophagealen Sphinkters verglichen und deren Wert diskutiert. Die Pruefung der Funktion von Oesophagus und gastrooesophagealem Sphinkter als ein integraler Bestandteil der Roentgenuntersuchung der Speiseroehre verbessert deren Treffsicherheit, wodurch die radiologische Untersuchung die primaere diagnostische Methode bei Patienten mit Schluckstoerungen darstellt. (orig.)

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

Conduct and results of the Interagency Nuclear Safety Review Panel's evaluation of the Ulysses space mission

International Nuclear Information System (INIS)

Sholtis, J.A. Jr.; Gray, L.B.; Huff, D.A.; Klug, N.P.; Winchester, R.O.

1991-01-01

The recent 6 October 1990 launch and deployment of the nuclear-powered Ulysses spacecraft from the Space Shuttle Discovery culminated an extensive safety review and evaluation effort by the Interagency Nuclear Safety Review Panel (INSRP). After more than a year of detailed independent review, study, and analysis, the INSRP prepared a Safety Evaluation Report (SER) on the Ulysses mission, in accordance with Presidential Directive-National Security Council memorandum 25. The SER, which included a review of the Ulysses Final Safety Analysis Report (FSAR) and an independent characterization of the mission risks, was used by the National Aeronautics and Space Administration (NASA) in its decision to request launch approval as well as by the Executive Office of the President in arriving at a launch decision based on risk-benefit considerations. This paper provides an overview of the Ulysses mission and the conduct as well as the results of the INSRP evaluation. While the mission risk determined by the INSRP in the SER was higher than that characterized by the Ulysses project in the FSAR, both reports indicated that the radiological risks were relatively small. In the final analysis, the SER proved to be supportive of a positive launch decision. The INSRP evaluation process has demonstrated its effectiveness numerous times since the 1960s. In every case, it has provided the essential ingredients and perspective to permit an informed launch decision at the highest level of our Government

Evaluation of periodic safety status analyses

International Nuclear Information System (INIS)

Faber, C.; Staub, G.

1997-01-01

In order to carry out the evaluation of safety status analyses by the safety assessor within the periodical safety reviews of nuclear power plants safety goal oriented requirements have been formulated together with complementary evaluation criteria. Their application in an inter-disciplinary coopertion covering the subject areas involved facilitates a complete safety goal oriented assessment of the plant status. The procedure is outlined briefly by an example for the safety goal 'reactivity control' for BWRs. (orig.) [de

Safety Committees for Argentinean Research Reactor - Regulatory Issues

International Nuclear Information System (INIS)

Perrin, Carlos D.

2009-01-01

In the field of radiological and nuclear safety, the Nuclear Regulatory Authority (ARN) of Argentina controls three research reactors and three critical assemblies, by means of evaluations, audits and inspections, in order to ensure the fulfillment of the requirements established in the Licenses, in the Regulatory Standards and in the Mandatory Documentation in general. From the Nuclear Regulatory Authority's point of view, within the general process of research reactors safety management, the Operational Organization self verification of radiological and nuclear safety plays an outstanding role. In this aspect the ARN has established specific requirements in the Regulatory Standards, in the Operation Licenses and in the Operational Limits and Conditions. These requirements include the figure of different safety committees, which act as reviewers or advisers in diverse situations. This paper describes the main characteristics of the committees, their function, scope and the regulatory documents where the requirements are included. (author)

Upgrade in the CNSNS of the determination process about the importance for the impact evaluation to the safety of defaults or violations in the national nuclear facilities

International Nuclear Information System (INIS)

Espinosa V, J. M.; Jauregui Ch, V.

2014-10-01

Inside the process of Impact Evaluation to the Safety of the Direccion General Adjunta de Seguridad Nuclear of the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) the Significance Determination Process (SDP) is used, developed by the United States Nuclear Regulatory Commission (US NRC), to evaluate the violations or defaults to the regulatory framework and to determine its importance to the risk by means of a fixed color: Green (Very low impact to the safety), White (Low impact to moderate to the safety), Yellow (Substantial impact to the safety) or Red (High impact to the safety). All this inside the seven safety foundations of the Reactor Oversight Process: Initiator Events, Mitigation Systems, Integrity of the Barriers, Preparation for Emergencies, Occupational Radiological Safety, Radiological Safety of the Public and Physical Safety. At present the US NRC has developed a new version of the SDP, which presents changes in its structure and the opportunity of carrying out informed evaluations in risk, with more detail about the violations or defaults that happen in different areas. The CNSNS carries out the adaptation of this last version of the SDP in order to have an updated tool for the violations and defaults characterization to the regulatory framework happened in the nuclear power plant of Laguna Verde. In this article is mentioned the legal framework that confers the CNSNS the attributions to impose urgency measures and administrative sanctions to its licensees, also is established the definition of the different colors that the SDP contemplates in function of the increased risk (ΔCdf), a description of the SDP objectives and the elements that conform it is presented, in the same way some examples to illustrate its application are raised. Finally, the steps to continue for their implementation are mentioned. (Author)

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)

Radiological consequence analysis. Report on the work package 10. Preliminary safety analysis for the site Gorleben; Radiologische Konsequenzanalyse. Bericht zum Arbeitspaket 10. Vorlaeufige Sicherheitsanalyse fuer den Standort Gorleben

Energy Technology Data Exchange (ETDEWEB)

Larue, Juergen; Baltes, Bruno; Fischer, Heidemarie; Frieling, Gerd; Kock, Ingo; Navarro, Martin; Seher, Holger

2013-02-15

Work package 10 of the preliminary safety analysis for the site Gorleben concerns the analysis of release scenarios and the radiological consequences. The report includes the description of the applied methodology, the concept for the mathematical description of scenarios, the variety of scenarios for the radiological consequence analysis with the definition of the reference scenario. The database for the calculation covers geology and hydrology, the final repository concept and the process of the final disposal system. The used models were the one-phase transport model MARINE and the two-phase transport model TOUGH2. The report summarizes the results including an evaluation of the realization of the demonstration concept with respect to solution transport, fluid transport, robustness of the modeling results and analogy discussion to other disposal variants (i.e. borehole disposal and storage of transport or storage casks).

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)

Radiologic considerations

International Nuclear Information System (INIS)

Judge, L.O.

1987-01-01

An increasing variety of imaging modalities as well as refinements of interventional techniques have led to a resurgence of radiologic interest and participation in urolithiasis management. Judicious selection of the diagnostic examination, close monitoring during the procedure, consultation with urologic colleagues, and a careful regard for radiation safety guidelines define the role of the radiologist in renal stone disease

Annual report on occupational safety 1985

International Nuclear Information System (INIS)

1986-09-01

This report presents information on occupational safety relating to the Company's employees for the year 1985, and compares data with figures for the previous year. The following headings are listed: principle activities of BNFL, general policy and organisation, radiological safety, including whole body, skin and extremity, and internal organ doses, non-radiological safety, incidents reportable to the health and safety executive. (U.K.)

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)

The First Report on Evaluating the Thoracic Radiology of the Medical Institutions for Pneumoconiosis in Korea

International Nuclear Information System (INIS)

Lee, Won Jeong; Chu, Sang Deok; Park, So Young; Choi, Byung Soon; Park, Jai Soung; Kim, Sung Jin; Ko, Kyung Sun

2010-01-01

The pnuemoconiotic findings on chest radiograph for pneumoconiosis are affected by the technique, the equipment and the reading environment. We report here on the results of evaluating the thoracic radiology of the Medical Institutions for Pneumoconiosis (MIPs). For the first time, we visited the MIPs to evaluate the thoracic radiography that is used to treat patients with pneumoconiotic complications, and this included evaluating the equipment and the technical parameters for thoracic radiography, the computed tomography, the education for quality assurance health care and the reading environment. We used the guideline published by the Occupational Safety and Health Research Institute (OSHRI). Ten images were randomly picked from the MIPs for evaluating the image quality, and then these were rated by two experienced chest radiologists for pneumoconiosis according to the criteria of the OSHRI. Of the 33 institutions, the failed group (mean<60) scored 36.4% for radiological technique (RT), 30.3% for image quality (IQ) and 21.2% for the reading environment (RE). There were statistically significantly differences between the passed and failed groups for RT (75.8 ± 9.1 vs. 40.8 ± 13.6, p<0.001), for IQ (68.3 ± 5.8 vs. 47.8 ± 9.4, p<0.001) and for RE (78.3 ± 15.8 vs. 18.3 ± 21.9, p<0.001). The group that received education was significantly higher for the RT (68.7 vs. 53.2, p=0.032), the IQ (65.3 vs. 56.6, p=0.039) and the RE (76.2 vs. 47.0, p=0.005) than that for the group that didn't receive education. The MIPs need surveillance and education for improving the quality assurance health care in thoracic radiography for treating patients with pneumoconiosis and who have complications

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)

Medical radiology terminology

International Nuclear Information System (INIS)

1986-01-01

Standardization achievements in the field of radiology induced the IEC to compile the terminology used in its safety and application standards and present it in publication 788 (1984 issue), entitled 'Medical radiology terminology'. The objective pursued is to foster the use of standard terminology in the radiology standards. The value of publication 788 lies in the fact that it presents definitions of terms used in the French and English versions of IEC standards in the field of radiology, and thus facilitates adequate translation of these terms into other languages. In the glossary in hand, German-language definitions have been adopted from the DIN standards in cases where the French or English versions of definitions are identical with the German wording or meaning. The numbers of DIN standards or sections are then given without brackets, ahead of the text of the definition. In cases where correspondance of the various texts is not so good, or reference should be made to a term in a DIN standard, the numbers are given in brackets. (orig./HP) [de

Digital subtraction angiography in head and neck radiology

Energy Technology Data Exchange (ETDEWEB)

Carmody, R F; Seeger, J F; Smith, R L; Horsley, W W; Miller, R W

1984-07-01

Intravenous digital subtraction angiography (IVDSA) was used to evaluate 44 patients with suspected otolaryngologic abnormalities. Sixteen had IVDSA for pulsatile tinnitus or suspected glomus tumor of the petrous bone. Nine patients were evaluated because of pulsatile neck masses, and 12 others had suspected tumors of the neck, face, and paranasal sinuses. Seven had IVDSA following head and neck trauma. The technique of examination is described. The current indications of IVDSA in head and neck radiology are discussed. It is concluded that IVDSA is a suitable substitute for conventional angiography for many otolaryngologic conditions and, because of its safety, can be used more liberally.

Radiation safety knowledge of medical center radiology technologists in southern Taiwan

Energy Technology Data Exchange (ETDEWEB)

Su Wen-Chuan; Huang Ying-Fong; Chen Cheng-Chung; Chang Pao-Shu [Kaohsiung Medical University, Taiwan (China)

2000-05-01

People who live in Taiwan are getting more and more afraid of radiation. Sometimes the phobia results from distorted knowledge. Radiology technologists, in one hand, are more well-educated in radiation and, in the other hand, have more chance to expose to radiation when they are operating radiation producing medical instruments in their daily life. So we are interested in whether they have enough knowledge to protect themselves. We pick up the radiology technology board examination to make the questionnaire for this study. The population is the radiology technologists who work at department of diagnostic radiology, of radiation therapy and nuclear medicine in medical centers. Statistics is then used to see the relationship between knowledge and the factors including gender, age and career period. Based on statistics, we find out that there is significant correlation between the knowledge with age or education level. Elder or lower education level ones has worse knowledge. Continued education may be highly recommended for radiology technologists to avoid occupational radiation injury. (author)

Radiation safety knowledge of medical center radiology technologists in southern Taiwan

International Nuclear Information System (INIS)

Su Wen-Chuan; Huang Ying-Fong; Chen Cheng-Chung; Chang Pao-Shu

2000-01-01

People who live in Taiwan are getting more and more afraid of radiation. Sometimes the phobia results from distorted knowledge. Radiology technologists, in one hand, are more well-educated in radiation and, in the other hand, have more chance to expose to radiation when they are operating radiation producing medical instruments in their daily life. So we are interested in whether they have enough knowledge to protect themselves. We pick up the radiology technology board examination to make the questionnaire for this study. The population is the radiology technologists who work at department of diagnostic radiology, of radiation therapy and nuclear medicine in medical centers. Statistics is then used to see the relationship between knowledge and the factors including gender, age and career period. Based on statistics, we find out that there is significant correlation between the knowledge with age or education level. Elder or lower education level ones has worse knowledge. Continued education may be highly recommended for radiology technologists to avoid occupational radiation injury. (author)

Analysis of conditions to safety and radiological protection of Brazilian research particle accelerators facilities; Analise das condicoes de protecao e seguranca radiologicas das instalacoes com aceleradores de particulas na area de pesquisa no Brasil

Energy Technology Data Exchange (ETDEWEB)

Lourenco, Manuel Jacinto Martins

2010-07-01

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)

BNL ALARA Center's development of a computerized radiological assessment and design system (RADS)

International Nuclear Information System (INIS)

Dionne, B.J.; Masciulli, S.; Connelly, J.M.

1993-01-01

The US Department of Energy's (DOE) Office of Health Physics and Industrial Hygiene sponsored a study of Radiological Engineering Programs at selected DOE contractor facilities. This study was conducted to review, evaluate, and summarize techniques and practices that should be considered in the design phase that reduce dose and the spread of radioactive materials during subsequent construction and operation of DOE radiological facilities. As in a previous study on operational ALARA programs, a variety of good-practice documents will be generated. It is envisioned that these documents will serve as a resource to assist radiological engineers in the process of designing radiological facilities, and in performing radiological safety/ALARA design reviews. This paper presents the features for three good-practice documents and related software applications that are being developed based on the findings of this study. The proposed software called Radiological Assessment and Design System (RADS) will be a menu-driven database and spreadsheet program. It will be designed to provide easy, consistent, and effective implementation of the methodologies described in the three good-practice documents. These documents and the associated RADS software will provide the user with the following three functions: (1) enter dose assessment information and data into computer worksheets and provide printed tables of the results which can then be inserted into safety analysis reports or cost-benefit analyses, (2) perform a wide variety of sorts of radiological design criteria from DOE Orders and produce a checklist of the desired design criteria, and (3) enter cost/benefit data and qualitative rating of attributes for various design alternatives which reduce dose into computer worksheets and provide printed reports of cost-effectiveness results

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

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

Safety climate and attitude as evaluation measures of organizational safety.

Science.gov (United States)

Isla Díaz, R; Díaz Cabrera, D

1997-09-01

The main aim of this research is to develop a set of evaluation measures for safety attitudes and safety climate. Specifically it is intended: (a) to test the instruments; (b) to identify the essential dimensions of the safety climate in the airport ground handling companies; (c) to assess the quality of the differences in the safety climate for each company and its relation to the accident rate; (d) to analyse the relationship between attitudes and safety climate; and (e) to evaluate the influences of situational and personal factors on both safety climate and attitude. The study sample consisted of 166 subjects from three airport companies. Specifically, this research was centered on ground handling departments. The factor analysis of the safety climate instrument resulted in six factors which explained 69.8% of the total variance. We found significant differences in safety attitudes and climate in relation to type of enterprise.

Effects of the Platelet Rich Plasma on Apexogenesis in Young Monkeys: Radiological and Hystologycal Evaluation

International Nuclear Information System (INIS)

Petrović, Vanja; Pejčić, Natasa; Rakić, Mia; Leković, V.; Stojić, Ž; Vasić, Una

2012-01-01

Platelet-reach plasma (PRP) is an attractive tool in regenerative medicine due to its ability to stimulate proliferation and differentiation of stem cells. Since dental pulp derived stem cells are recognized as central in apexogenesis, the aim of the study was to evaluate radiologically and histologically effects of PRP on apexogenesis in teeth with immature roots. The study included eight monkeys (Cercopithecus Aethiops) divided in two equal groups for evaluation 3 and 12 months after treatment. All participants obtained the same treatment including pulpotomy and after-treatment with: hydroxiapatite (HA)-incisor and HA+canine PRP. Radiological evaluation was performed using the long cone paralleling technique for recording of defined parameters and histological evaluation was performed using tissue removed en block for the observation of parameters related to apexogenesis. The results obtained radiologically and histologically have shown increase in bridge formation in HA+PRP (75%) group after 3 months comparing to HA group (50%). Contrary to that, after 12 months there were no significant differences between groups. The root delay was not registered in the HA+PRP group contrary to HA group where it was registered in 25% after 12 months. Results of the study suggest that PRP is a powerful tool for intensive and rapid apexogenesis since it offers clear and comprehensive results (mostly in the first three months) which are early radiologically visible without any failure in the proposed requests

Effects of the Platelet Rich Plasma on Apexogenesis in Young Monkeys: Radiological and Hystologycal Evaluation

Energy Technology Data Exchange (ETDEWEB)

Petrović, Vanja; Pejčić, Natasa; Rakić, Mia; Leković, V.; Stojić, Ž [University of Belgrade, School of Dentistry (Serbia); Vasić, Una [University of Belgrade, Faculty of Medicine (Serbia)

2012-07-01

Platelet-reach plasma (PRP) is an attractive tool in regenerative medicine due to its ability to stimulate proliferation and differentiation of stem cells. Since dental pulp derived stem cells are recognized as central in apexogenesis, the aim of the study was to evaluate radiologically and histologically effects of PRP on apexogenesis in teeth with immature roots. The study included eight monkeys (Cercopithecus Aethiops) divided in two equal groups for evaluation 3 and 12 months after treatment. All participants obtained the same treatment including pulpotomy and after-treatment with: hydroxiapatite (HA)-incisor and HA+canine PRP. Radiological evaluation was performed using the long cone paralleling technique for recording of defined parameters and histological evaluation was performed using tissue removed en block for the observation of parameters related to apexogenesis. The results obtained radiologically and histologically have shown increase in bridge formation in HA+PRP (75%) group after 3 months comparing to HA group (50%). Contrary to that, after 12 months there were no significant differences between groups. The root delay was not registered in the HA+PRP group contrary to HA group where it was registered in 25% after 12 months. Results of the study suggest that PRP is a powerful tool for intensive and rapid apexogenesis since it offers clear and comprehensive results (mostly in the first three months) which are early radiologically visible without any failure in the proposed requests.

Radiological evaluation of a liver simulator in comparison to a human real liver

International Nuclear Information System (INIS)

Toledo, Janine M.; Campos, Tarcisio P.R. de

2009-01-01

The present study evaluates the radiological features of a human real healthy liver reproducing its characteristics on a developed liver simulator. The radiological evaluation will be performed through radiological methods such as CT and X-ray images, density and weight measurements, as well as representation of the coloration and texture. According to literature, the liver is the highest weight organ and gland of the body, weighing approximately 1,5 kg. On the liver, the nutrients are absorbed from the digestive tract and are prosecuted and stored for future use by other organs. Also the liver is responsible for the neutralization and elimination of various toxic substances. Thus, it is an interface between the digestive system and the blood. Besides, this organ is the principal source of plasmatic proteins like the albumin, transport of graxos oily acids. Due to its proprieties, the liver holds a large amount of radionuclides on any uptake from external source. The liver simulator was designed to have the same density, weight and corresponding shape. The radiographic image was produced by conventional X-rays machine, in which the radiographic applied parameters were the same applied to abdomen. The result of the radiographic and CT images demonstrates radiological equivalence between the simulator and human real liver. Hounsfield number of the synthetic liver tissue was found on the range of human livers. Therefore, due to its similar shape, chemical composition, radiological response, the liver simulator can be used to investigate ionizing radiation procedures during radiation therapy intervention. (author)

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

Fundamental features and main problems of nuclear power and radiological safety law

International Nuclear Information System (INIS)

Moser, B.

1981-01-01

This report deals on a general basis with the legal spheres affected by the utilisation of nuclear energy and protection from ionising radiation. Following a historical survey of the development both in the field of national legisation in Austria and internationally, the five principal legal spheres are discussed in detail. These are administrative law, liability and insurance law, criminal law, constitutional law and international law. In the foreground of discussion is administrative law, which is mainly of a preventive nature. This also comprises radiological safety law. Next in importance is liability and insurance law, which, in contrast to the former, aims at compensation for damage. Criminal law is also intended to have a preventive effect. Finally, the author discusses the peaceful use of nuclear energy in relation to the constitutional law and the international law in force. (Auth.)

Radiological clerkships as a critical curriculum component in radiology education

International Nuclear Information System (INIS)

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

2011-01-01

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

Decree No. 78/84 of 5 September 1984 regulating safety and radiological protection in mines and related ore treatment and uranium recovery

International Nuclear Information System (INIS)

1984-01-01

This Decree was issued in pursuance of Decree-Law No. 426/83 of 7 December 1983 which provides that safety and radiological protection regulations shall be made for activities involving the mining of uranium and related treatment of uranium. It lays down definitions of technical radiation protection terms and sets out the requirements for permissible concentrations and internal and sets out the requirements for permissible concentrations and internal and external dose-limits for workers and members of the public. The Decree also sets up a Radiological Protection Service responsible for ensuring that the provisions of the Decree are observed. (NEA) [fr

Evaluation on safety issues of SMART

International Nuclear Information System (INIS)

Kim, W. S.; Seol, K. W.; Yoon, Y. K.; Lee, J. H.

2001-01-01

Safety issues on the SMART were evaluated in the light of the compliance with the Ministerial Ordinance of Technical Requirements applying to Nuclear Installations, which was recently revised. Evaluation concludes that regulatory requirements associated with following items have to be developed as the licensing criteria for the SMART: (1) proving the safety of design or materials different form existing reactors; (2) coping with beyond design basis accidents; (3) rulemaking on the safety of reactor safeguard vessel ; (4) ensuring integrity of steam generator tubes; and (5) classifying equipment based on their safety significance. Appropriate actions including implementation of new requirements under development should be taken for safety issues such as diversity of reactivity control and in-service inspection of steam generator tubes that are not complied with the current Technical Requirements. Safety level of the SMART design will be evaluated further by the more detailed assessment according to the Technical Requirements, and additional safety issues will be identified and resolved, if it necessary

West African Journal of Radiology

African Journals Online (AJOL)

... the Science and Technology of Radiology, clinical case reports, discoveries and ... Magnetic Resonance Imaging Diagnoses in the Lumbar Spine of Adults With ... Safety in Pregnancy among radiologists and other Health Workers in Nigeria.

LNG Safety Assessment Evaluation Methods

Energy Technology Data Exchange (ETDEWEB)

Muna, Alice Baca [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); LaFleur, Angela Christine [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2015-05-01

Sandia National Laboratories evaluated published safety assessment methods across a variety of industries including Liquefied Natural Gas (LNG), hydrogen, land and marine transportation, as well as the US Department of Defense (DOD). All the methods were evaluated for their potential applicability for use in the LNG railroad application. After reviewing the documents included in this report, as well as others not included because of repetition, the Department of Energy (DOE) Hydrogen Safety Plan Checklist is most suitable to be adapted to the LNG railroad application. This report was developed to survey industries related to rail transportation for methodologies and tools that can be used by the FRA to review and evaluate safety assessments submitted by the railroad industry as a part of their implementation plans for liquefied or compressed natural gas storage ( on-board or tender) and engine fueling delivery systems. The main sections of this report provide an overview of various methods found during this survey. In most cases, the reference document is quoted directly. The final section provides discussion and a recommendation for the most appropriate methodology that will allow efficient and consistent evaluations to be made. The DOE Hydrogen Safety Plan Checklist was then revised to adapt it as a methodology for the Federal Railroad Administration’s use in evaluating safety plans submitted by the railroad industry.

Optimal safety is the philosophy

International Nuclear Information System (INIS)

Anon.

1990-01-01

In order to promote international sharing of knowledge of radiation dose reduction at nuclear plants, the OECD's Paris-based Nuclear Energy Agency (NEA) has launched plans and preparations for a new institution, the Information System on Occupational Exposure (ISOE). Eight OECD countries are evaluating a pilot project and the NEA is discussing the establishment of a permanent ISOE. The aim is to have instant answers to varied questions on effective dose-reduction techniques, typical doses for particular jobs, dose rates at standard points in plants and the way they are being affected by dose-reduction techniques. With answers based on data from all OECD countries with experience in nuclear power plant operations. At the centre of the nuclear industry's radiological protection is the principle that all radiation doses should be kept as low as reasonably achievable (alara), economic and social factors being taken into account. If this principle were applied beyond radiological protection to safety in general, for example, road safety, it, would lead to much better overall safety. (UK)

Radiological worker training

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-10-01

This Handbook describes an implementation process for core training as recommended in Implementation Guide G441.12, Radiation Safety Training, and as outlined in the DOE Radiological Control Standard (RCS). The Handbook is meant to assist those individuals within the Department of Energy, Managing and Operating contractors, and Managing and Integrating contractors identified as having responsibility for implementing core training recommended by the RCS. This training is intended for radiological workers to assist in meeting their job-specific training requirements of 10 CFR 835. While this Handbook addresses many requirements of 10 CFR 835 Subpart J, it must be supplemented with facility-specific information to achieve full compliance.

Radiological worker training

International Nuclear Information System (INIS)

1998-10-01

This Handbook describes an implementation process for core training as recommended in Implementation Guide G441.12, Radiation Safety Training, and as outlined in the DOE Radiological Control Standard (RCS). The Handbook is meant to assist those individuals within the Department of Energy, Managing and Operating contractors, and Managing and Integrating contractors identified as having responsibility for implementing core training recommended by the RCS. This training is intended for radiological workers to assist in meeting their job-specific training requirements of 10 CFR 835. While this Handbook addresses many requirements of 10 CFR 835 Subpart J, it must be supplemented with facility-specific information to achieve full compliance

Radiological evaluation of chronic hemophilic arthropathy by the Pettersson score: Problems in correlation in adult patients

Energy Technology Data Exchange (ETDEWEB)

Hamel, J.; Pohlmann, H.; Schramm, W.

1988-01-01

This study deals with the distribution and extent of hemophilic arthropathy (HA) in 52 adult patients suffering from severe hemophilia A. A clinical and radiological evaluation was undertaken and the results were compared. The limitations of the currently used radiological scoring system are discussed. (orig.)

Radiologic evaluation of the liver in the alcoholic patient

International Nuclear Information System (INIS)

Peng, J.J.; Hirsch, G.; Posteraro, R.H.; Leo, J.S.; Blackwell, D.E.

1985-01-01

It has been well documented that long-term abuse of alcohol leads to dysfunction of multiple organ systems of the body. The liver, which is the primary organ responsible for alcohol metabolism, is also a major target for damage. Cirrhosis of the liver is the seventh leading cause of death in the United States. The radiologist plays an important role in the evaluation and possibly in the treatment of the conditions which result from alcohol abuse. The advantages and limitations of various radiologic diagnostic modalities in the evaluation of alcoholic liver disease are presented and discussed. 47 references

Investigation of evaluation method for marine radiological impact during an accident

Energy Technology Data Exchange (ETDEWEB)

NONE

2012-08-15

In 2012, JNES carried out to investigate the measurement information of radionuclide released to the ocean at Fukushima Daiichi NPP accident, the foreign regulation for marine radiological impact, and the evaluation method for release and diffusion to the ocean at the accident inside and outside Japan. (author)

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

Evaluation of the Internet precence of diagnostic radiology units at German universities

International Nuclear Information System (INIS)

Seitz, J.; Siegmund, M.; Voelk, M.; Feuerbach, S.; Strotzer, M.

2002-01-01

Purpose. Analyzing the availability and the contents of the internet homepages of the radiological departments of German universities.Material and method. In June and July 2001 the internet homepages of 36 radiological departments of German universities were evaluated in a study. A medical student experienced in using the world wide web examined the websites concerning the following criteria: research, teaching, informations for patients, clinical topics and general information. Additionally an evaluation of the technical standard of the presentation was performed.Results. 31 of the 36 radiological departments presented a homepage in the world wide web. The subject research was presented by 29 institutes. Also 29 departments provided information concerning teaching in their presentations. In 24 cases informations especially for patients were given. In all topics there is a huge variety of the quality and quantity of the provided information throughout the different institutions. 21 homepages available without restriction during the study period; 3 were nearly completely under construction. Multimedia techniques were only used in 2 homepages. The structural hierarchy of the webpages was in the average only two or three levels. Only 6 providers presented an additional version of their homepage in english.Conclusion. In the moment the possibility of internet-presentation is sub-optimal used by the responsible persons of the radiological institutions. The main emphasis is on research and teaching. There is nearly no use of multimedial elements in the presentations. Only a minority of the homepages can be read by international viewers because of the lack of an english version of the pages. (orig.) [de

Development and validation of a questionnaire to evaluate infection control in oral radiology

Science.gov (United States)

Pinelli, Camila; da Silva Tagliaferro, Elaine P; Corrente, José E; Ambrosano, Glaucia M B

2017-01-01

Objectives: To create and validate a questionnaire to evaluate infection control in oral radiology. Methods: The questionnaire was developed after review of the literature, which included published articles and the biosafety protocols available from healthcare agencies. The initial version of the questionnaire was composed of 14 multiple choice questions and was divided into 3 domains on handwashing, disinfection/protection of surfaces and disinfectant used. Content validity was assessed by two expert committees, which reviewed the content and scope of the questionnaire and the relevance of each item, respectively. Reliability was evaluated using test–retest and internal consistency methods with 115 undergraduate dentistry students. Construct validity was assessed using the known-groups technique and factor analysis. The known-groups technique involved 641 undergraduate dentistry students, 20 PhD students and 15 oral radiology professors. In the factor analysis, 3 radiology technicians also participated in addition to the 641 undergraduates, 20 PhD students and 15 oral radiology professors. Results: The content validity results were found to be satisfactory to excellent for the ordinal variables (intraclass correlation coefficient = 0.722–1.000) and good to great for the yes/no questions (kappa = 0.662–0.913) in terms of reliability and good internal consistency (Cronbach's alpha = 0.88). After a factor analysis, some questions were excluded, and the questions were grouped into new domains. Significant differences were observed between answers from different groups. The final version of the questionnaire was composed of nine domains. Conclusions: The questionnaire created was found to exhibit good psychometric properties for assessing infection control in oral radiology. PMID:28112553

ATMOSPHERIC DISPERSION COEFFICIENTS AND RADIOLOGICAL AND TOXICOLOGICAL EXPOSURE METHODOLOGY FOR USE IN TANK FARMS

Energy Technology Data Exchange (ETDEWEB)

GRIGSBY KM

2011-04-07

This report presents the atmospheric dispersion coefficients used in Tank Farms safety analysis. The basis equations for calculating radiological and toxicological exposures are also included. In this revision, the time averaging for toxicological consequence evaluations is clarified based on a review of DOE complex guidance and a review of tank farm chemicals.

Probabilistic evaluation of scenarios in long-term safety analyses. Results of the project ISIBEL; Probabilistische Bewertung von Szenarien in Langzeitsicherheitsanalysen. Ergebnisse des Vorhabens ISIBEL

Energy Technology Data Exchange (ETDEWEB)

Buhmann, Dieter; Becker, Dirk-Alexander; Laggiard, Eduardo; Ruebel, Andre; Spiessl, Sabine; Wolf, Jens

2016-07-15

In the frame of the project ISIBEL deterministic analyses on the radiological consequences of several possible developments of the final repository were performed (VSG: preliminary safety analysis of the site Gorleben). The report describes the probabilistic evaluation of the VSG scenarios using uncertainty and sensitivity analyses. It was shown that probabilistic analyses are important to evaluate the influence of uncertainties. The transfer of the selected scenarios in computational cases and the used modeling parameters are discussed.

Effects of the platelet rich plasma on apexogenesis in young monkeys: Radiological and hystologycal evaluation

Directory of Open Access Journals (Sweden)

Petrović Vanja

2012-01-01

Full Text Available Platelet-reach plasma (PRP is an attractive tool in regenerative medicine due to its ability to stimulate proliferation and differentiation of stem cells. Since dental pulp derived stem cells are recognized as central in apexogenesis, the aim of the study was to evaluate radiologically and histologically effects of PRP on apexogenesis in teeth with immature roots. The study included eight monkeys (Cercopithecus Aethiops divided in two equal groups for evaluation 3 and 12 months after treatment. All participants obtained the same treatment including pulpotomy and after-treatment with: hydroxiapatite (HA-incisor and HA+canine PRP. Radiological evaluation was performed using the long cone paralleling technique for recording of defined parameters and histological evaluation was performed using tissue removed en block for the observation of parameters related to apexogenesis. The results obtained radiologically and histologically have shown increase in bridge formation in HA+PRP (75% group after 3 months comparing to HA group (50%. Contrary to that, after 12 months there were no significant differences between groups. The root delay was not registered in the HA+PRP group contrary to HA group where it was registered in 25% after 12 months. Results of the study suggest that PRP is a powerful tool for intensive and rapid apexogenesis since it offers clear and comprehensive results (mostly in the first three months which are early radiologically visible without any failure in the proposed requests.

21 CFR 315.6 - Evaluation of safety.

Science.gov (United States)

2010-04-01

... 21 Food and Drugs 5 2010-04-01 2010-04-01 false Evaluation of safety. 315.6 Section 315.6 Food and... USE DIAGNOSTIC RADIOPHARMACEUTICALS § 315.6 Evaluation of safety. (a) Factors considered in the safety...)(1) To establish the safety of a diagnostic radiopharmaceutical, FDA may require, among other...

RADRELAY RADIOLOGICAL DATA LINK DEVICE

International Nuclear Information System (INIS)

Harpring, L.; Frank Heckendorn, F.

2007-01-01

The RadRelay effort developed small, field appropriate, portable prototype devices that allow radiological spectra to be downloaded from field radiological detectors, like the identiFINDER-U, and transmitted to land based experts. This communications capability was designed for the U. S. Coast Guard (USCG) but is also applicable to the Customs and Border Protection (CBP) personnel working in remote locations. USCG Level II personnel currently use the identiFINDER-U Hand-Held Radioisotope ID Devices (HHRIID) to detect radiological materials during specific boarding operations. These devices will detect not only radiological emissions but will also evaluate those emissions against a table of known radiological spectra. The RadRelay has been developed to significantly improve the functionality of HHRIID, by providing the capability to download radiological spectra and then transmit them using satellite or cell phone technology. This remote wireless data transfer reduces the current lengthy delay often encountered between the shipboard detection of unknown radiological material and the evaluation of that data by technical and command personnel. That delay is reduced from hours to minutes and allows the field located personnel to remain on station during the inspection and evaluation process

BNL ALARA center's development of a computerized Radiological Assessment and Design System (RADS)

International Nuclear Information System (INIS)

Dionne, B.J.; Connelly, J.M.

1993-01-01

The US Department of Energy's (DOE) Office of Health Physics and Industrial Hygiene sponsored a study of Radiological Engineering Programs at selected DOE contractor facilities. This study was conducted to review, evaluate, and summarize techniques and practices that should be considered in the design phase that reduce dose and the spread of radioactive materials during subsequent construction and operation at DOE radiological facilities. As in a previous study on operational ALARA programs, a variety of open-quotes good-practice documentsclose quotes will be generated. It is envisioned that these documents will serve as a resource to assist radiological engineers in the process of designing radiological facilities, and in performing radiological safety/ALARA design reviews. This paper presents the features for three good-practice documents and related software applications that are being developed based on the findings of this study. The proposed software called open-quotes Radiological Assessment and Design Systemclose quotes (RADS) will be a menu-driven database and spreadsheet program. It will be designed to provide easy, consistent, and effective implementation of the methodologies described in the three good-practice documents. These documents and the associated RADS software will provide the user with the following three functions: (1) enter dose assessment information and data into computer worksheets and provide printed tables of the results which can then be inserted into safety analysis reports or cost-benefit analysis, (2) perform a wide variety of sorts of radiological design criteria from DOE Orders and produce a checklist of the desired design criteria, and (3) enter cost/benefit data and qualitative ratings of attributes for various design alternatives which reduce dose into computer worksheets and provide printed reports of cost-effectiveness results

Current state of the auto-evaluation process of the behaviour code in the safety of research reactors in Mexico

International Nuclear Information System (INIS)

Mamani A, Y. R.; Salgado G, J. R.

2011-11-01

In Mexico, the regulator organism in nuclear matter is the National Commission of Nuclear Safety and Safeguards, and a nuclear research reactor exists, the TRIGA Mark III, operated by the National Institute of Nuclear Research. In this work the main aspects of the current state and the future challenges are presented with relationship to the installation of the auto-evaluation process of the behaviour code in the safety of research reactors for the TRIGA reactor case. Additionally, the legal mark of the licensing process for the nuclear activities in a research reactor is described in a brief way, and the main characteristics of the reactor, the uses for the isotopes production, the administration and the verification of the safety, the administration program of the radiological protection, the emergency plan and the operation personnel qualification are emphasized. (Author)

Radiological evaluation of tumor response in oncological studies (tumor response evaluation)

International Nuclear Information System (INIS)

Gebauer, B.; Riess, H.

2011-01-01

Purpose: Radiological-morphological response evaluation plays a major role in oncological therapy and studies for approval. Specific criteria have been developed for some tumor entities and chemotherapeutics. Application, limitations and definitions of the most frequently used criteria for tumor response evaluation will be presented. Materials and Methods: Review based on a selective literature research. Results: In clinical oncological therapy studies, WHO and RECIST are the most frequently used criteria to evaluate morphological therapy response. RECIST criteria have been modified recently, especially with respect to the evaluation of lymph nodes, and were published as RECIST 1.1 in 2009. All criteria were originally developed and defined to review clinical multicenter trials for approval. Using these criteria in a clinical situation, certain limitations have to be considered. To evaluate response, a baseline scan before therapy start is mandatory. Special tumor response criteria have been defined for some certain tumor entities. Oncologists and radiologists should define in advance which criteria are used before starting therapy. Conclusion: The use of defined criteria is very important in oncology response evaluation. In-depth knowledge of the criteria and their limits is required for correct usage. (orig.)

The radiological accident in Yanango

International Nuclear Information System (INIS)

2000-01-01

The use of nuclear technologies has fostered new, more effective and efficient medical procedures and has substantially improved diagnostic and therapeutic capabilities. However, in order that the benefits of the use of ionizing radiation outweigh the potential hazards posed by this medium, it is important that radiation protection and safety standards be established to govern every aspect of the application of ionizing radiation. Adherence to these standards needs to be maintained through effective regulatory control, safe operational procedures and a safety culture that is shared by all. Occasionally, established safety procedures are violated and serious radiological consequences ensue. The radiological accident described in this report, which took place in Lilo, Georgia, was a result of such an infraction. Sealed radiation sources had been abandoned by a previous owner at a site without following established regulatory safety procedures, for example by transferring the sources to the new owner or treating them as spent material and conditioning them as waste. As a consequence, 11 individuals at the site were exposed for a long period of time to high doses of radiation which resulted inter alia in severe radiation induced skin injuries. Although at the time of the accident Georgia was not an IAEA Member State and was not a signatory of the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency, the IAEA still provided assistance to the Government of Georgia in assessing the radiological situation, while the World Health Organization (WHO) assisted in alleviating the medical consequences of the accident. The two organizations co-operated closely from the beginning, following the request for assistance by the Georgian Government. The IAEA conducted the radiological assessment and was responsible for preparing the report. The WHO and its collaborating centres within the Radiation Emergency Medical Preparedness and Assistance Network

Diagnosis of radiological security of installations; Diagnostico de la seguridad radiologica de instalaciones

Energy Technology Data Exchange (ETDEWEB)

Herrera V, L [Laboratorio de Vigilancia Radiologica Ambiental, Gerencia de Seguridad del ININ (Mexico)

1991-07-01

The objective of this work is to discuss the diagnosis of the radiological safety of nuclear or radioactive facilities. It was concluded that the one diagnoses like discipline of the radiological safety is susceptible of being represented, taught and programmable in computer and useful systems as preventive tool and of inspection.

Radiological evaluation of long term complications of oral rehabilitations of thin ridges with titanium blade implants

Directory of Open Access Journals (Sweden)

P. Diotallevi

2014-03-01

Full Text Available Aim: The aim of this study was to assess the sensitivity of orthopantomography (OPT in the diagnosis of long term complications in oral rehabilitations with blade implants. Materials and methods A total of 235 blade implants in 189 patients, inserted between 1988 and 2003, were retrospectively analyzed. The records consisted of a first OPT taken between January and December 2010, and a second one 12 months after. The evaluation of implant health considered: integrity of the blade, normal radiological representation of the bone around the implant, dense and cortical appearance of bone around the implant collar. The evaluation of radiological complications considered: implant fracture, bone resorption around the implant, recession of the bone around the implant collar. Results The sensitivity of the panoramic evaluation was equal to 100%. The complications detected were 5 cases of periimplantitis, 9 cases of bone pericervical bone recession and 3 cases of fracture of the implant body. In cases of pericervical bone resorption the following radiological check up 12 months after the first one showed the progression of the disease in 6 out of 9 cases, with irreversible implant failure. In subjects with a radiological pattern of implant health there were no complications in the subsequent check up after 12 months. In the subjects with complications the specificity was equal to 100%. Conclusion The radiographic evaluation by the means of OPT has shown high sensitivity in the diagnosis of long term complications of oral rehabilitations with blade implants and allows prompt therapeutic interventions. Radiological complications appeared mostly in the long term check ups and mainly consisted in recession of the bone around the neck or around the entire implant. More rarely implant fractures occurred, which, in the case of blades, sometimes were not associated with any clinical symptoms: therefore, postsurgical evaluation should not be separated from

Evaluation of behaviour and Safety in a geologic deep repository

International Nuclear Information System (INIS)

1997-01-01

This report presents a comprehensive description of the post-closure radiological safety assessment of a repository for the spent fuel arisings resulting from the Spanish nuclear program. This Safety Assessment constitutes a first step within a systematical process that will permit, thorough successive approximations, to predict the performance of the different barriers of the disposal system, and its capability to comply with the assigned safety functions and with the established safety criteria. The primary bases for this Safety Assessment are the following: The disposal concept considers the storage of the fuel assemblies in carbon steel canisters of 10 cm of thickness, emplaced horizontally in galleries excavated in granite of 2,4 m of diameter and 500 m of length, using a bentonite thickness of 75 cm around canisters as buffer material. The repository is located in a granitic site defined with available data about surface characteristics of Spanish granites. The exercise uses a probabilistic approximation in order to cope with the uncertainties associated with the different imputs parameters. (Author)

Analysis of the Radiology Reports from Radiology Clinics

International Nuclear Information System (INIS)

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

2009-01-01

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

Evaluation of diagnostic radiology services in five Latin American countries: Results for mammography

International Nuclear Information System (INIS)

Brandan, M.E.; Caspani, C.E.M.; Mora, R. de la; Miranda, A.A.; Plazas, M.-C.; Borras, C.

2001-01-01

Under the auspices of PAHO/WHO, a multicentric investigation is carried out in five Latin American countries. Its aim is to correlate quality indicators of radiology services with the accuracy of the radiological interpretation as determined by a panel of experts. We present preliminary results from mammographic imaging facilities, which indicate that the failure to comply with the international standards of quality control produces images of unacceptable quality, as measured either by using a phantom or by an independent evaluation of the clinical images. (author)

Digital subtraction angiography in head and neck radiology

International Nuclear Information System (INIS)

Carmody, R.F.; Seeger, J.F.; Smith, R.L.; Horsley, W.W.; Miller, R.W.

1984-01-01

Intravenous digital subtraction angiography (IVDSA) was used to evaluate 44 patients with suspected otolaryngologic abnormalities. Sixteen had IVDSA for pulsatile tinnitus or suspected glomus tumor of the petrous bone. Nine patients were evaluated because of pulsatile neck masses, and 12 others had suspected tumors of the neck, face, and paranasal sinuses. Seven had IVDSA following head and neck trauma. The technique of examination is described. The current indications of IVDSA in head and neck radiology are discussed. It is concluded that IVDSA is a suitable substitute for conventional angiography for many otolaryngologic conditions and, because of its safety, can be used more liberally. (orig.)

International scaling of nuclear and radiological events

International Nuclear Information System (INIS)

Wang Yuhui; Wang Haidan

2014-01-01

Scales are inherent forms of measurement used in daily life, just like Celsius or Fahrenheit scales for temperature and Richter for scale for earthquakes. Jointly developed by the IAEA and OECD/NEA in 1990, the purpose of International Nuclear and Radiological Event Scale (INES) is to help nuclear and radiation safety authorities and the nuclear industry worldwide to rate nuclear and radiological events and to communicate their safety significance to the general public, the media and the technical community. INES was initially used to classify events at nuclear power plants only. It was subsequently extended to rate events associated with the transport, storage and use of radioactive material and radiation sources, from those occurring at nuclear facilities to those associated with industrial use. Since its inception, it has been adopted in 69 countries. Events are classified on the scale at seven levels: Levels 1-3 are called 'incidents' and Levels 4-7 'accidents'. The scale is designed so that the severity of an event is about ten times greater for each increase in level on the scale. Events without safety significance are called 'deviations' and are classified Below Scale/Level 0. INES classifies nuclear and radiological accidents and incidents by considering three areas of impact: People and the Environment; Radiological Barriers and Control; Defence-in-Depth. By now, two nuclear accidents were on the highest level of the scale: Chernobyl and Fukumashi. (authors)

Plant safety and performance indicators for regulatory use

International Nuclear Information System (INIS)

Ferjancic, M.; Nemec, T.; Cimesa, S.

2004-01-01

Slovenian Nuclear Safety Administration (SNSA) supervises nuclear and radiological safety of Krsko NPP. This SNSA supervision is performed through inspections, safety evaluations of plant modifications and event analyses as well as with the safety and performance indicators (SPI) which are a valuable data source for plant safety monitoring. In the past SNSA relied on the SPI provided by Krsko NPP and did not have a set of SPI which would be more appropriate for regulatory use. In 2003 SNSA started with preparation of a new set of SPI which would be more suitable for performing the regulatory oversight of the plant. New internal SNSA procedure which is under preparation will define use and evaluation of SPI and will include definitions for the proposed set of SPI. According to the evaluation of SPI values in comparison with the limiting values and/or trending, the procedure will define SNSA response and actions. (author)

Radiological safety aspects of industrial radiography

International Nuclear Information System (INIS)

Hanekom, A.P.

1983-01-01

Industrial radiography and especially gamma-radiography, has established itself as a very powerful tool in non-destructive testing. Unfortunately there is an amount of risk attached to the use of industrial radiography. The primary causes of radiography accidents include: working conditions, equipment failure and lack of supervisory control. To alleviate the radiological risks involved with gamma-radiography, the Atomic Energy Corporation (AEC) has imposed various conditions for the possession, use, and conveyance of radioactive material. This includes personnel training and equipment specifications

Radiation shielding and safety design

Energy Technology Data Exchange (ETDEWEB)

Lee, Yong Ouk; Gil, C. S.; Cho, Y. S.; Kim, D. H.; Kim, H. I.; Kim, J. W.; Lee, C. W.; Kim, K. Y.; Kim, B. H. [KAERI, Daejeon (Korea, Republic of)

2011-07-15

A benchmarking for the test facility, evaluations of the prompt radiation fields, evaluation of the induced activities in the facility, and estimation of the radiological impact on the environment were performed in this study. and the radiation safety analysis report for nuclear licensing was written based on this study. In the benchmark calculation, the neutron spectra was measured in the 20 Mev test facility and the measurements were compared with the computational results to verify the calculation system. In the evaluation of the prompt radiation fields, the shielding design for 100 MeV target rooms, evaluations of the leakage doses from the accidents and skyshine analysis were performed. The evaluation of the induced activities were performed for the coolant, inside air, structural materials, soil and ground-water. At last, the radiation safety analysis report was written based on results from these studies

Radiological Source Terms for Tank Farms Safety Analysis

Energy Technology Data Exchange (ETDEWEB)

COWLEY, W.L.

2000-06-27

This document provides Unit Liter Dose factors, atmospheric dispersion coefficients, breathing rates and instructions for using and customizing these factors for use in calculating radiological doses for accident analyses in the Hanford Tank Farms.

Radiological safety of decayed source removal facility (DSRF) - an overview

International Nuclear Information System (INIS)

Rajput, Raksha; George, Jain Reji; Pathak, B.K.

2018-01-01

Industrial radiography is one of the major applications of radioisotope in engineering industry for Non-Destructive Testing (NDT). The equipment used for this purpose is called Industrial Radiography Exposure Device (IGRED) or radiography (RG) camera. In India, more than 1800 IGREDs including imported cameras are being used in NDT industry. These cameras are of different types and have various capacities to house different radioisotopes. Generally, 192 Ir sources are being used for NDT work. The sources are being supplied by BRIT to the users. After the useful period of the utilization of gamma intensity, the decayed source is returned to BRIT in RG camera. The decayed source is removed from the camera in the Decayed Source Removal Facility (DSRF). This facility serves the purpose of a miniature hot-cell with the capability of storing the decayed sources which are removed from the cameras. The empty camera is inspected for its mechanical functions and sent to BRIT's hot-cell for loading the new source. DSRF is situated at BRIT Vashi Complex. This paper deals with the radiological safety in the operation of DSRF for removing decayed sources from industrial radiography cameras

The American Board of Radiology perspective on maintenance of certification: Part IV: Practice quality improvement in radiologic physics

International Nuclear Information System (INIS)

Frey, G. Donald; Ibbott, Geoffrey S.; Morin, Richard L.; Paliwal, Bhudatt R.; Thomas, Stephen R.; Bosma, Jennifer

2007-01-01

Recent initiatives of the American Board of Medical Specialties (ABMS) in the area of maintenance of certification (MOC) have been reflective of the response of the medical community to address public concerns regarding quality of care, medical error reduction, and patient safety. In March 2000, the 24 member boards of the ABMS representing all medical subspecialties in the USA agreed to initiate specialty-specific maintenance of certification (MOC) programs. The American Board of Radiology (ABR) MOC program for diagnostic radiology, radiation oncology, and radiologic physics has been developed, approved by the ABMS, and initiated with full implementation for all three disciplines beginning in 2007. The overriding objective of MOC is to improve the quality of health care through diplomate-initiated learning and quality improvement. The four component parts to the MOC process are: Part I: Professional standing, Part II: Evidence of life long learning and periodic self-assessment, Part III: Cognitive expertise, and Part IV: Evaluation of performance in practice (with the latter being the focus of this paper). The key components of Part IV require a physicist-based response to demonstrate commitment to practice quality improvement (PQI) and progress in continuing individual competence in practice. Diplomates of radiologic physics must select a project to be completed over the ten-year cycle that potentially can improve the quality of the diplomate's individual or systems practice and enhance the quality of care. Five categories have been created from which an individual radiologic physics diplomate can select one required PQI project: (1) Safety for patients, employees, and the public, (2) accuracy of analyses and calculations, (3) report turnaround time and communication issues, (4) practice guidelines and technical standards, and (5) surveys (including peer review of self-assessment reports). Each diplomate may select a project appropriate for an individual

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)

Radiological protection procedures for industrial applications of computed radiography; Procedimentos de protecao radiologica em aplicacoes industriais da radiografia computadorizada

Energy Technology Data Exchange (ETDEWEB)

Aquino, Josilto Oliveira de

2009-03-15

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)

Waste Encapsulation and Storage Facility interim operational safety requirements

CERN Document Server

Covey, L I

2000-01-01

The Interim Operational Safety Requirements (IOSRs) for the Waste Encapsulation and Storage Facility (WESF) define acceptable conditions, safe boundaries, bases thereof, and management or administrative controls required to ensure safe operation during receipt and inspection of cesium and strontium capsules from private irradiators; decontamination of the capsules and equipment; surveillance of the stored capsules; and maintenance activities. Controls required for public safety, significant defense-in-depth, significant worker safety, and for maintaining radiological consequences below risk evaluation guidelines (EGs) are included.

Oil wells and gas wells: aspects of radiological safety

International Nuclear Information System (INIS)

Soares, S.M.V.O.

1987-01-01

The objective of the present work is to present and analyse the main radiological protection problems associated with non destructive inspections of oil wells, with the view of minimizing the dose to members of the public living in nearby urban zones. Problems related to the surveillance of such activities and the need for well formulated procedures are also discussed based on specific Brasilian regulations. Finally, some examples of radiological accidents that have occured in urban zones are described including the methodology employed for the rescue of Iridium-192 sources and for the estimate of radiation doses for workers and general public. (author) [pt

Evaluation of the contribution of radiological imaging to the final diagnosis in medical case reports

International Nuclear Information System (INIS)

Wiesinger, Isabel; Scharf, Gregor; Platz, Natascha; Dendl, Lena M.; Stroszczynski, Christian; Schreyer, Andreas G.; Pawlik, Michael T.

2015-01-01

To evaluate the clinical value and impact of radiological imaging in published medial case reports. We analysed 671 consecutively published case reports of a peer-reviewed medical journal for case reports. The general use of radiological imaging as well as the specific imaging modality used in each case (ultrasound, x-ray, fluoroscopy, CT, MRI) was documented, and most importantly the 'final problem solver', i.e. the diagnostic modality giving the final clue to the patient's diagnosis, was identified. In 511 of 671 (76.1 %) analysed case reports at least one radiological modality was used in the diagnostic cascade. In 28.6 % of all cases the final diagnosis was achieved by radiological imaging. All other cases were solved by the patient's history and physical examination (15.2 %), histology (12.4 %), and blood analysis (9.6 %). When radiology was the 'final problem solver', it was mainly CT (51.6 %) and MRI (30.6 %). In 52.2 % of the case reports the radiological image was included in the article. In case reports published in a prominent general medical journal radiological imaging is an important key player in the diagnostic process. In many cases, it is also the diagnostic tool which ultimately leads to determining the final diagnosis. (orig.)

Evaluation of the contribution of radiological imaging to the final diagnosis in medical case reports

Energy Technology Data Exchange (ETDEWEB)

Wiesinger, Isabel; Scharf, Gregor; Platz, Natascha; Dendl, Lena M.; Stroszczynski, Christian; Schreyer, Andreas G. [University Hospital Regensburg, Institute of Radiology, Regensburg (Germany); Pawlik, Michael T. [Intensive Care and Emergency Medicine, Institute of Anaesthesiology, Regensburg (Germany)

2015-05-01

To evaluate the clinical value and impact of radiological imaging in published medial case reports. We analysed 671 consecutively published case reports of a peer-reviewed medical journal for case reports. The general use of radiological imaging as well as the specific imaging modality used in each case (ultrasound, x-ray, fluoroscopy, CT, MRI) was documented, and most importantly the 'final problem solver', i.e. the diagnostic modality giving the final clue to the patient's diagnosis, was identified. In 511 of 671 (76.1 %) analysed case reports at least one radiological modality was used in the diagnostic cascade. In 28.6 % of all cases the final diagnosis was achieved by radiological imaging. All other cases were solved by the patient's history and physical examination (15.2 %), histology (12.4 %), and blood analysis (9.6 %). When radiology was the 'final problem solver', it was mainly CT (51.6 %) and MRI (30.6 %). In 52.2 % of the case reports the radiological image was included in the article. In case reports published in a prominent general medical journal radiological imaging is an important key player in the diagnostic process. In many cases, it is also the diagnostic tool which ultimately leads to determining the final diagnosis. (orig.)

Contribution to the study of the new international philosophy of the radiological safety in the natural uranium chemical treatment

International Nuclear Information System (INIS)

Moraes da Silva, T. de

1990-01-01

The objective of this work is to adapt the Radiological Safety System in the facilities concerned to the chemical treatment of the uranium concentrated (yellow-cake) until conversion in uranium hexafluoride in the pilot plant of IPEN-CNEN/SP, to the new international philosophy adopted by ICRP and IAEA. The new philosophy changes fully the Radiological Protection concepts of preceding philosophy, changes, also, the concept of the workplace and individual monitoring as well as the classification of the working areas. In this paper we show the monitoring program, in each phase of the natural uranium treatment chemical process in conversion facility for external irradiation, surface contamination and air contamination. The results were analysed according with the new philosophy and used to reclassify the workplace. It was introduced the condition work concept taking account the time spent by the worker in that workplace. (author)

Competency-Based Teaching in Radiology - Implementation and Evaluation of Interactive Workstation-Based Learning to Apply NKLM-Based Content.

Science.gov (United States)

Koestner, Wolfgang; Otten, Wiebke; Kaireit, Till; Wacker, Frank K; Dettmer, Sabine

2017-11-01

Purpose  New teaching formats are required to implement competency-based teaching in radiology teaching. Therefore, we have established and evaluated two practical competency-based radiological courses. Materials and Methods  The courses were held in a multimedia room with 25 computers and a professional DICOM viewer. Students were taught basic image analysis and presented clinical cases with a DICOM viewer under supervision of an instructor using desktop monitoring software. Two courses (elective course and obligatory course) were evaluated by the students (n = 160 and n = 100) and instructors (n = 9) using an anonymized online survey. Results  Courses were evaluated positively by the students and instructors. From the perspective of the students, the courses increased understanding of cross-sectional anatomy (elective/obligatory course: 97 %/95 %) and radiologic findings (97 %/99 %). Furthermore, the course increased the students' interest in radiology (61 %/65 %). The students considered this way of teaching to be relevant to their future occupation (92 % of students in the obligatory course). The higher incidence of teacher-student interaction and the possibility of independent image analysis were rated positively. The majority of instructors did not observe increased distractibility due to the computers (67 %) or notice worse preparation for MC tests (56 %). However, 56 % of instructors reported greater preparation effort. Conclusion  Practical competency-based radiological teaching using a DICOM viewer is a feasible innovative approach with high acceptance among students and instructors. It fosters competency-based learning as proposed by the model curriculum of the German Radiological Society (DRG) and the National Competency-based Catalogue of Learning Objectives for Undergraduate Medical Education (NKLM). Key Points   · Practical competency-based radiological teaching is highly accepted by students and instructors

Radiological evaluation of familial osteopetrosis

International Nuclear Information System (INIS)

Moon, Moo Chang; Kang, Shin Wha; Won, Jong Jin; Rhee, Song Joo; Choi, Ki Chul

1980-01-01

Authors found 16 patients with benign osteopetrosis out of 62 members of 4 families and analysed these patients clinically, radiologically, hematologically and biochemically at the Department of Radiology, Jeonbug National University Hospital from October 1977 to June 1980. The results are as follows; 1. We obtained that there is evidence of familial tendency in developing osteopetrosis because of the fact that 15 patients (94%) developed in 3 families and more than 2 patients in each family. In genetical point of view we suspected dominant trait of inheritance and could rule out recessive trait because patients were found in successive generations except for one family. There were no consangulneous marriages among the parents of these patients. 2. The majority of patients were adolescent or adult above 10 years of age when the disease was diagnosed. The incidence was identical in both sex. 3. No clinical symptoms and historical abnormalities were found in 11 patients (69%) and 5 patients (31%) showed only mild symptoms. Among 5 patients with clinical symptoms 3 patients showed pathologic fractures. In all 3 patients, fractures occurred only by mild trauma and affected sites were tubular bones and they were transverse type. 4. There were no specific relationship between ABO types and Rh reactions in developing osteopetrosis and no specific findings in hematological, biochemical and routine urinalysis. 5. The only diagnostic finding in most patients were the typical and specific radiological findings

Criticality safety evaluation in Tokai Reprocessing Plant

International Nuclear Information System (INIS)

Shirai, Nobutoshi; Nakajima, Masayoshi; Takaya, Akikazu; Ohnuma, Hideyuki; Shirouzu, Hidetomo; Hayashi, Shinichiro; Yoshikawa, Koji; Suto, Toshiyuki

2000-04-01

Criticality limits for equipments in Tokai Reprocessing Plant which handle fissile material solution and are under shape and dimension control were reevaluated based on the guideline No.10 'Criticality safety of single unit' in the regulatory guide for reprocessing plant safety. This report presents criticality safety evaluation of each equipment as single unit. Criticality safety of multiple units in a cell or a room was also evaluated. The evaluated equipments were ones in dissolution, separation, purification, denitration, Pu product storage, and Pu conversion processes. As a result, it was reconfirmed that the equipments were safe enough from a view point of criticality safety of single unit and multiple units. (author)

French days of radiology (J.F.R.) 2005

International Nuclear Information System (INIS)

2005-01-01

Five parts are presented, the nuclear safety authority informs the radiologists on the evolution of the regulation in radiation protection and its practical application; statements of medical and dental radiodiagnosis equipments; licensing for use of radiodiagnosis installation; to use the diagnosis reference levels in radiology to optimize the practices; radiation protection in interventional radiology. (N.C.)

Site evaluation for nuclear installations. Safety requirements

International Nuclear Information System (INIS)

2003-01-01

This Safety Requirements publication supersedes the Code on the Safety of Nuclear Power Plants: Siting, which was issued in 1988 as Safety Series No. 50-C-S (Rev. 1). It takes account of developments relating to site evaluations for nuclear installations since the Code on Siting was last revised. These developments include the issuing of the Safety Fundamentals publication on The Safety of Nuclear Installations, and the revision of various safety standards and other publications relating to safety. Requirements for site evaluation are intended to ensure adequate protection of site personnel, the public and the environment from the effects of ionizing radiation arising from nuclear installations. It is recognized that there are steady advances in technology and scientific knowledge, in nuclear safety and in what is considered adequate protection. Safety requirements change with these advances and this publication reflects the present consensus among States. This Safety Requirements publication was prepared under the IAEA programme on safety standards for nuclear installations. It establishes requirements and provides criteria for ensuring safety in site evaluation for nuclear installations. The Safety Guides on site evaluation listed in the references provide recommendations on how to meet the requirements established in this Safety Requirements publication. The objective of this publication is to establish the requirements for the elements of a site evaluation for a nuclear installation so as to characterize fully the site specific conditions pertinent to the safety of a nuclear installation. The purpose is to establish requirements for criteria, to be applied as appropriate to site and site-installation interaction in operational states and accident conditions, including those that could lead to emergency measures for: (a) Defining the extent of information on a proposed site to be presented by the applicant; (b) Evaluating a proposed site to ensure that the site

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

Science.gov (United States)

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

2017-10-01

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

Guide for understanding and evaluation of safety culture

International Nuclear Information System (INIS)

2008-01-01

This report was the guide of understanding and evaluation of safety culture. Operator's activities for enhancement of safety culture in nuclear installations became an object of safety regulation in the management system. Evaluation of operator's activities (including top management's involvement) to prevent degradation of safety culture and organization climate in daily works needed understanding of safety culture and diversity of operator's activities. This guide was prepared to check indications of degradation of safety culture and organization climate in operator's activities in daily works and encourage operator's activities to enhance safety culture improvement and good practice. Comprehensive evaluation of operator's activities to prevent degradation of safety culture and organization climate would be performed from the standpoints of 14 safety culture elements such as top management commitment, clear plan and implementation of upper manager, measures to avoid wrong decision making, questioning attitude, reporting culture, good communications, accountability and openness, compliance, learning system, activities to prevent accidents or incidents beforehand, self-assessment or third party evaluation, work management, change management and attitudes/motivation. Element-wise examples and targets for evaluation were attached with evaluation check tables. (T. Tanaka)

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

International Nuclear Information System (INIS)

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

2017-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2017-10-15

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