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Sample records for radiological safety evaluation

  1. Radiological safety evaluation report for NUWAX-79 exercise

    International Nuclear Information System (INIS)

    King, W.C.

    1979-03-01

    An analysis of the radiological safety of the NUWAX-79 exercise to be conducted on the Nevada Test Site in April 1979 is given. An evaluation of the radiological safety to the participants is made using depleted uranium (D-38) in mock weapons parts, and 223 Ra and its daughters as a radioactive contaminant of equipment and terrain. The radiological impact to offsite persons is also discussed, particularly for people living at Lathrop Wells, Nevada, which is located 7 miles south of the site proposed for the exercise. It is the conclusion of this evaluation that the potential radiological risk of this exercise is very low, and that no individual should receive exposure to radioactivity greater than one-tenth of the level permitted under current federal radiation exposure guidelines

  2. Safety aspects in radiology

    International Nuclear Information System (INIS)

    Silva, D.C. da.

    1991-05-01

    The development of a program for the evaluation of the physical installations and operational procedures in diagnostic radiology with respect to radiation-safety is described. In addition, a proposal for the quality analysis of X-ray equipment and film-processing is presented. The purpose is both to ensure quality and safety of the radiology service, as well as to aid in the initial and in-service training of the staff. Interviews with patients, staff practicing radiology at a wide range of levels and the controlling authorities were carried out in the State of Rio de Janeiro in order to investigate the existence and the effective use of personal radioprotection equipment as well as user's and staff's concern for radiation safety. Additionally physical measurements were carried out in University Hospitals in Rio de Janeiro to assess the quality of equipment in day-to-day use. It was found that in the locations which did not have routine maintenance the equipment was generally in a poor state which lead to a high incidence of repetition of examinations and the consequent financial loss. (author)

  3. Multi-criteria analysis for evaluating the radiological and ecological safety measures in radioactive waste management

    International Nuclear Information System (INIS)

    Sazykina, T.G.; Kryshev, I.I.

    2006-01-01

    A methodological approach is presented for multicriterial evaluating the effectiveness of radiation ecological safety measures during radioactive waste management. The approach is based on multicriterial analysis with consideration of radiological, ecological, social, economical consequences of various safety measures. The application of the multicriterial approach is demonstrated taking as an example of decision-making on the most effective actions for rehabilitation of a water subject, contaminated with radionuclides [ru

  4. 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)

  5. Evaluation of the Radiological Safety of 192 Ir Apparatus for Industrial Gamma Radiography

    International Nuclear Information System (INIS)

    Aquino, J. O.; Silva, F. C. A. da; Ramalho, A. T.; Godoy, J. M. O.

    2004-01-01

    The majority of the 192Ir apparatus for industrial gamma radiography have been in usage in Brazil for more than 20 years. They are portable, and almost all operate according to category II. The main objective of this work was to assess the radiological safety of the 11 models of 192Ir apparatus most used in Brazil. The 11 models of 192Ir apparatus were studied with respect to compliance with the main safety requirements of three editions of international Standards ISO 3999. Six models were already manufactured incorporating the safety devices specified in the first edition of ISO 3999, issued in 1977. However, five models were not. The validity of their type B certificates for transport packages was also evaluated. (Author) 8 refs

  6. 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

  7. 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.

  8. Radiological safety evaluation for a Waste Transfer Facility at Savannah River Site

    International Nuclear Information System (INIS)

    Ades, M.J.

    1993-01-01

    This paper provides a review of the radiological safety evaluation performed for a Waste Transfer Facility (WTF) located at the Savannah River Site (SRS). This facility transfers liquid radioactive waste between various waste processing facilities and waste storage facilities. The WTF includes functional components such as the diversion box and the pump pits, waste transfer lines, and the outside yard service piping and electrical services. The WSRC methodology is used to evaluate the consequences of postulated accidents that result in the release of radioactive material. Such accidents include transfer line breaks, underground liquid pathway release, fire in pump tank cells and HEPA filters, accidents due to natural phenomena, and externally induced events. Chemical hazards accidents are not considered. The analysis results indicate that the calculated mean onsite and offsite radiological consequences are bounded by the corresponding WSRC dose limits for each accident considered. Moreover, the results show that the maximum onsite and offsite doses calculated for the WTF are lower than the maximum doses determined for the whole radioactive waste facility where the WTF is located

  9. 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

  10. 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

  11. 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.

  12. 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

  13. 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)

  14. 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)

  15. 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

  16. 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)

  17. Implementation of a Radiological Safety Coach program

    Energy Technology Data Exchange (ETDEWEB)

    Konzen, K.K. [Safe Sites of Colorado, Golden, CO (United States). Rocky Flats Environmental Technology Site; Langsted, J.M. [M.H. Chew and Associates, Golden, CO (United States)

    1998-02-01

    The Safe Sites of Colorado Radiological Safety program has implemented a Safety Coach position, responsible for mentoring workers and line management by providing effective on-the-job radiological skills training and explanation of the rational for radiological safety requirements. This position is significantly different from a traditional classroom instructor or a facility health physicist, and provides workers with a level of radiological safety guidance not routinely provided by typical training programs. Implementation of this position presents a challenge in providing effective instruction, requiring rapport with the radiological worker not typically developed in the routine radiological training environment. The value of this unique training is discussed in perspective with cost-savings through better radiological control. Measures of success were developed to quantify program performance and providing a realistic picture of the benefits of providing one-on-one or small group training. This paper provides a description of the unique features of the program, measures of success for the program, a formula for implementing this program at other facilities, and a strong argument for the success (or failure) of the program in a time of increased radiological safety emphasis and reduced radiological safety budgets.

  18. Implementation of a Radiological Safety Coach program

    International Nuclear Information System (INIS)

    Konzen, K.K.

    1998-01-01

    The Safe Sites of Colorado Radiological Safety program has implemented a Safety Coach position, responsible for mentoring workers and line management by providing effective on-the-job radiological skills training and explanation of the rational for radiological safety requirements. This position is significantly different from a traditional classroom instructor or a facility health physicist, and provides workers with a level of radiological safety guidance not routinely provided by typical training programs. Implementation of this position presents a challenge in providing effective instruction, requiring rapport with the radiological worker not typically developed in the routine radiological training environment. The value of this unique training is discussed in perspective with cost-savings through better radiological control. Measures of success were developed to quantify program performance and providing a realistic picture of the benefits of providing one-on-one or small group training. This paper provides a description of the unique features of the program, measures of success for the program, a formula for implementing this program at other facilities, and a strong argument for the success (or failure) of the program in a time of increased radiological safety emphasis and reduced radiological safety budgets

  19. 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

  20. A Checklist to Improve Patient Safety in Interventional Radiology

    International Nuclear Information System (INIS)

    Koetser, Inge C. J.; Vries, Eefje N. de; Delden, Otto M. van; Smorenburg, Susanne M.; Boermeester, Marja A.; Lienden, Krijn P. van

    2013-01-01

    To develop a specific RADiological Patient Safety System (RADPASS) checklist for interventional radiology and to assess the effect of this checklist on health care processes of radiological interventions. On the basis of available literature and expert opinion, a prototype checklist was developed. The checklist was adapted on the basis of observation of daily practice in a tertiary referral centre and evaluation by users. To assess the effect of RADPASS, in a series of radiological interventions, all deviations from optimal care were registered before and after implementation of the checklist. In addition, the checklist and its use were evaluated by interviewing all users. The RADPASS checklist has two parts: A (Planning and Preparation) and B (Procedure). The latter part comprises checks just before starting a procedure (B1) and checks concerning the postprocedural care immediately after completion of the procedure (B2). Two cohorts of, respectively, 94 and 101 radiological interventions were observed; the mean percentage of deviations of the optimal process per intervention decreased from 24 % before implementation to 5 % after implementation (p < 0.001). Postponements and cancellations of interventions decreased from 10 % before implementation to 0 % after implementation. Most users agreed that the checklist was user-friendly and increased patient safety awareness and efficiency. The first validated patient safety checklist for interventional radiology was developed. The use of the RADPASS checklist reduced deviations from the optimal process by three quarters and was associated with less procedure postponements.

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

    OpenAIRE

    A َKalantari; SAM Khosravani

    2014-01-01

    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 descri...

  2. 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

  3. Radiological evaluation of chondroblastoma

    Energy Technology Data Exchange (ETDEWEB)

    Hudson, T.M.; Hawkins, I.F. Jr.

    1981-04-01

    Eleven new and six recurrent chondroblastomas were studied with multiple radiological imaging methods (plain radiography, conventional tomography, computed tomography, radionuclide bone scanning, and angiography). When the plain radiographic appearance was typical, conventional tomography or computed tomography (CT) was helpful, but other studies were not. Periosteal reaction and angiographic hypervascularity were common and did not indicate cortical breakthrough. For large, aggressive, or atypical lesions, conventional tomography and CT were helpful in delineating anatomic extent, and angiography was of value in demonstrating major vessel displacement. Radionuclide bone scanning was not useful.

  4. 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

  5. Review and evaluation of the Millstone Unit 3 probabilistic safety study. Containment failure modes, radiological source - terms and offsite consequences

    International Nuclear Information System (INIS)

    Khatib-Rahbar, M.; Pratt, W.; Ludewig, H.

    1985-09-01

    A technical review and evaluation of the Millstone Unit 3 probabilistic safety study has been performed. It was determined that; (1) long-term damage indices (latent fatalities, person-rem, etc.) are dominated by late failure of the containment, (2) short-term damage indices (early fatalities, etc.) are dominated by bypass sequences for internally initiated events, while severe seismic sequences can also contribute significantly to early damage indices. These overall estimates of severe accident risk are extremely low compared with other societal sources of risk. Furthermore, the risks for Millstone-3 are comparable to risks from other nuclear plants at high population sites. Seismically induced accidents dominate the severe accident risks at Millstone-3. Potential mitigative features were shown not to be cost-effective for internal events. Value-impact analysis for seismic events showed that a manually actuated containment spray system might be cost-effective

  6. 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

  7. Human-centred radiological software techniques supporting improved nuclear safety

    International Nuclear Information System (INIS)

    Szoeke, Istvan; Johnsen, Terje

    2013-01-01

    The Institute for Energy Technology (IFE) is an international research foundation for energy and nuclear technology. IFE is also the host for the international OECD Halden Reactor Project. The Software Engineering Department in the Man Technology Organisation at IFE is a leading international centre of competence for the development and evaluation of human-centred technologies, process visualisation, and the lifecycle of high integrity software important to safety. This paper is an attempt to give a general overview of the current, and some of the foreseen, research and development of human-centred radiological software technologies at the Software Engineering department to meet with the need of improved radiological safety for not only nuclear industry but also other industries around the world. (author)

  8. 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.

  9. Design aspects of radiological safety in nuclear facilities

    International Nuclear Information System (INIS)

    Patkulkar, D.S.; Purohit, R.G.; Tripathi, R.M.

    2014-01-01

    In order to keep operational performance of a nuclear facility high and to keep occupational and public exposure ALARA, radiological safety provisions must be reviewed at the time of facility design. Deficiency in design culminates in deteriorated system performance and non adherence to safety standards and could sometimes result in radiological incident. Important radiological aspects relevant to safety were compiled based on operating experiences, design deficiencies brought out from past nuclear incidents, experience gained during maintenance, participation in design review of upcoming nuclear facilities and radiological emergency preparedness

  10. 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.

  11. 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

  12. 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%)

  13. 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.

  14. 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

  15. Improving patient safety in radiology: a work in progress

    International Nuclear Information System (INIS)

    Sze, Raymond W.

    2008-01-01

    The purpose of this paper is to share the experiences, including successes and failures, as well as the ongoing process of developing and implementing a safety program in a large pediatric radiology department. Building a multidisciplinary pediatric radiology safety team requires successful recruitment of team members, selection of a team leader, and proper and ongoing training and tools, and protected time. Challenges, including thorough examples, are presented on improving pediatric radiology safety intradepartmentally, interdepartmentally, and institutionally. Finally, some major challenges to improving safety in pediatric radiology, and healthcare in general, are presented along with strategies to overcome these challenges. Our safety program is a work in progress; this article is a personal account and the reader is asked for tolerance of its occasional subjective tone and contents. (orig.)

  16. 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)

  17. 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)

  18. 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

  19. 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

  20. 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.

  1. 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.

  2. 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

  3. 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

  4. 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

  5. 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 .

  6. 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

  7. Evaluation of radiological safety assessment of a repository in a clay rock formation. Evaluacion del comportamiento y de la seguridad de un almacenamiento profundo en arcilla

    Energy Technology Data Exchange (ETDEWEB)

    1999-12-15

    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)

  8. Urogenital system diseases's radiological evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Bianchi, S; Mecozzi, B

    1985-01-01

    Radiological urogenital radiography reliability, can be compromised because of absence of a correct urodynamic diagnosis. It is then required that specialist radiologists know the problems concerning the urogenital system radiographies cannot be made in many cases, because of the scarcity in hospitals of idoneous urodynamic services.

  9. 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

  10. Indicators of the management for the continuous improvement of the radiological safety in a radioactive facility

    International Nuclear Information System (INIS)

    Amador B, Z. H.

    2006-01-01

    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)

  11. 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

  12. 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)

  13. Decision Strategy: Radiological Evaluations: Air

    Energy Technology Data Exchange (ETDEWEB)

    Sohier, A

    2000-07-01

    The objectives of SCK-CEN's R and D programme on off-site emergency management are (1) to improve methods to assess in real time the radiological impact to the population and the environment during a nuclear emergency; (2) to support and advise the Belgian authorities on specific problems concerning existing and potential hazards from exposure to ionising radiation in normal and accidental conditions; (3) to organise training courses on off-site emergency response to nuclear accidents. Main achievements in 1999 are reported on.

  14. Decision Strategy: Radiological Evaluations: Air

    International Nuclear Information System (INIS)

    Sohier, A.

    2000-01-01

    The objectives of SCK-CEN's R and D programme on off-site emergency management are (1) to improve methods to assess in real time the radiological impact to the population and the environment during a nuclear emergency; (2) to support and advise the Belgian authorities on specific problems concerning existing and potential hazards from exposure to ionising radiation in normal and accidental conditions; (3) to organise training courses on off-site emergency response to nuclear accidents. Main achievements in 1999 are reported on

  15. Radiological evaluation of spontaneous pneumoperitoneum

    International Nuclear Information System (INIS)

    Kim, H. S.; Kim, J. D.; Rhee, H. S.

    1982-01-01

    112 cases of spontaneous penumoperitoneum, the causes of which were confirmed by clinical and surgical procedure at Presbyterian Medical Center from January, 1977 to July, 1981 were reviewed radiologically. The results were as follows: 1. Perforation of duodenal ulcer (46/112: 41.1%), stomach ulcer (22/112: 19.6%), and stomach cancer (11/112: 9.8%) were the three most common causes of spontaneous penumoperitoneum. These were 70.5% of all causes. 2. The most common site of free gas was both subdiaphragmatic areas (46: 41.1%). Others were Rt. subdiaphragmatic only (31: 27.7%), both subdiaphragmatic with subhepatic (16: 14.3%), Rt. subdiaphragmatic with subhepatic (7: 6.2%), Rt. subdiaphragmatic only (5: 4.4%), diffuse in abdomen (4: 3.6%), and subhepatic only (3: 2.7%). So 92.0% (103/112) were located in RUQ. 3. The radiological shape of free gas was classified: crescent (52: 46.4%) of small amount; half-moon (21: 18.8%) of moderate amount; large or diffuse (39: 34.8%) of large amount.4. The age between 31 and 60 occupied 69.1% (77/112), and male was predominant (5.2 times). 5. The patient's position showing free air most frequently was erect

  16. Radiological protection and safety in medicine

    International Nuclear Information System (INIS)

    Anon.

    1998-01-01

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

  17. 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

  18. Radiation safety concerns during interventional radiology

    International Nuclear Information System (INIS)

    Victor Raj, D.; Livingstone, Roshan Samuel

    2001-01-01

    Interventional radiological procedures are on the increase by virtue of the fact that these procedures replace highly invasive surgical and other procedures. Radiation dose to patients and hospital workers are of significance since these procedures tend to impart large dose to them. Moreover, long term risk from radiation absorbed by patients is of concern since the life expectancy of major fraction of patients is long after undergoing the procedure. This study intends to measure radiation dose imparted to patients as well as personnel- radiologists, technologists, nurses, etc. and estimate the risk factor involved

  19. 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

  20. Nuclear and radiological safety, 1980-1993

    International Nuclear Information System (INIS)

    1994-06-01

    This document lists all sales publications of the International Atomic Energy Agency dealing with Nuclear Safety, issued during the period 1980-1993. It gives an abstract of these publications along with contents and prices in Austrian Schillings

  1. Radiologic evaluation of chondromalacia patellae

    International Nuclear Information System (INIS)

    Lund, F.; Nilsson, B.E

    1980-01-01

    In a series of patients in whom the patello-femoral joint has been examined by arthroscopy, in conjunction with arthrotomy or both, previously obtained films were reviewed. A series of radiologic morphometric measurements with bearing on the shape of the patella and the patello-femoral joint was carried out and compared between patients who had normal patello-femoral joints, patients with chondromalacia grade II or III and patients with chondromalacia grade IV or arthrosis. No difference between the three groups in any of the variables was found. However, a shallow excavation in the subchondral bone was observed in the lateral view of the patella in most of those patients with proven chondromalacia patellae. (Auth.)

  2. 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)

  3. 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

  4. 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

  5. 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.

  6. Gastric Mucosal Erosions - Radiologic evaluation -

    International Nuclear Information System (INIS)

    Kim, Seung Hyup

    1985-01-01

    70 cases of gastric mucosal erosions were diagnosed by double contrast upper gastrointestinal examinations and endoscopic findings. Analyzing the radiologic findings of these 70 cases of gastric mucosal erosions, the following results were obtained. 1. Among the total 70 cases, 65 cases were typical varioliform erosions showing central depressions and surrounding mucosal elevations. Remaining 5 cases were erosions of acute phase having multiple irregular depressions without surrounding elevations. 2. The gastric antrum was involved alone or in part in all cases. Duodenal bulb was involved with gastric antrum in 4 cases. 3. The majority of the cases had multiple erosions. There were only 2 cases of single erosion. 4. In 65 cases of varioliform erosions; 1) The diameter of the surrounding elevations varied from 3 to 20 mm with the majority (47 cases) between 6 and 10 mm. 2) In general, the surrounding elevations with sharp margin on double contrast films were also clearly demonstrated on compression films but those with faint margin were not. 3) The size of the central barium collections varied from pinpoint to 10 mm with the majority under 5 mm. The shape of the central barium collections in majority of the cases were round with a few cases of linear, triangular or star-shape. 5. In 5 cases of acute phase erosions; 1) All the 5 cases were females. 2) On double contrast radiography, all the cases showed multiple irregular depressed lesions without surrounding elevations. 3) 1 case had the history of hematemesis. 4) In 1 case, there was marked radiological improvement on follow-up study of 2 months interval. 6. In 23 cases, there were coexistent diseases with gastric mucosal erosions. These were 13 cases of duodenal bulb ulcers,7 cases of benign gastric ulcers and 3 others

  7. 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

  8. 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

  9. 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

  10. 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

  11. Safety and regulatory aspects of radiological laboratories

    International Nuclear Information System (INIS)

    Kumar, N.; Saxena, M.K.; Kannan, S.; Pujari, P.K.; Tomar, B.S.

    2017-01-01

    The erstwhile Radiochemistry Division (RCD) at Radiological Laboratories (RLG) was mainly concerned with the basic research and development work related to actinide chemistry and studies involving nuclear fission. The various activities of the different divisions are development of Non Destructive Assay (NDA) methods for the determination of actinides, characterization of advanced Pu based fuels using latest spectroscopic methods, development of sol-gel route for fabrication of different type of fuels, studies on high temperature thermodynamics of actinide compounds, development of methods for recovery and recycling of fuel scrap, mass spectrometric analysis of nuclear fuels and structural characterization of various uranium and plutonium compounds using X-ray diffraction and fluorescence techniques, trace elements analysis, need-based developmental work, inventory information and control of nuclear materials

  12. Considerations about radiological safety in industrial gammagraphy

    International Nuclear Information System (INIS)

    Sajaroff, P.M.

    1988-01-01

    Gammagraphy is the most dangerous practice out of the commonly employed with radioactive materials or radiation sources in industry, medicine, research and training. The amount of accidents which took place in different countries and their radiological consequences oblige to take extreme precautions in order to reduce their happening to the maximum. The principal cause of the accidents is the human error, the most common of which are described. Safe operation depends on the quality of the equipment and the human factors, thus it is mandatory to accomplish a series of requirements, the most important of which are presented. The solution of the problem mainly requires the application of an adequate programme of quality warranty to the design, construction, testing and operation. Furthermore, the radiation sources must be identified by unnoticed persons. Finally a brief description of some accidents which took place in different countries are presented. (M.E.L.) [es

  13. Radiological Emergency Response Health and Safety Manual

    Energy Technology Data Exchange (ETDEWEB)

    D. R. Bowman

    2001-05-01

    This manual was created to provide health and safety (H&S) guidance for emergency response operations. The manual is organized in sections that define each aspect of H and S Management for emergency responses. The sections are as follows: Responsibilities; Health Physics; Industrial Hygiene; Safety; Environmental Compliance; Medical; and Record Maintenance. Each section gives guidance on the types of training expected for managers and responders, safety processes and procedures to be followed when performing work, and what is expected of managers and participants. Also included are generic forms that will be used to facilitate or document activities during an emergency response. These ensure consistency in creating useful real-time and archival records and help to prevent the loss or omission of information.

  14. Radiologic evaluation of malignant histiocytoma

    International Nuclear Information System (INIS)

    Park, Ki Soon; Lee, Sun Wha; Yoon, Yup; Sung, Dong Wook; Ahn, Chi Yul

    1987-01-01

    Malignant fibrous histiocytoma is a new malignant tumor entity of histiocytic origin which arises as a primary tumor of the bone as well as the soft tissue. Radiologic features of 12 cases of pathologically proven intra-and extraosseous malignant fibrous histiocytoma were analyzed. The results were as follows : 1. Seven cases were of soft tissue origin and 5 cases were of primary bone origin. 2. Seven were male and 5 were female: Eight cases were beyond 5th decades. 3. The clinical presentations of malignant fibrous histiocytoma of the soft tissue origin were a mass with rapid growth or high rate of local recurrence. The roentgen evidence of soft tissue density mass was demonstrated in 7 cases and scintigraphic evidence of cortical invasion was suggested in 2 cases. 4. Malignant fibrous histiocytoma arising from bones had ill defined moth-eaten osteolytic lesion with cortical destruction, periosteal reaction and soft tissue extension. 5. Among 12 cases, there were 2 cases of pulmonary metastases and 2 cases of osseous metastases. 6. In the presence of soft tissue mass with locally aggressive behavior and/or nonspecific roentgen features of malignant bone tumor, one should consider the possibility of malignant fibrous histiocytoma

  15. Radiologic evaluation of pancreatic pseudocyst

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, T. H.; Kim, Y. J.; Hong, I. S.; Kim, M. S.; Sung, K. J. [Yeonsei University Wonju College of Medicine, Wonju (Korea, Republic of)

    1986-12-15

    Pancreatic pseudocyst is a collection of necrotic tissue, old blood and secretions that escaped from the pancreas damaged by pancreatitis, trauma and chronic alcoholism. There is no epithelial cell lining the cystic wall. With the advent of ultrasound and CT more accurate diagnosis can be made. Our study was carried out to analyse the radiological and clinical findings of 32 cases of pancreatic pseudocysts confirmed at Wonju College of Medicine Yonsei University from Jan. 1979 to Aug. 1986. The results are as follows: 1. Male to female ratio was 4.3:1 Incidence was the most common in 4th decades. 2. The most frequent symptom was epigastric pain (100%). 3. In a total of 32 cases, 15 cases had a underlying cause of pancreatitis, 9 cases abdominal trauma. 4. In laboratory findings, serum amylase level was elevated in 23 cases, leucocytosis in 10 cases. 5. On chest films, the lungs were mostly normal. Soft tissue mass density in 12 cases was the most common finding on abdomen films. 6. UGI series were helpful in directing attention by pancreatic pseudocysts' location and size. 7. Ultrasonogram using primary procedure for the detection of pseudocyst (23 cases) disclosed anechoic lesion in 8 cases, mixed echo lesion in 15 cases. Mixed echo patterns, in terms of internal echo patters, were echogenic spots (8 cases), septation and echogenic spots (3 cases), fluid-fluid level (3 cases), etc. 8. CT scanning is the best imaging procedure, providing detailed morphologic information about the pancreatic pseudocyst and surrounding tissue.

  16. 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

  17. 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

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

    International Nuclear Information System (INIS)

    1996-08-01

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

  19. 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

  20. 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)

  1. 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.

  2. 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)

  3. Radiological evaluation of abdominal trauma

    International Nuclear Information System (INIS)

    Ahn, K. S.; Cho, Y. H.; Kim, O.

    1982-01-01

    Simple abdomen film has played an important role in decision of emergency operations in patients with the abdominal trauma. Nowadays, it still acts as a primary and inevitable processes in emergency condition. At the Department of Radiology, Hanil Hospital, 70 patients, who were laparotomied due to penetrating or nonpernetraing abdominal trauma, were observed and analyzed with simple abdomen film after comparison with the operative findings. The results are as follows: 1. Most frequent age distribution was 10 to 39 years and marked 70%. Male was in 90% incidence. 2. Penetrating injury largely involved the small bowel and abdominal wall. Non-penetrating injury usually involved the spleen, small bowel, liver, kidney, pancreas, duodenum. 3. Single organ injury occurred in higher incidence at the small bowel and abdominal wall. Multiple organ injury occurred in higher incidence at the spleen, liver, kidney and pancreas. 4. Organ distribution was 26% in spleen, 22% in small bowel, 14% in liver, 11% in abdominal wall. 7% in pancreas, 7% in kidney. 5% in duodenum, 4% in GB and CBD, 2% in diaphragm, 2% in colon, and 1% in stomach. 5. The specific roentgen findings and their frequency which useful in differential diagnosis at abdominal trauma, were as follows: a) flank fluid; Detectable possibility was 71% in liver laceration, 69% in spleen laceration and 57% in pancreas laceration. b) ipsilateral psoas shadow obliteration; Detectable possibility was 57% in liver laceration, 57% in kidney laceration and 46% in spleen laceration. c) free air; Detactable possibility was 60% in duodenal perforation, and 36% in peroration of upper part of small bowel. d) Reflex ileus; Detectable possibility was 64% in small bowel, 50% in liver laceration and 35% in spleen laceration. e) rib fracture; Detactable possibility was 36% in liver laceration and 23% in spleen laceration. f) pleural effusion; Detectable possibility was 29% in liver laceration and 27% in spleen laceration

  4. 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

  5. Radiological safety aspects of handling plutonium

    International Nuclear Information System (INIS)

    Sundararajan, A.R.

    2016-01-01

    Department of Atomic Energy in its scheme of harnessing the nuclear energy for electrical power generation and strategic applications has given a huge role to utilization of plutonium. In the power production programme, fast reactors with plutonium as fuel are expected to play a major role. This would require establishing fuel reprocessing plants to handle both thermal and fast reactor fuels. So in the nuclear fuel cycle facilities variety of chemical, metallurgical, mechanical operations have to be carried out involving significant inventories of "2"3"9 Pu and associated radionuclides. Plutonium is the most radiotoxic radionuclide and therefore any facility handling it has to be designed and operated with utmost care. Two problems of major concern in the protection of persons working in plutonium handling facilities are the internal exposure to the operating personnel from uptake of plutonium and transplutonic nuclides as they are highly radiotoxic and the radiation exposure of hands and eye lens during fuel fabrication operations especially while handling recycled high burn up plutonium. In view of the fact that annual limit for intake is very small for "2"3"9Pu and its radiation emission characteristics are such that it is a huge challenge for the health physicists to detect Pu in air and in workers. This paper discusses the principles and practices followed in providing radiological surveillance to workers in plutonium handling areas. The challenges in protecting the workers from receiving exposures to hands and eye lens in handling high burn up plutonium are also discussed. The sites having Pu fuel cycle facilities should have trained medical staff to handle cases involving excessive intake of plutonium. (author)

  6. Radiological evaluation of acoustic neurinoma

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jong Tae; Park, Chang Yun; Choi, Byung So [Yonsei University College of Medicine, Seoul (Korea, Republic of)

    1974-04-15

    All 25 patients surgically proven acoustic neurinoma was analysed clinically, radiographically at Severance Hospital of Yonsei Univ. The patients not proved surgically in spite of clinical diagnosis of acoustic neurinoma was excluded from this study. The results are summarized as follows; The clinical findings are; 1. The incidence of tumor in female was twice more frequent than in male and the range of age was 20-50 years peak of age at onset of symptom. 2. The clinical symptoms were variable from unilateral hearing impairment or less (100%), headache (84%) to tinnitus (60%) in order of frequency. 3. The tumor growth in the left cerebellopontine angle was twice more than in the right side with the radio of 16:8. However, in one case bilateral simultaneous growth of acoustic neurinoma was noted. The radiological findings are: The best radiographic method to study the shape and size of internal acoustic canal to demonstrate erosion or destruction of petrous pyramida was considered to be straight frontal view and tomography of the skull in our series. 1. The shape of internal acoustic canal in tumors were straight (in 2 cases), bulbous (in 12 cases), and flared (in 11 cases). Particularly there was erosion or destruction of petrous bone in all of the flared cases of canal. 2. The acoustic meatal erosion was mainly suprameatal in 14 cases of 17 which was noted definite erosion radiographically. 3. The difference of height (vertical diameter) of both side of acoustic canal were follows; 6 cases among 25 was in the range of 0-2 mm measurement, remainder was more than 2 mm. Hence the variation in greater than 1 mm in between both sides of canal in same patient should be regard as abnormal as of acoustic neurinoma. 4. The carotid angiogram shows hydrocephalic pattern in 12 cases among 17. 5. In the vertebral angiogram of 8 cases, anterolateral displacement of basilar artery (in 6 caes), the upward displacement of superior cerebellar artery (in 4 cases) was common findings

  7. Radiological evaluation of acoustic neurinoma

    International Nuclear Information System (INIS)

    Lee, Jong Tae; Park, Chang Yun; Choi, Byung So

    1974-01-01

    All 25 patients surgically proven acoustic neurinoma was analysed clinically, radiographically at Severance Hospital of Yonsei Univ. The patients not proved surgically in spite of clinical diagnosis of acoustic neurinoma was excluded from this study. The results are summarized as follows; The clinical findings are; 1. The incidence of tumor in female was twice more frequent than in male and the range of age was 20-50 years peak of age at onset of symptom. 2. The clinical symptoms were variable from unilateral hearing impairment or less (100%), headache (84%) to tinnitus (60%) in order of frequency. 3. The tumor growth in the left cerebellopontine angle was twice more than in the right side with the radio of 16:8. However, in one case bilateral simultaneous growth of acoustic neurinoma was noted. The radiological findings are: The best radiographic method to study the shape and size of internal acoustic canal to demonstrate erosion or destruction of petrous pyramida was considered to be straight frontal view and tomography of the skull in our series. 1. The shape of internal acoustic canal in tumors were straight (in 2 cases), bulbous (in 12 cases), and flared (in 11 cases). Particularly there was erosion or destruction of petrous bone in all of the flared cases of canal. 2. The acoustic meatal erosion was mainly suprameatal in 14 cases of 17 which was noted definite erosion radiographically. 3. The difference of height (vertical diameter) of both side of acoustic canal were follows; 6 cases among 25 was in the range of 0-2 mm measurement, remainder was more than 2 mm. Hence the variation in greater than 1 mm in between both sides of canal in same patient should be regard as abnormal as of acoustic neurinoma. 4. The carotid angiogram shows hydrocephalic pattern in 12 cases among 17. 5. In the vertebral angiogram of 8 cases, anterolateral displacement of basilar artery (in 6 caes), the upward displacement of superior cerebellar artery (in 4 cases) was common findings

  8. Probabilistic safety analysis and radiological protection

    International Nuclear Information System (INIS)

    Guimaraes, A.C.F.; Goes, A.G.A.

    1990-05-01

    The author presents a brief description of NUREG-1150 and NUREG-0956, both documents of great importance in the risk area. Based on document's recommendations and following NUREG-1150 similar methodology, a calculation model is proposed in this publication, with the purpose of analyzing the consequences of a severe accident in Angra-I Power Station. The suggested model can be divided in two stages: the first one called front-end considers the power station system safety during the accident, and the second called back-end cares for accident consequences. 9 refs. (B.C.A.)

  9. 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

  10. 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.

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

    International Nuclear Information System (INIS)

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

    2000-01-01

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

  12. 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.

  13. 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.

  14. 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

  15. 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.

  16. 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

  17. Diabetic muscle infarction: radiologic evaluation

    International Nuclear Information System (INIS)

    Chason, D.P.; Fleckenstein, J.L.; Burns, D.K.; Rojas, G.

    1996-01-01

    Four patients with severe diabetes mellitus presenting with acute thigh pain, tenderness, and swelling were evaluated by imaging techniques and biopsy. Edema in the affected muscles was seen in two patients with MRI studies. Femoral artery calcification and mild muscle swelling was present in one patient who underwent CT. Decreased echogenicity was seen in the involved muscle in a patient studied with ultrasound. Serum enzymes were normal or mildly elevated in three patients (not reported in one). Biopsy demonstrated necrosis and regenerative change in all cases. MRI, although nonspecific, is the best imaging technique to suggest the diagnosis of DMI in the appropriate clinical setting, thereby obviating biopsy. (orig./MG)

  18. Radiologic evaluation of wrist arthrography

    International Nuclear Information System (INIS)

    Park, Yang Hee; Seong, Hyeun Lim; Yang, Jae Beom; Park, Chan Sup; Lee, Sang Seun

    1991-01-01

    Wrist arthrography allows direct visualization of the cartilage and synovial structure not seen in plain film. Arthrography of the wrist is valuable in evaluating patients with persistent wrist pain and limitation of motion after trauma. Wrist arthrography was performed in the evaluation of 30 patients with rheumatoid arthritis (2 cases), ganglions (12 cases), and wrist trauma (16 cases), and contrast media was injected in radiocarpal joint. The arthrographic findings were analyzed, and the results were as follows: In 16 patients with wrist trauma, 12 cases (75%) of compartment communication was seen including communication with distal radioulnar joint (44%), midcarpal joint (69%), and common carpometacarpal joint (63%). Of the total 30 patients, the pisiform-triquetral joint communicated with the radio carpal joint in 9 cases (30%). In 16 patients with trauma, the findings of post-traumatic arthritis included tendon communication (50%), irregular synovium (31%), and rupture of the joint capsule (25%). There was no lymphatic filling. Of 3 scaphoid fracture patients without bony callus formation, fibrous union was verified in one patient and nouncion in 2. O 12 patients with ganglion, communication between the ganglion and radiocarpal joint was seen in 2 cases and no communication in 10 cases

  19. 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.

  20. 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

  1. 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

  2. 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

  3. Radiological evaluation of myositis ossificans

    International Nuclear Information System (INIS)

    Kwon, Yang Sook; Kim, Soo Han; Lim, Young Chae; Shin, Hyun Ja

    1986-01-01

    The 35 patients who have suffered from myositis ossificans were investigate for 11 years. They were post traumatic patients. They trauma was divided into 3 groups; spinal cord injury, direct injury (fracture) and mixed type involving both. We evaluated the age distribution, the frequency of myositis ossificans, predilection site, bilaterally and relation between predilection site and bilaterally to the type of trauma. The results are as follows; 1. The age distribution was highest in 4th decades (12 among 35 patients). 2. In regard to distribution of 35 patients, spinal cord injury were most common (15 cases, 43%), the fracture nextly common (14, 40%) and then mixed type (6, 17%). 3. Among 51 cases of myositis ossificans, the frequency was highest in spinal cord injury (25 cases, 49%), next was fracture (14, 27%). 4. The predilection site of myositis ossificans were thigh (18 cases, 35%), hip (17, 33%) and buttock (6, 12%). 5. In correlation between predilection site of myositis ossificans and level of spinal cord injury, hip is the most frequent site in thoracic injury. 6. The bilaterally of myositis ossificans is 39% (20 among 51 lesions).

  4. 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

  5. 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.

  6. 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

  7. 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

  8. 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)

  9. 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)

  10. 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

  11. 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

  12. 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.

  13. 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

  14. 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.

  15. 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

  16. 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.

  17. 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

  18. 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

  19. Evaluation of radiological safety in industrial gammagraphy services during the construction of Bolivia-Brazil gas transmission lines (GASBOL), by regulatory inspections from brazilian CNEN

    International Nuclear Information System (INIS)

    Aquino, Josilto O. de; Silva, Francisco Cesar A. da; Leocadio, Joao Carlos; Pinho, Adaugoberto S. de; Souza, Luiz Antonio C. de; Lourenco, Manoel J.; Nicola, Marcello S.; Melo, Ivan F.

    2001-01-01

    This paper presents a brief description of the Brazilian Regulatory Authority's (National Commission of Nuclear Energy - CNEN) action about safety control on industrial radioactive installations. It shows some specific radiation safety inspections that were done during the construction of the Bolivia-Brazil Gas Transmission Line (GASBOL). In this GASBOL work, it was used industrial radiography sources for weld quality control. During two years were done thirty regulatory safety inspections in these movable installations that use gamma radiography devices. As final result, it was noticed that the national system of inspection to control the safe use of radioactive sources in industrial activities is really efficient because none overexposure was detect and every CNEN's recommendations were applied by the operators. Some result about the gamma devices and violations are also showed. (author)

  20. Radiology

    International Nuclear Information System (INIS)

    Meyers, M.A.

    1989-01-01

    This paper reports on disease processes originating within the alimentary tract, may extend through the extraperitoneal spaces, and abnormalities primarily arising within other extraperitoneal sites may significantly affect the bowel. Symptoms and signs may be obscure, delayed, or nonspecific, and the area is generally not accessible to auscultation, palpation, or percussion. Radiologic evaluation thus plays a critical role

  1. [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.

  2. 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

  3. 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

  4. 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

  5. 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

  6. 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

  7. 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

  8. 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

  9. 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

  10. 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

  11. 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)

  12. Automated system for the management of the radiological safety in a radiopharmaceutical and labelled compounds production center

    International Nuclear Information System (INIS)

    Amador B, Z.H.; Alvarez Builla de Sologuren, E.

    2006-01-01

    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)

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

    Energy Technology Data Exchange (ETDEWEB)

    Dr. Bradley J Schrader

    2009-03-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Dr. Bradley J Schrader

    2010-10-01

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

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

    International Nuclear Information System (INIS)

    Schrader, Bradley J.

    2009-01-01

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

  16. Evaluation in Radiology as a pedagogic contribution

    International Nuclear Information System (INIS)

    Ros Mendoza, L. H.

    2012-01-01

    After defining evaluation (a systematic process of data collection and analysis in order to take decisions in a specific field; in our case, radiology training at medical school), we should specify the characteristics of such evaluation, which include the aim (what for?), subject-matter (which content?), benchmarks (i.e., the standards against which we are comparing), when to evaluate, and how strictly or at what cost. Once these questions have been answered, we are able to select the most appropriate procedures for evaluation, bearing in mind that evaluation is a process, while grading implies an already made decision. There are different types of evaluation: the initial evaluation, which is not necessarily nominal, is performed to define the student’s level at the beginning of the course; the normative or norm-referenced evaluation has a relative nature, as it compares student achievement to that of others; and the absolute or criterion-referenced evaluation, which is based on established criteria, where the goals which should be achieved become the key element for designing teaching and evaluation. Evaluation may be used to generate motivation. This requires the establishment of clear and relevant objectives as well as knowledge on how to correct mistakes. Oral questions in the classroom may also be motivating. Within the triple domain to be taken into account (cognitive, affective and psychomotor), the objectives to be measured should be considered in a hierarchical order from simple to complex: necessary knowledge, comprehension of such concepts, practical application (in a context that is different from that where knowledge has been gained), and the so-called “superior operations” (analysis, synthesis and grading). Then, the technical features of evaluation will be defined: internal and external validity in relation to difficulty and discrimination; reliability, i.e. accuracy and consistency according to the degree of objectivity; and finally

  17. 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.

  18. Radiology

    International Nuclear Information System (INIS)

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

    1990-01-01

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

  19. Evaluation of separation distance from the temporary storage facility for decontamination waste to ensure public radiological safety after Fukushima nuclear power plant accident

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Min Jung; Go, A Ra; Kim, Kwang Pyo [Kyung Hee University, Yongin (Korea, Republic of)

    2016-09-15

    The object of this study was to evaluate the separation distance from a temporary storage facility satisfying the dose criteria. The calculation of ambient dose rates took into account cover soil thickness, facility size, and facility type by using MCNPX code. Shielding effects of cover soil were 68.9%, 96.9% and 99.7% at 10 cm, 30 cm and 50 cm respectively. The on-ground type of storage facility had the highest ambient dose rate, followed by the semi-ground type and the underground type. The ambient dose rate did not vary with facility size (except 5 × 5 × 2 m size) due to the self-shielding of decontamination waste in temporary storage. The separation distances without cover soil for a 50 × 50 × 2 m size facility were evaluated as 14 m (minimum radioactivity concentration), 33 m (most probably radioactivity concentration), and 57 m (maximum radioactivity concentration) for on-ground storage type, 9 m, 24 m, and 45 m for semi-underground storage type, and 6 m, 16 m, and 31 m for underground storage type.

  20. Evaluation of reactor safety

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1960-04-15

    Although the operation of nuclear reactors has a remarkably good record of safety, the prevention of possible reactor accidents is one of the major factors that atomic planners have to contend with. At the same time, excessive caution may breed an attitude that hampers progress, either by resisting new development or by demanding unnecessarily elaborate and expensive precautions out of proportion to the actual hazards involved. The best course obviously is to determine the possible dangers and adopt adequate measures for their prevention, providing of course, for a reasonable margin of error in judging the hazards and the effectiveness of the measures. The greater the expert understanding and thoroughness with which this is done, the narrower need the margin be. This is the basic idea behind the evaluation of reactor safety

  1. 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.

  2. 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)

  3. 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

  4. 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

  5. Pancreatic transplantation: Radiologic evaluation of vascular complications

    International Nuclear Information System (INIS)

    Snider, J.F.; Hunter, D.W.; Kuni, C.C.; Castaneda-Zuniga, W.R.; Letourneau, J.G.

    1991-01-01

    Transplantation of the pancreas is an increasingly common therapeutic option for preventing or delaying complications of type I diabetes mellitus. The authors studied the relative roles of various radiologic examinations in diagnosing vascular complications in these grafts including arterial and venous thrombosis, stenosis, and anastomotic leak (the most common vascular factors that necessitate pancreatectomy of the transplant), as defined with pathologic or arteriographic data. The results of 78 scintigraphic flow studies, 40 abdominal and pelvic computed tomographic (CT) scans, 27 sonograms, and eight color Doppler studies were evaluated in 52 patients who received a total of 27 cadaveric and 26 living-donor grafts over a 12-year period. These results were correlated with the data from 45 gross and microscopic pathologic studies and 37 arteriograms to determine their relative value in enabling detection of graft thrombosis and other vascular complications. Scintigraphy, CT, sonography, and color Doppler were all sensitive in detection of generalized graft abnormalities but lacked specificity in defining the underlying etiologic factors

  6. Pancreatic transplantation: Radiologic evaluation of vascular complications

    Energy Technology Data Exchange (ETDEWEB)

    Snider, J.F.; Hunter, D.W.; Kuni, C.C.; Castaneda-Zuniga, W.R.; Letourneau, J.G. (Univ. of Minnesota Hospital and Clinic, Minneapolis (USA))

    1991-03-01

    Transplantation of the pancreas is an increasingly common therapeutic option for preventing or delaying complications of type I diabetes mellitus. The authors studied the relative roles of various radiologic examinations in diagnosing vascular complications in these grafts including arterial and venous thrombosis, stenosis, and anastomotic leak (the most common vascular factors that necessitate pancreatectomy of the transplant), as defined with pathologic or arteriographic data. The results of 78 scintigraphic flow studies, 40 abdominal and pelvic computed tomographic (CT) scans, 27 sonograms, and eight color Doppler studies were evaluated in 52 patients who received a total of 27 cadaveric and 26 living-donor grafts over a 12-year period. These results were correlated with the data from 45 gross and microscopic pathologic studies and 37 arteriograms to determine their relative value in enabling detection of graft thrombosis and other vascular complications. Scintigraphy, CT, sonography, and color Doppler were all sensitive in detection of generalized graft abnormalities but lacked specificity in defining the underlying etiologic factors.

  7. 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)

  8. Compliance of Iranian dentists with safety standards of oral radiology

    Science.gov (United States)

    Shahab, S; Kavosi, A; Nazarinia, H; Mehralizadeh, S; Mohammadpour, M; Emami, M

    2012-01-01

    Objectives Dentists use radiographs in their daily practice. Their knowledge and behaviour towards radiographic examination can affect patients' exposure to radiation. The aim of this study was to survey the knowledge and behaviour of Iranian dentists regarding oral radiology safety standards. Methods 1000 questionnaires were given to the participants of the 48th Annual Congress of the Iranian Dental Association, of which 700 were returned. The participants were asked about demographic data, primary knowledge of radiation protection, selection criteria, radiographic equipment and technique, methods of patient and personnel protection and management of radiographic waste. Descriptive analysis of data was performed. Results 44% of respondents said the initial radiograph they took was of the periapical view of a limited area. 12% preferred the periapical paralleling technique. F-speed film was used by 9% and E-speed film by 62%. Only 2% had digital receptors. Proper exposure time was selected by 26.5%. The use of long and rectangular collimators was 15% and 6%, respectively. 34% occasionally covered their patients with both thyroid shields and lead aprons. 36% used the position and distance rule correctly for their own protection. Proper disposal of the used processing solutions and the lead foils were done by only 1% and 3%, respectively. Conclusions It can be concluded that the majority of dentists in the study group did not select the proper method, material and equipment in order to minimize the exposure of their patient to unnecessary radiation in dental radiography. PMID:22301640

  9. 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

  10. 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.)

  11. 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.)

  12. 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.

  13. 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.)

  14. Effect of Kiken-Yochi training (KYT) induction on patient safety at the department of radiological technology

    International Nuclear Information System (INIS)

    Yasuda, Mitsuyoshi; Uchiyama, Yushi; Sakiyama, Koshi; Shibata, Masako; Sasaki, Haruaki; Kato, Kyoichi; Nakazawa, Yasuo; Sanbe, Takeyuki; Yoshikawa, Kohki

    2013-01-01

    In this report, we evaluated whether radiological technologists' (RTs') awareness of patient safety would improve and what kind of effects would be seen at the department of radiological technology by introducing KYT [K: kiken (hazard), Y: yochi (prediction), T: (training)]. KYT was carried out by ten RTs based on a KYT sheet for the department of radiological technology. To evaluate the effects of KYT, we asked nine questions each to ten participants before and after KYT enforcement with regard to their attitude to patient safety and to operating procedures for working safely. Significant improvements after KYT enforcement were obtained in two items concerning medical safety: It is important for any risk to be considered by more than one person; The interest in preventive measures against medical accident degree conducted now) and one concerning operating procedures (It is necessary to have a nurse assist during testing with the mobile X-ray apparatus) (p<0.05). Performing KYT resulted in improved awareness of the importance of patient safety. KYT also enabled medical staffers to evaluate objectively whether the medical safety measures currently performed would be effective for patients. (author)

  15. 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

  16. 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.

  17. Safety significance evaluation system

    International Nuclear Information System (INIS)

    Lew, B.S.; Yee, D.; Brewer, W.K.; Quattro, P.J.; Kirby, K.D.

    1991-01-01

    This paper reports that the Pacific Gas and Electric Company (PG and E), in cooperation with ABZ, Incorporated and Science Applications International Corporation (SAIC), investigated the use of artificial intelligence-based programming techniques to assist utility personnel in regulatory compliance problems. The result of this investigation is that artificial intelligence-based programming techniques can successfully be applied to this problem. To demonstrate this, a general methodology was developed and several prototype systems based on this methodology were developed. The prototypes address U.S. Nuclear Regulatory Commission (NRC) event reportability requirements, technical specification compliance based on plant equipment status, and quality assurance assistance. This collection of prototype modules is named the safety significance evaluation system

  18. 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)

  19. 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.

  20. 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.

  1. 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

  2. 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

  3. 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.

  4. 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

  5. Radiology

    International Nuclear Information System (INIS)

    Edholm, P.R.

    1990-01-01

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

  6. User questionnaire to evaluate the radiological workspace

    NARCIS (Netherlands)

    van Ooijen, Peter M. A.; Koesoema, Allya P.; Oudkerk, Matthijs

    2006-01-01

    Over the past few years, an increase in digitalization of radiology departments can be seen, which has a large impact on the work of the radiologists. This impact is not only demonstrated by the increased use of digital images but also by changing demands on the whole reading environment. In this

  7. Learning from errors in radiology to improve patient safety.

    Science.gov (United States)

    Saeed, Shaista Afzal; Masroor, Imrana; Shafqat, Gulnaz

    2013-10-01

    To determine the views and practices of trainees and consultant radiologists about error reporting. Cross-sectional survey. Radiology trainees and consultant radiologists in four tertiary care hospitals in Karachi approached in the second quarter of 2011. Participants were enquired as to their grade, sub-specialty interest, whether they kept a record/log of their errors (defined as a mistake that has management implications for the patient), number of errors they made in the last 12 months and the predominant type of error. They were also asked about the details of their department error meetings. All duly completed questionnaires were included in the study while the ones with incomplete information were excluded. A total of 100 radiologists participated in the survey. Of them, 34 were consultants and 66 were trainees. They had a wide range of sub-specialty interest like CT, Ultrasound, etc. Out of the 100 responders, 49 kept a personal record/log of their errors. In response to the recall of approximate errors they made in the last 12 months, 73 (73%) of participants recorded a varied response with 1 - 5 errors mentioned by majority i.e. 47 (64.5%). Most of the radiologists (97%) claimed receiving information about their errors through multiple sources like morbidity/mortality meetings, patients' follow-up, through colleagues and consultants. Perceptual error 66 (66%) were the predominant error type reported. Regular occurrence of error meetings and attending three or more error meetings in the last 12 months was reported by 35% participants. Majority among these described the atmosphere of these error meetings as informative and comfortable (n = 22, 62.8%). It is of utmost importance to develop a culture of learning from mistakes by conducting error meetings and improving the process of recording and addressing errors to enhance patient safety.

  8. 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)

  9. Preclosure radiological safety analysis for the exploratory shaft facilities

    International Nuclear Information System (INIS)

    Ma, C.W.; Miller, D.D.; Jardine, L.J.

    1992-06-01

    This study assesses which structures, systems, and components of the exploratory shaft facility (ESF) are important to safety when the ESF is converted to become part of the operating waste repository. The assessment follows the methodology required by DOE Procedure AP-6.10Q. Failures of the converted ESF during the preclosure period have been evaluated, along with other underground accidents, to determine the potential offsite radiation doses and associated probabilities. The assessment indicates that failures of the ESF will not result in radiation doses greater than 0.5 rem at the nearest unrestricted area boundary. Furthermore, credible accidents in other underground facilities will not result in radiation doses larger than 0.5 rem, even if any structure, system, or component of the converted ESF fails at the same time. Therefore, no structure, system, or component of the converted ESF is important to safety

  10. 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

  11. 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.

  12. 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.)

  13. 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.

  14. 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.)

  15. 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

  16. 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)

  17. 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)

  18. Objectives of safety evaluation

    International Nuclear Information System (INIS)

    Rosen, M.

    1980-01-01

    An examination of the safety aspects of exported nuclear power plants demonstrates that additional and somewhat special considerations exist for these plants. In view of this and the generally small regulatory staffs of importing coutnries, suggestions are given for measures which should be taken by various organizations involved in the export and import of nuclear power facilities to raise the level of the very essential safety assessment. (orig.)

  19. 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.)

  20. 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)

  1. 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

  2. '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)

  3. Eminent radiological safety issues confronting the State of Hawaii

    International Nuclear Information System (INIS)

    Hashimoto, H.H.

    1984-01-01

    The State of Hawaii currently has over one hundred radioactive material use licenses. Nuclear Regulatory Commission licenses are primarily held by hospitals, industrial radiographers, and academic institutions. Complementing this, the State Department of Health regulates x-ray machines, radium, and has an emergency response role for accidents involving radioactive materials. The existing radiation protection program was created by piecemeal legislation. As a result, regulatory surveillance and actual control vary widely among the agencies. The State Legislature, in 1980, decided that action must be taken to set a clear state policy towards the use and disposal of nuclear materials. It was therefore recommended that the State of Hawaii Radiation Safety Advisory Committee be convened to assist the state in the evaluation of the issues. This report contains issue papers on radiation related topics addressed by the Radiation Safety Advisory Committe. Topics discussed include transportation, environmental monitoring, emergency response, and waste disposal. A survey of various radioactive sources identified medical applications as a category requiring stricter control. Selected chapters of the Hawaii Revised Statutes are also examined

  4. 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

  5. Dosimetric evaluation program for dental radiology practices

    International Nuclear Information System (INIS)

    Gregori, B.; Milat, J.; Fernandez, J.; Micinquevich, S.; Andrieu, J.

    1992-01-01

    The preliminary results of a program undertaken to estimate the doses to patients associated with dental radiology practices in Argentine, are presented. Information collected from the search demonstrated that the Dieck and coronal techniques are the most commonly used practices, while all the examinations are performed by using a circular collimator. For both practices, the dosimetric studies were carried out on a Rando Alderson phantom. All dose measurements were made using thermoluminescent detectors LiF and Ca 2 F. In addition, a mathematical model was developed by applying the Monte Carlo method to a MIRD-V phantom. Circular and rectangular collimators were used. Absorbed dose distribution on head and neck, as well as surface dose distribution, were estimated. The comparison of the performance of both collimators shows that the use of the rectangular one allows for a dose reduction of 80%. Besides, a good correlation between the physical and mathematical models applied was found. (author)

  6. 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)

  7. Radiologic evaluation of spinal epidural mass

    International Nuclear Information System (INIS)

    Lee, Ho Kyu; Lee, Moon Kyu; Chang, Kee Hyun

    1987-01-01

    It is often difficult to differentiate each pathologic entity among various spinal epidural masses on the radiologic basis. We retrospectively analysed radiologic findings of 67 cases of pathologically proven spinal epidural mass to find out any specific findings of each epidural mass. The results are as follows : 1. Of 67 cases, metastasis (16 cases), epidural abscess (15 cases), neurogenic tumor (16 cases) and meningioma (8 cases) are most common. The others consist of epidural angioma (3 cases), vertebral hemangioma (2 cases), chondrosarcoma (2 cases), fibrosarcoma (1 case), eosinophilic granuloma (1 case), lymphoma (1 case), lipoma (1 case) and lymphoid hyperplasia (1 case). 2. Destruction of the adjacent bone was commonly associated with the epidural mass in metastasis (75%) and epidural abscess (67%). It was also noted in 2 cases of chondrosarcoma, 1 fibrosarcoma and 1 eosinophilic granuloma. 3. Pressure erosion of adjacent bone was demonstrated in neurogenic tumor (75%) and meningioma (25%). 4. Narrowing of intervertebral space was seen in only 27% of epidural abscess. 5. The paraspinal tumor was associated in 67% of metastasis, 80% of epidural abscess, 75% of neurogenic tumor, 33% of meningioma. It was also seen in 2 cases of chondrosarcoma, 1 fibrosarcoma and 1 eosinophilic granuloma. 6. The intradural tumor was associated in 50% of neurogenic tumor and 67% of meningioma. 7. On axial CT image, most of the epidural mass shows eccentric location with displacing dural sac to the opposite side. The diseases that occasionally show encircling location are metastasis, epidural abscess, vertebral hemangioma, chondrosarcoma, eosinophilic granuloma, and lymphoma. Neurogenic tumor only shows multicentric location. 8. The disease extent more than height of one vertebral body was seen in 80% of epidural abscess, 58% of neurogenic tumor, 100% of epidural angioma. It was also seen in 2 cases of chondrosarcoma, 1 fibrosarcoma, 1 eosinophilic granuloma, 1 lymphoma, 1

  8. Radiological safety training for accelerator facilities: DOE handbook

    International Nuclear Information System (INIS)

    1997-03-01

    This program management guide describes the proper implementation standard for core training as outline in the DOE Radiological Control (RadCon) Manual. Its purpose is to assist DOE employees and Managing and Operating (M ampersand O) contractors having responsibility for implementing the core training recommended by the RadCon Manual

  9. Radiological safety training for accelerator facilities: DOE handbook

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-03-01

    This program management guide describes the proper implementation standard for core training as outline in the DOE Radiological Control (RadCon) Manual. Its purpose is to assist DOE employees and Managing and Operating (M&O) contractors having responsibility for implementing the core training recommended by the RadCon Manual.

  10. 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)

  11. 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)

  12. 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.)

  13. 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)

  14. Radiological and clinical evaluation of colorectal cancer

    International Nuclear Information System (INIS)

    Shin, O. J.; Chin, S. Y.; Lee, K. S.; Park, S. S.

    1982-01-01

    One hundred thirty two cases of the pathologically proven colorectal cancer at Korea Atomic Energy Research Institute Hospital in the period from January 1973 to June 1980 were analyzed radiologically and clinically. The results were as follows: 1. The colorectal cancer was prevalent in rectosigmoid area and in the fourth to seventh decade of life. 2. The clinical pictures were classified into two groups. The one was rectosigmoid cancer with bowel habit changes. The other was one with no specific symptoms or signs. The clinical pictures of the right colon cancer were rather indirected, chronic and systemic than those of the left one. 3. The roentgenological findings were classified into two groups. The one was rectum and left colon cancer with symmetrical annular narrowing and the other showed trumpet-like proximal dilatation. 4. The most frequent complication was intestinal obstruction. 5. The majority of colorectal cancer was adenocarcinoma. The squamous cell carcinoma and atypical cell carcinoma were most prevalent in rectum, but malignantly lymphoma often occurred in right colon. The rarest colorectal cancer was atypical cell carcinoma in rectum

  15. Radiological evaluation of chinchilla mastication organs

    International Nuclear Information System (INIS)

    Sulik, M.; Sobolewska, E.; Ey-Chmielewska, H.; Fraczak, B.; Seremak, B.

    2007-01-01

    The studies were undertaken in order to analyse radiologically bone structures of the maxilla and mandibula including the teeth in chinchillas that show pathological overgrowth of incisor and molar teeth. The analysis included 10 sick and 10 healthy animals, whose skulls were post-mortem dissected and compared. The x - ray pictures were examined for significant elements of the bone structure; shape and saturation of incisor and molar teeth, shape, saturation, and thickness of cranial sutures, as well as the evenness of the intensity of the symptoms. The structure of the incisor teeth revealed excessive tissue mineralisation. The tooth canal was invisible, which may indicate fibrosis of the pulp. The cutting edges exhibited excessive mineralisation, which implied a lack of abrasion. The pulp growth cone was invisible. The shape of the upper incisor was altered and semicircular, this prevented contact between the edges of the opposing teeth. The surface structure of the molars was considerably saturated with invisible dental pulp, which may imply fibrosis. The roots of the teeth were distended and flask-like inb shape, and considerably saturated. The visible excessive mineralisation in all the molar teeth implied a general process of osteosclerosis. (author)

  16. 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.

  17. 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.

  18. 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

  19. Experiment to evaluate software safety

    International Nuclear Information System (INIS)

    Soubies, B.; Henry, J.Y.

    1994-01-01

    The process of licensing nuclear power plants for operation consists of mandatory steps featuring detailed examination of the instrumentation and control system by the safety authorities, including softwares. The criticality of these softwares obliges the manufacturer to develop in accordance with the IEC 880 standard 'Computer software in nuclear power plant safety systems' issued by the International Electronic Commission. The evaluation approach, a two-stage assessment is described in detail. In this context, the IPSN (Institute of Protection and Nuclear Safety), the technical support body of the safety authority uses the MALPAS tool to analyse the quality of the programs. (R.P.). 4 refs

  20. 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.

  1. 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)

  2. 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

  3. Radiological safety design considerations for fusion research experiments

    International Nuclear Information System (INIS)

    Crase, K.W.; Singh, M.S.

    1979-01-01

    A wide variety of fusion research experiments are in the planning or construction stages. Two such experiments, the Nova Laser Fusion Facility and the Mirror Fusion Test Facility (MFTF), are currently under construction at Lawrence Livermore Laboratory. Although the plasma chamber vault for MFTF and the Nova target room will have thick concrete walls and roofs, the radiation safety problems are made complex by the numerous requirements for shield wall penetrations. This paper addresses radiation safety considerations for the MFTF and Nova experiments, and the need for integrated safety considerations and safety technology development during the planning stages of fusion experiments

  4. Radiologic evaluation of carcinoma of the gallbladder

    International Nuclear Information System (INIS)

    Kim, I. Y.; Kim, K. W.; Yoo, H. S.; Lee, J. T.; Park, C. Y.

    1983-01-01

    Thirty five cases of pathlogically proven carcinoma of the gallbladder at Yonsei Univ. College. of Med. Severance Hospital in the period from May, 1978 to Oct, 1982 were analyzed radiologically and clinically. The brief results are as follows: 1. The ratio of male to female was 1 : 1.2 and prevalent in the sixth decade of life. 2. Clinical feature show RUQ pain in 24 cases. Epigastric pain in 13 cases and jaundice in 6 cases, symptom duration is variable from 1 week to over year. 3. Oral and IV cholangiography were performed in 17 cases. Nonvisualization of gallbladder was observed in 14 cases. Filling defect in gallbladder was observed in 2 cases and air biliarygram is observed in 1 case. 4. UGI series was performed in 11 cases. Postbulbar indentation was observed in 9 cases, gastric antrum indentation in 2 cases, postbulbar indentation with adhesion in 2 cases and normal finding was observed in 2 cases. 5. PTC was performed in 7 cases. Nonvisualization of gallbladder was observed in 7 cases, abrupt obstruction at porta hepatis in 3 cases, abrupt eccentric obstruction extrahepatic duct at cystic duct level in 2 cases, lobulated mass effect in extrahepatic duct at the level of cystic duct opening in 1 case. Round swing of extrahepatic duct with dilatation was observed in 1 case. 6. ERCP was performed in 11 cases. Nonvisualization of gallbladder was observed in 8 cases, irregular large intraluminal filling defect in 2 cases, multiple stone in 1 case, abrupt narrowing proximal CBD in 3 cases, extrinsic mass effect in CHD was observed in 1 case. 7. Celiac angiography was performed in 3 cases. Cystic artery hypertrophy was observed in 1 case and halo appearance in gallbladder area was observed in 1 case. 8. Ultrasound for investigation of carcinoma of gallbladder was performed in 16 cases. Homogenous echoes in gallbladder was observed in 6 cases, Bull's eye appearance in 4 cases, fungasting mass in

  5. 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)

  6. 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

  7. 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.

  8. 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)

  9. 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)

  10. 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)

  11. [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).

  12. 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

  13. Malaysian experiences in radiological safety assessment on norm wastes

    International Nuclear Information System (INIS)

    Syed Hakimi Sakuma Syed Ahmad; Khairuddin Mohamad Kontol

    2000-01-01

    Radiological Impact Assessments (RIAs) on proposed disposal sites for NORM wastes were performed in Malaysia. Analysis results were used to derive site specific guidelines for allowable residual concentrations of radionuclides in soil, calculation of doses and risks. Appropriate use scenarios and site specific parameters were used as much as possible so as to be realistic so that will reasonably ensure that individual dose limits and or constraints will be achieved. Disposals were performed to fulfil Atomic Energy Licensing Board of Malaysia (AELB) requirements for which the operator must carry out a radiological impact assessment. This is to demonstrate that no member of public will be exposed to more than 1 mSv/year from all activities. Fatal cancer risk factor is 5x10 -2 per man.Sv. Radionuclides of main concern are radium-226 and radium-228 which are considered as toxic. Sensitivity and uncertainty analyses were performed to show that the parameters used as input into the computer model were justified so as to improve confidence of the public and the AELB in respect of the results of the analysis. Case study to determine a proposed near surface disposal site for treated oil sludge was described. (author)

  14. 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

  15. 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)

  16. 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

  17. 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

  18. 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

  19. 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

  20. 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

  1. 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.

  2. 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.

  3. 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...

  4. 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)

  5. 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

  6. The maintenance and the radiological safety in gamma irradiation facilities

    International Nuclear Information System (INIS)

    Torres C, G.

    1991-01-01

    Presently work the outstanding aspects of the operation and maintenance of the Industrial Irradiator JS 6500 are described that the ININ operates, in the Nuclear Center of Salazar, Estado de Mexico and its relationship with the radiological security for the occupationally exposed personnel. The signal devices are described and of control of the associate teams, as the system of cooling of the source; the plant of treatment of water of the pool and the system of extraction of ozone. On the other hand the procedures are mentioned for the sure operation and the application of the annual programs of maintenance, in their aspects of more interest, to reduce to the maximum the correction of faults, during the routine operation

  7. 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

  8. 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

  9. Medical social consequences of the safety problems of oncological radiology

    International Nuclear Information System (INIS)

    Pilipenko, M.Yi.; Stadnik, L.L.; Shal'opa, O.Yu.; Rigan, M.M.; Skalets'kij, Yu.M.

    2015-01-01

    Actuality of the problem of patient safety in oncoradiology in Ukraine is grounded. The results of international audit TLD (IAEA/WHO) quality during dosimetry procedures cobalt-telegamma vehicles in Ukraine are investigated, as well as legal and regulatory framework providing for the safety of radiotherapy care, scientific publications on patient safety. Methods: statistical, analytical, bibliographical, systematic approach. On the example of radiation therapy using the results of the international program of the IAEA/WHO TLD audit quality dosimetry calibration devices for remote gamma therapy in Ukraine from 1998 to 2014 the attempt to assess the extent of medical and social consequences of underestimating of medical errors in oncoradiology is made. The problems of regulatory nature of medical errors in oncoradiology are preliminary identified. The problem of medical errors in the treatment of cancer radiation methods in Ukraine is extremely important. Usually the problems of errors in oncoradiology are considered in organizational, technical, personnel and technical aspects, while medical and social consequences of problem are not covered. About 10 thousand of cancer patients in year may suffer from errors related only to dose calculation according to the optimistic variant, while the number of patients for the same period on the pessimistic case can reach 15 thousand. There are a number of legal character problems in oncoradiology related to patient safety that require clarification. The first priority for improving the safety of patients in oncoradiology is the recording and analysis of radiation therapy defects and their consequences

  10. Radiologic evaluation of nonalcoholic fatty liver disease

    Science.gov (United States)

    Lee, Seung Soo; Park, Seong Ho

    2014-01-01

    Nonalcoholic fatty liver disease (NAFLD) is a frequent cause of chronic liver diseases, ranging from simple steatosis to nonalcoholic steatohepatitis (NASH)-related liver cirrhosis. Although liver biopsy is still the gold standard for the diagnosis of NAFLD, especially for the diagnosis of NASH, imaging methods have been increasingly accepted as noninvasive alternatives to liver biopsy. Ultrasonography is a well-established and cost-effective imaging technique for the diagnosis of hepatic steatosis, especially for screening a large population at risk of NAFLD. Ultrasonography has a reasonable accuracy in detecting moderate-to-severe hepatic steatosis although it is less accurate for detecting mild hepatic steatosis, operator-dependent, and rather qualitative. Computed tomography is not appropriate for general population assessment of hepatic steatosis given its inaccuracy in detecting mild hepatic steatosis and potential radiation hazard. However, computed tomography may be effective in specific clinical situations, such as evaluation of donor candidates for hepatic transplantation. Magnetic resonance spectroscopy and magnetic resonance imaging are now regarded as the most accurate practical methods of measuring liver fat in clinical practice, especially for longitudinal follow-up of patients with NAFLD. Ultrasound elastography and magnetic resonance elastography are increasingly used to evaluate the degree of liver fibrosis in patients with NAFLD and to differentiate NASH from simple steatosis. This article will review current imaging methods used to evaluate hepatic steatosis, including the diagnostic accuracy, limitations, and practical applicability of each method. It will also briefly describe the potential role of elastography techniques in the evaluation of patients with NAFLD. PMID:24966609

  11. Radiologic evaluation of neonatal and childhood hypertension

    International Nuclear Information System (INIS)

    Amour, T.S.; Siegel, M.J.

    1986-01-01

    The authors reviewed the radiographic findings in 40 neonates and 90 children and adolescents with hypertension. In neonates the common causes of secondary hypertension were renal vascular thrombosis (33%), polycystic kidney disease (25%), and obstructive uropathy (17%). US and renal scans were the most useful studies and yielded diagnostic information in approximately 70% of cases. Surgically correctable hypertension was found in almost half the patients. In patients over 1 year of age, the common causes of hypertension were medical renal disease (50%) and renovascular hypetension (15%). Urography, scintigraphy, and arteriography played a crucial role in their evaluation

  12. Radiological evaluation of the acromioclavicular joint

    International Nuclear Information System (INIS)

    Vaeaetaeinen, U.; Maekelae, A.; Pirinen, A.

    1991-01-01

    X-ray measurement of the acromioclavicular (AC) joint may cause difficulties because of different projections and the lack of a reproducible measurement. In order to find the ideal measurement to estimate the state of the AC joint, 28 healthy adult volunteers were X-rayed. The least vulnerable measurement for errors in projection was the distance between the coracoid process and the upper part of the clavicle. The effect of stress was evaluated; the range of normal AC joint laxity was determined as 3 mm. (orig.)

  13. Radiological evaluation of the acromioclavicular joint

    Energy Technology Data Exchange (ETDEWEB)

    Vaeaetaeinen, U.; Maekelae, A. (Kuopio Univ. Central Hospital (Finland). Dept. of Surgery); Pirinen, A. (Kuopio Univ. Central Hospital (Finland). Dept. of Radiology)

    1991-02-01

    X-ray measurement of the acromioclavicular (AC) joint may cause difficulties because of different projections and the lack of a reproducible measurement. In order to find the ideal measurement to estimate the state of the AC joint, 28 healthy adult volunteers were X-rayed. The least vulnerable measurement for errors in projection was the distance between the coracoid process and the upper part of the clavicle. The effect of stress was evaluated; the range of normal AC joint laxity was determined as 3 mm. (orig.).

  14. Radiological evaluation of nonvisualizing kidney on IVP

    International Nuclear Information System (INIS)

    Moon, J. H.; Sung, K. B.; Cho, O. K.; Hahm, C. K.

    1983-01-01

    IVP is simple, noninvasive screening examination of the kidneys and is helpful for evaluation of the functional and structural changes if the pyelogram was obtained. Unilateral nonvisualizing kidney may be resulted from various diseases that can produce vascular obstruction, functional determination of the glomerular filtration and obstruction of the lower urinary tract. In cases of nonvisualizing kidney further study including RGP, renal angiography, CT, ultrasonography and RI imaging is needed. During the perfect of 10 years from 1972 to 1981, 100 cases of nonvisualizing kidney which could be diagnosed by other imaging studies. The authors reviews medical records and finding of RGP, renal angiography, CT and ultrasonography of the nonvisualizing kidneys. The results were as follows: 1. The material included 53 male and 47 female patterns. The age distribution was broad, but mostly in the twenties and forties of ages. 2. There was no remarkable differentiation between sides of involvement in both sexes. 3. The underlying diseases of nonvisualizng kidney on IVP were renal tuberculosis (33 patients), ureteral stricture (16 patients), ureteral stone (12 patients), real tumor (10 patients), pelvic mass (10 patients), chronic pyelonephritis (8 patients), renal agenesis (5 patients), renal trauma (4 patients), and renal disease of vascular origin (2 patients) respectively. 4. RGP was performed in 79 out of 100 cases. RGP was the most confirmative diagnostic procedure in cases of inflammatory diseases of the kidney and renal pelvic tumors. 5. Renal angiography was performed in 19 cases. Renal angiography was very helpful in the diagnosis and evaluation of the extent of the diseases in 6 cases of renal tumors, 3 cases renal trauma, 2 cases of renal vascular diseases and 3 cases of renal agenesis. 6. Body CT was performed in one case of renal cell carcinoma and other 6 cases of hydronephrosis mainly from tumors of the pelvic cavity including 4 cervical carcinomas and a

  15. Accelerator driven systems from the radiological safety point of view

    Indian Academy of Sciences (India)

    Spallation reaction products like high energy gammas, neutrons, muons, pions and several radiotoxic nuclides including Po-210 complicate the situation. In the present paper, we discuss radiation safety measures like bulk shielding, containment of radiation leakage through ducts and penetration and induced activity in the ...

  16. 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.)

  17. 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.).

  18. 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.

  19. 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.

  20. 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.

  1. 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

  2. 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)

  3. 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)

  4. 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)

  5. Radiological safety assessment inside ancient Egyptian tombs in Saqqara.

    Science.gov (United States)

    El-Kameesy, S U; Salama, E; El-Fiki, S A; Ehab, M; Rühm, W

    2016-12-01

    Many archaeological sites in Egypt are unique worldwide, such as ancient tombs and pyramids, because they document fundamental developments in human civilization that took place several thousands of years ago. For this reason, these sites are visited by numerous visitors every year. The present work is devoted to provide a pre-operational radiological baseline needed to quantify occupational radiation exposure at the famous Saqqara region in Cairo, Egypt. A hyperpure Ge detector has been used in the γ-ray spectrometric analysis while the (222)Rn concentration was measured using a portable radon monitor RTM 1688-2, SARAD. The mean specific activities of (226)Ra, (232)Th and (40)K in the samples collected from the interior walls of the Saqqara tombs were determined and found to show average values of 16, 8.5 and 45 Bq kg(-1), respectively. The concentration of radon was measured inside the tombs Serapeum, South tomb and the Zoser Pyramid (fifth level) and an associated average working level of 0.83 WL was obtained. In order to avoid the health hazards associated with the exposure to radon during the long period of work inside these tombs, proposed solutions are introduced.

  6. Exercises for radiological and nuclear emergency response. Planing - performance - evaluation

    International Nuclear Information System (INIS)

    Bayer, A.; Faleschini, J.; Goelling, K.; Stapel, R.; Strobl, C.

    2010-01-01

    The report of the study group emergency response seminar covers the following topics: (A) purpose of exercises and exercise culture: fundamentals and appliances for planning, performance and evaluation; (B) exercises in nuclear facilities; (C) exercises of national authorities and aid organizations on nuclear scenarios; exercises of national authorities and aid organizations on other radiological scenarios; (D) exercises in industrial plants, universities, medical facilities and medical services, and research institutes; (E) transnational exercises, international exercises; (F): exercises on public information.

  7. Online Food Safety Information System for Nuclear or Radiological Emergencies

    International Nuclear Information System (INIS)

    Albinet, Franck; Adjigogov, Lazar; Dercon, Gerd

    2016-01-01

    Over the last year, the protocol with regards to data management and visualization requirements for food safety decision-making, developed under CRP D1.50.15 on R esponse to Nuclear Emergency Affecting Food and Agriculture , was further implemented. The development team moved away from early series of disconnected prototypes to a more advanced Information System integrating both data management and visualization components outlined in the agreed protocol

  8. 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.

  9. 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

  10. Quality and safety based management of radiological and clinical equipment

    International Nuclear Information System (INIS)

    Arora, S.; Saini, P.S.

    2001-01-01

    TQM (Total quality management) is the 'buzz' acronym expected in almost every aspect of industrial manufacturing, product development and services solicited by the outside agencies. The correct management of the many technological resources in health institutions in terms of efficiency, effectiveness and safety is a necessity in view of the criteria on which modern medicine is based. Almost all activities -be they diagnostic, therapeutic and rehabilitative - carried out within a modern hospital are based on widespread application of equipment and technology, the efficiency of which can directly influence the quality of service offered to the patient

  11. 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

  12. 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)

  13. 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.

  14. 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)

  15. The public component of sea basins radiological safety

    International Nuclear Information System (INIS)

    Agutov, V.I.

    2003-01-01

    Full text: The sea is the key and essential element of the basin although the bigger share of the basin consists of the river ecosystems. The classical theory of sustainable basin development implies that the one of the main indicator of sustainable development is the river ecosystem biodiversity and especially the sturgeon kind of fish with long life cycle. The fish biodiversity and stocks of valuable fish were totally destroyed. One of the most serious causes for that was the inadequate water policy aimed at the construction of the river dam complexes and the construction of the huge water reservoirs. These water reservoirs were used for different purposes, but the main danger is coming from their usage as nuclear power plant cooling ponds. The wide public has received the opportunity to learn about the ecological danger of such objects. The modern Russian society doesn't fully believe to the results of monitoring by state agencies. In order to propel these activities the creation of non-governmental ecological organizations is needed within the all the key elements of river ecosystems. The information skeleton throughout the whole basin needed for successful and effective functioning of these organizations can be constructed only under the condition of having good and modern means of communication such as electronic ones (e-mail, Internet) and publishing of own newspapers and bulletins. Our regional non-governmental organization has created already such a network within the Don and accepting existing local organizations as members. The activities on the creation of the same networks have been already induced in the Volga and Ural rivers basins. Now the networks are more or less shaped and we start equipping the local NGOs with radiation detection devices of 'Inspector'class for measuring the beta and gamma radiation. Having the needed experts and specialists the independent networked organizations will be able not only to monitor the radiological situation

  16. 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

  17. 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

  18. Safety evaluation of food flavorings

    International Nuclear Information System (INIS)

    Schrankel, Kenneth R.

    2004-01-01

    Food flavorings are an essential element in foods. Flavorings are a unique class of food ingredients and excluded from the legislative definition of a food additive because they are regulated by flavor legislation and not food additive legislation. Flavoring ingredients naturally present in foods, have simple chemical structures, low toxicity, and are used in very low levels in foods and beverages resulting in very low levels of human exposure or consumption. Today, the overwhelming regulatory trend is a positive list of flavoring substances, e.g. substances not listed are prohibited. Flavoring substances are added to the list following a safety evaluation based on the conditions of intended use by qualified experts. The basic principles for assessing the safety of flavoring ingredients will be discussed with emphasis on the safety evaluation of flavoring ingredients by the Food and Agriculture Organization (FAO) and World Health Organization (WHO) Joint Expert Committee on Food Additives (JECFA) and the US Flavor and Extract Manufacturers Expert Panel (FEXPAN). The main components of the JECFA evaluation process include chemical structure, human intake (exposure), metabolism to innocuous or harmless substances, and toxicity concerns consistent with JECFA principles. The Flavor and Extract Manufacturers Association (FEMA) evaluation is very similar to the JECFA procedure. Both the JECFA and FEMA evaluation procedures are widely recognized and the results are accepted by many countries. This implies that there is no need for developing countries to conduct their own toxicological assessment of flavoring ingredients unless it is an unique ingredient in one country, but it is helpful to survey intake or exposure assessment. The global safety program established by the International Organization of Flavor Industry (IOFI) resulting in one worldwide open positive list of flavoring substances will be reviewed

  19. Radiological Operational Safety Verification for LILW Disposal Facility

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Ju Youl [FNC Technology, SNU, Seoul (Korea, Republic of); Jeong, Seung Young; Kim, Byung Soo [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2011-10-15

    The successful implementation of radioactive waste repository program depends on scientific and technical aspects of excellent safety strategy as well as on societal aspects such as stakeholder acceptance and confidence. Monitoring is considered as key element in serving both ends. It covers all stages of the disposal process from site selection to institutional monitoring after the repository is closed. Basically, the purpose of the monitoring of radioactive waste disposal facility is not to reveal any increase of radioactivity due to the repository, but to provide reassurance and confirmation that the repository is fulfilling its passive safety purpose as an initial disposal concept and that long-term safety driven by regulatory requirements is ensured throughout the entire lifetime of disposal facility including post-closure phase. Five principal objectives of monitoring of geological disposal are summarized by IAEA-TECDOC-1208 as follows 1) Supporting management decisions in a staged programme of repository development: 2) Strengthening understanding of system behavior: 3) Societal decision making: 4) Accumulating an environmental database: 5) Nuclear safeguards (if repository contains fissile material, i.e., spent fuel or plutonium-rich waste) Based on the results of detailed studies of the above objectives and related phenomena, 6 categories of potential monitoring parameters are determined as follows: (1) degradation of repository structures, (2) behavior of the waste package and its associated buffer material, (3) near field chemical interactions between introduced materials, groundwater and host rock, (4) chemical and physical changes to the surrounding geosphere, (5) provision of an environmental database, and (6) nuclear safeguards. Typical monitoring parameters include temperature (heat), water level, pore-water and moisture content (groundwater), rock pressure, fractures, displacement and deformation (stress), water quality chemistry and dissolved

  20. 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)

  1. 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

  2. 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

  3. 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)

  4. Radiological safety aspects of the operation of electron linear accelerators

    International Nuclear Information System (INIS)

    Swanson, W.P.

    1979-01-01

    This manual is intended as a guide for the planning and implementation of radiation protection programmes for all types of electron linear accelerators. Material is provided for guidance in the planning and installation stages, as well as for the implementation of radiation protection for continuing operations. Because of their rapidly growing importance, the problems of installation and radiation safety of standard medical and industrial accelerators are discussed in separate sections. Special discussions are devoted to the radiation protection problems unique to electron accelerators: thick-target bremsstrahlung, the electromagnetic cascade, the estimation of secondary-radiation yields from thick targets, and instrumental corrections for accelerator duty factor. In addition, an extensive review of neutron production is given which includes new calculations of neutron production in various materials. A recalculation of activation in a variety of materials has been done for this manual, and specific gamma-ray constants have been recalculated for a number of nuclides to take into account the contribution of K X-rays. The subjects of air and water activation, as well as toxic gas production in air have been specially reviewed. Betatrons and electron microtrons operating at the same energy produce essentially the same kind of secondary radiation as electron linacs and the material given in this manual is directly applicable to them

  5. 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

  6. 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)

  7. Radiology

    International Nuclear Information System (INIS)

    Lissner, J.

    1985-01-01

    Diagnostic radiology is still the foremost of all innovative medical disciplines. This has many advantages but also some handicaps, e.g. the siting problem of medical equipment whose clinical potential is not fully known. This applies in particular to nuclear spin tomography, where the Laender governments and the Scientific Council seen to agree that all universities should have the appropriate equipment as soon as possible in order to intensify interdisciplinary research. Formerly, in the case of computerized tomography, there was less readiness. As a result, the siting of CT equipment is less organically structured. A special handicap of innovative fields is the problem of training and advanced training. The Chamber of Medicine and the Association of Doctors Participating in the Health Insurance Plan have issued regulations aimed at a better standardisation in this field. (orig.) [de

  8. 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.

  9. 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.

  10. 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

  11. 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)

  12. Radiological safety programme for the health departments in Parana, Brazil

    International Nuclear Information System (INIS)

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

    1998-01-01

    As a result of Brazil's centralized administration in the past, various parts of the public service were somewhat inefficient. Another reason was the size of the country. To improve the situation in the health sector, it was decided to transfer administrative responsibility to the municipal authorities. Accordingly, the public health system is now defined under the appropriate legislation as the 'Unified Health System' (SUS), comprising federal, state and municipal levels. This system promotes decentralization of therapeutic or preventive services (including the Radiation Facility Health Inspectorate) and proposes any additional legislation required. In Parana the Radiation Facility Health Inspectorate has 3600 organizations listed, employing ionizing radiation in medicine, industry and research, which need to be regularly inspected for licensing and control. In 1994, 50% of the annual inspection target in the state was attained. The Radiation Safety Programme for the Health Departments in Parana directs these activities in this State. Its strategies are: (1) to establish implementation phases for activities planned for each area; (2) to take advantage of the SUS structure to introduce or expand operational services at the primary, secondary and tertiary levels with appropriate equipment. The tertiary level involves co-ordination of the Programme and complementary executive functions, as well as maintaining an information system with other related organizations. The other levels include licensing, control and emergency response. As the Programme develops, indicators will be established to help identify progress achieved and correct operating strategy where necessary. Thus, the services provided to the public will be enhanced in quality and the radiation doses reduced. In addition, in emergency situations, the time elapsing between the event and its notification to the authorities will be reduced, minimizing the consequences of any accidents. (author)

  13. Radiological safety assessment of gas mantle industries in India

    International Nuclear Information System (INIS)

    Sadagopan, G.; Venkataraman, G.

    1994-01-01

    Thorium, a radioactive element of actinide family was discovered by Berzelius in 1828 and named by him in honor of the Scandinavian God open-quote Thor close-quote. Following its discovery the earliest known use of thorium was in the making of gas mantles. The other use as an X-ray contrast medium open-quote Thorotrast close-quote has since long been discontinued, where as even today its use in gas mantles is continued. Gas lights have been used as a source of light since 1800's. In India, although electric bulbs have replaced most of the gas lights, even today in villages and in urban areas where there is no continuous power supply and in outdoor lightings gas lamps are used. The mantle which is used in these lamps is called the Welsbach mantle and is a netted hose that is impregnated with thorium nitrate and other metals. The function of a gas mantle is to produce a bright light during operation of the lighting device (gas or kerosene lamp) in which the mantle is placed. When placed in a lighting device and heated to 1300-1800 degree Celcius thorium in the mantle incandesces and gives off bright light. In India presently there are about 70 manufacturing units handling 150 metric tons of thorium nitrate annually. There are about four hundred persons involved in manufacturing 200 million mantles per year. Thorium is chosen because of its property of incadescence, however since it is radioactive, radiation safety of the workplace, handling personnel and safe environmental condition for members of public have to be maintained

  14. 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.

  15. 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

  16. 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)

  17. 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

  18. 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.

  19. 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

  20. 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.

  1. Dosskin code for radiological evaluation of skin radioactive contaminations

    International Nuclear Information System (INIS)

    Cornejo D, N.

    1996-01-01

    The conceptual procedure and computational features of the DOSSKIN code are shown. This code calculates, in a very interactive way, skin equivalent doses and radiological risk related to skin radioactive contaminations. The evaluation takes into account the contributions of contaminant daughter nuclides and backscattering of beta particles in any skin cover. DOSSKIN also allows to estimate the maximum time needed to decontaminate the affected zone, using, as input quantity, the limit value of skin equivalent dose considered by users. The comparison of the results obtained by the DOSSKIN code with those reported by different authors are showed. The differences of results are less than 30%. (authors). 4 refs., 3 fig., 1 tab

  2. 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.

  3. 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

  4. 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.

  5. Quality of life evaluation of workers for diagnostic radiology services

    International Nuclear Information System (INIS)

    Fernandes, Ivani Martins

    2011-01-01

    The main objective of this study was to evaluate the quality of life (QOL) of diagnostic radiology services workers at a hospital of Sao Paulo city. It aimed also to draw the profile of these workers identifying the variables, as its influence on their quality of life. A descriptive exploratory study with qualitative and quantitative approaches was carried out. The data were collected using the questionnaires: the abbreviated instrument for the assessment of the QOL, World Health Organization Quality of Life Instrument bref (WHOQOL-bref) and a questionnaire including the social demographic variables, work conditions and the variables that express the lifestyle of individuals, both questionnaires self-applied. The sample was formed by 118 workers, among them: physicians, technologists/technicians in radiology, nurses, technicians and assistants in nursing, and others health professionals. The data analysis included descriptive statistics, nonparametric tests and the use of a linear regression model. The reliability of the instrument for the studied sample was verified by Cronbach's Alpha Coefficient (α). The WHOQOL-bref proved to be an adequate instrument, with a good level of internal consistency (α=0.884), being easily and quickly administrated for the evaluation of the QOL. The study provided an overview of the perception of quality of life of the studied group. (author)

  6. 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

  7. 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.

  8. 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)

  9. Radiologic evaluation of the globus symptom using videotape recorder

    International Nuclear Information System (INIS)

    Kim, Myeong Jin; Chung, Tae Sub; Lee, Jong Tae; Yoo, Hyung Sik; Suh, Jung Ho; Chang, Tae Young; Park, In Yong

    1988-01-01

    The authors examined barium swallow in 213 patients with globus symptom and 79 patients with vague gastric problems without globus symptom. Abnormal findings were more frequently detected on videorecording than on conventional esophagogram. Radiologic findings were transient cricopharyngeal indentation (CPI), residual barium collection and delayed clearing from hypopharynx (RB), laryngeal penetration of barium, barium retention in vallecula and or pyriform sinuses. Among them residual barium in hypopharynx was more frequently detected in patients with globus symptom than in patients without globus symptom. Globus symptom was more frequent in adult women, but age and sex difference did not affect the incidence of the abnormal radiologic findings. Cricopharyngeal indentation was most frequently seen at the level of C5-6 interspace and had a tendency of moving upward gradually during the indentation in about half of the cases. Most of the CPI was seen in early phase of swallowing and was visible within 1 sec. Residual barium collection was mostly seen in C6 or C6-7 level. RB had no cause and effect relationship with CPI, and it was not secondary result of obstructive effect of CPI. The authors think that videotape recording can be a useful method for evaluation of globus symptom. The residual barium collection in hypopharynx can be a significant finding in globus symptom

  10. Evaluation of a high-level waste radiological maintenance facility

    International Nuclear Information System (INIS)

    Collins, K.J.

    1998-01-01

    The Savannah River Site''s (SRS) Defense Waste Processing Facility (DWPF) near Aiken, SC is the nation''s first and world''s largest high level waste vitrification facility. DWPF began, operations in March 1996 to process radioactive waste, consisting of a matrixed predominantly 137 Cs precipitate and a predominately 90 Sr and alpha emitting sludge, into boro-silicate glass for long term storage. Presently, DWPF is processing only sludge waste and is preparing to process a combination of sludge and precipitate waste. During precipitate operations, canister dose rates are expected to exceed 10 Sv hr -1 (1000 rem hr -1 ). In sludge-only operations, canister contact gamma dose rates are approximately 15 mSv hr -1 (1500 mrem hr -1 ). Transferable contamination levels have been greater than 10 mSv hr -1 (100 cm 2 ) -1 for beta-gamma emitters and into the millions of Bq (100 cm 2 ) -1 for the alpha emitting radionuclides. This paper presents an evaluation of the radiological maintenance areas and their ability to support radiological work

  11. Evaluation of the field size in dental diagnostic radiology system

    International Nuclear Information System (INIS)

    Andrade, P.S.; Potiens, M.P.A.

    2006-01-01

    In this work the field size of a dental X rays machine was evaluated considering the recommendation of the Brazilian Health Ministry Regulation 453 which established basic lines of radiological protection in medical and dental diagnostic radiology. The diameter of the field should not be superior to 6 cm in the localized end point, limiting the radiated area and protecting the head-neck region. The measurements were carried out in a dental X rays machine, Dabi Atlante, model Spectro 70X Seletronic. For the field size or useful beam determination, the intra-oral films were positioned on a plain surface to be exposed in four stages and two focus-film distances (FFD), 20 cm and 27.5 cm: 1) with spacer cone; 2) without spacer cone; 3) with spacer cone and film-holding device; 4) without spacer cone and film-holding device. The results show that the diameter of the field size is satisfactory only for FFD = 20 cm. When the film-holding device is used, which is recommended by the Regulation 453, item 5.8 d(ii), the diameter of the field size exceeds the maximum recommended value of 6 cm. (authors)

  12. Evaluations of gonad and fetal doses for diagnostic radiology.

    Science.gov (United States)

    Tung, C J; Tsai, H Y

    1999-07-01

    A national survey of patient doses for diagnostic radiology was planned in the Republic of China. We performed a pilot study for this survey to develop a protocol of the dose assessments. Entrance skin doses and organ (including ovary, testicle and uterus) doses were measured by thermoluminescent dosimeters and calculated by means of Monte Carlo simulations for several diagnostic procedures. We derived a formula and used the RadComp software for the computation of entrance skin doses. This formula involves several factors, such as kVp, mAs, the focus-to-skin-distance and aluminum filtration. RadComp software was applied to obtain free-air entrance exposures which were converted to entrance skin doses by considering the backscattering radiation from the body. Organ doses were measured using a RANDO phantom and calculated using a mathematical phantom for several diagnostic examinations. Genetically significant doses were calculated from ovary and testicle doses for the evaluation of hereditary effects. Embryo/fetal doses were determined from the uterine doses by considering the increase in uterus size with gestational age. We found that the patient doses studied in this work were all below the reference doses recommended by the National Radiological Protection Board of the U.K.

  13. Radiologic evaluation of adriamycin induced toxic cardiomyopathy in childhood leukemia

    International Nuclear Information System (INIS)

    Kim, Young Joo; Moon, Young Hee; Kang, Kyung Jin; Kim, Ok Hwa; Kim, Choon Yul; Bahk, Yong Whee

    1992-01-01

    The cardiomyopathy associated with Adriamycin is frequently fatal and full clinical recovery is uncommon. To evaluate the radiological manifestation and the outcome of Adriamycin induced cardiac toxicity, we retrospectively reviewed the serial chest X-ray films of children treated with Adriamycin. Among 154 children with leukemia, fourteen patients developed clinical and radiologic evidence of congestive heart failure (CHF). Six out of 14 (43%) died of CHF within 2 weeks after attack and eight children survived after their acute episodes of CHF, were controlled following digoxin and diuretic therapy. Despite the improving clinical evidence of heart failure, the follow-up chest roentgenograms of these 8 children showed definite cardiomegaly as compared with the pre-treatment chest X-ray. Three children among 8 had minimal cardiomegaly and the remaining five children showed persistent, marked cardiomegaly during the period of 9-25 months of follow up. In summary, when CHF develops during chemotherapy in leukemic children, the possibility of Adriamycin induced cardiac toxicity should be suspected. Our findings showed that persistence of cardiomegaly represented significant cardiomyopathy despite clinical improvement of CHF

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

    International Nuclear Information System (INIS)

    Titik Kartika; Ishak

    2013-01-01

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

  15. 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)

  16. RADIOLOGICAL AND PATHOLOGICAL EVALUATION OF TRICHILEMMAL CYSTS OF THE SCALP

    Directory of Open Access Journals (Sweden)

    Deb Kumar Boruah

    2017-09-01

    Full Text Available BACKGROUND Trichilemmal cysts or pilar tumours are slow growing scalp lesion commonly found in elderly women. These slow growing lesions may cause morbidity and even mortality. Recurrence of the lesions after local excision is common. These trichilemmal cyst usually indolent with benign nature or may transform to proliferating trichilemmal cyst or Proliferating Pilar Tumour (PPT or may show malignant transformation. The aim of the study is to study the radiological and pathological evaluation of trichilemmal cysts of scalp. MATERIALS AND METHODS A hospital-based cross-sectional retrospective study was conducted. The study group comprised of 20 patients presenting to the Departments of Radiodiagnosis, Radiotherapy, General Surgery, Plastic Surgery and Dermatology in a tertiary care hospital from July 2015 to August 2017. All patients were initially evaluated clinically followed by cross-sectional imaging modality like Computed Tomography (CT or Magnetic Resonance Imaging (MRI. RESULTS In 20 patients, a total of 51 trichilemmal cysts were evaluated where 46 (90.2% were benign trichilemmal cysts and 5 (9.8% showed malignant transformation. The mean age of presentation was 47.9 yrs. ± 1.5 (SD with male:female ratio of 1:3.The mean duration of presence of trichilemmal cyst was 5.9 yrs. ± 3.2 (SD. Out of 5 malignant trichilemmal cysts 3 patients (15% showed bony calvarial erosion and 2 patients (10% showed intracranial extensions. Statistical significance with ‘p’ value of 0.003 was noted between the size of largest dimension of trichilemmal cyst and their histopathology without any statistical significance between duration of swelling and their histopathology. CONCLUSION Even though, the trichilemmal cysts of scalp are denoted as benign lesion, as they usually shows recurrence and its affinity to become locally aggressive and turn into malignancy is there. Hence, clinical, radiological and pathological correlation isnecessary to decreased

  17. 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

  18. 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

  19. 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.

  20. 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)

  1. 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.

  2. 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.

  3. 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)

  4. 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).

  5. Radiologic evaluation of the maxillary natural pathologic conditions in children

    International Nuclear Information System (INIS)

    Prk, Tae Won; Choi, Soon Chul

    1992-01-01

    The authors evaluated the distribution of the antral pathologic conditions and their radiographic features on the Waters' radiographs of 151 children patients who had been radiographed at the department of Oral Radiology, Seoul National University Hospitals. The obtained results were as follows : 1. The most common pathologic condition was inflammatory change (58%). Percentage of cases showing cystic lesion and fibro-osseous lesion were 25% and 11% respectively. 2. In cases of inflammatory change, odontogenic origins were 12 cases (13%) and bilateral occurrences were 37 cases (39%). 3. The most common radiographic feature of the inflammatory conditions was various types of mucosal thickening (78%). Percentage of cases showing totally increased radiopacity was 18%. 4. Intrinsic cystic lesions were 26 cases (65%) and dentigerous cyst was the most common extrinsic cyst. 5. Most of the fibro-osseous lesions (15 from 17 cases) were fobrous dysplasea. 6. Maxillary sinus hypoplasia (5 cases) and Burkitt's lymphoma (4 cases) were also observed.

  6. Radiologic evaluation of the maxillary natural pathologic conditions in children

    Energy Technology Data Exchange (ETDEWEB)

    Prk, Tae Won; Choi, Soon Chul [Dept. of Oral Radiology, College of Dentistry, Seoul National University, Seoul (Korea, Republic of)

    1992-08-15

    The authors evaluated the distribution of the antral pathologic conditions and their radiographic features on the Waters' radiographs of 151 children patients who had been radiographed at the department of Oral Radiology, Seoul National University Hospitals. The obtained results were as follows : 1. The most common pathologic condition was inflammatory change (58%). Percentage of cases showing cystic lesion and fibro-osseous lesion were 25% and 11% respectively. 2. In cases of inflammatory change, odontogenic origins were 12 cases (13%) and bilateral occurrences were 37 cases (39%). 3. The most common radiographic feature of the inflammatory conditions was various types of mucosal thickening (78%). Percentage of cases showing totally increased radiopacity was 18%. 4. Intrinsic cystic lesions were 26 cases (65%) and dentigerous cyst was the most common extrinsic cyst. 5. Most of the fibro-osseous lesions (15 from 17 cases) were fobrous dysplasea. 6. Maxillary sinus hypoplasia (5 cases) and Burkitt's lymphoma (4 cases) were also observed.

  7. 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 .

  8. Evaluation of radiological teaching programs in the Internet

    International Nuclear Information System (INIS)

    Seitz, J.; Schubert, S.; Voelk, M.; Scheibl, K.; Paetzel, C.; Schreyer, A.; Djavidani, B.; Feuerbach, S.; Strotzer, M.

    2003-01-01

    Evaluation of web based training programs,which can be contacted from the homepages of radiological departments of German universities.Material and method From june 2000 to january 2002 the 75 web based training programs of 57 providers,which can be contacted from the web pages of the radiological departments of german universities were evaluated in a prospective study.A medical student experienced in using the world wide web examined each training program three times in an interval of six months using the following criteria: availability of the web sites,target group,kind of training program,contents and structure and the technical solution. 51 of the 57 the homepages were fully available at each visit. 64 of the 75 web based training programs which could be connected from these sites were available at all three visitis.One program was only partially available at one spot check. 8 of the 75 programs were designed for physicians and medically trained personal, 23 were made for medical students and 44 addressed both target groups (partially more than once mentioned).The number of the presented cases ranged between one single and 3700. In 31 of 75 training programs links to other teaching files were found.A complete presentation of cases was presented by 48 of the 75 web sites.5 of the 75 web sites offered physiological images for comparison. In 20 training programs the pathological changes were optically marked in the x-ray images.A logical and didactical structure was found in 24 teaching files, 14 gave the possibility to check the learning results.No provider made use of the possibility to pass credits to the students or physicians acount with regard to official training programs. Multimedia techniques were used in 15 training programs.43 sites used data reduced preview images (thumbnails).The latest update of the site is mentioned in 55 of the 75 web sites. 19 of 57 providers had either no possibility of contact or did not answer to an e-mail. From the homepages

  9. An attempt to evaluate the risks associated with radiological terror

    International Nuclear Information System (INIS)

    Paschoa, A.S.; Dantas, B.M.

    2014-01-01

    The evaluation of the risk of a terrorist attack has been made frequently by multiplying the probability of occurrence of a terrorist attempt by the probability of its success and a quantity which represents the consequences of a successful attack. In the case of a radiological attack the consequences will vary in case the action will be active or passive. Thirteen radionuclides were examined for their potential uses in credible threats or terrorist attacks based on their availability from laboratories and hospitals. Taking into account the dose conversion coefficients published by the International Atomic Energy Agency, those radionuclides with higher dose effectiveness for ingestion are the following: 210 Po; 226 Ra and 241 Am. Other radionuclides which can be used in threats and terror attacks, like 137 Cs for example have also been examined. The risks associated with the selected radionuclides have been tentatively ranked as high, medium, or low. The probability used to evaluate risks depends on the motivation of the terrorist and the capacity, which implies availability or the actual possibility of obtaining a particular radionuclide. On the other hand, whenever a list of radionuclides to be used in a malevolent action is available to a terrorist, the choice of the most adequate will depend also on the action to be undertaken. This work ranks risks associated with radiological terror based on physical, chemical, radio-toxicological and other relevant data on radionuclides, which were either already used in terror attacks, or were pointed out as adequate to be used in such malevolent actions. (author)

  10. 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)

  11. 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)

  12. 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)

  13. 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.

  14. 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)

  15. 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)

  16. Evaluating safety management system implementation

    International Nuclear Information System (INIS)

    Preuss, M.

    2009-01-01

    Canada is committed to not only maintaining, but also improving upon our record of having one of the safest aviation systems in the world. The development, implementation and maintenance of safety management systems is a significant step towards improving safety performance. Canada is considered a world leader in this area and we are fully engaged in implementation. By integrating risk management systems and business practices, the aviation industry stands to gain better safety performance with less regulatory intervention. These are important steps towards improving safety and enhancing the public's confidence in the safety of Canada's aviation system. (author)

  17. Radiologic evaluation of intestinal obstruction in the neonates

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jin Hee; Kim, Dong Woo; Lee, Eun Suk; Kwon, Sun Young [Eul Ji General Hospital, Daejeon (Korea, Republic of); Lee, Sang Young [Chonbuk National University College of Medicine, Jeonju (Korea, Republic of); Kang, Hye Jeong [Eul Ji General Hospital, Seoul (Korea, Republic of)

    1995-10-15

    The purpose of this study is to evaluate the radiologic findings of the intestinal obstruction in the neonate according to the causes and to determine the findings useful for the differential diagnosis. The materials consisted of 29 neonates with surgically proven gastrointestinal tract obstruction. We analyzed simple abdominal radiography and barium study comparing with the operative findings. The causes of intestinal obstruction were gastric atresia in 1 case, duodenal atresia in 3 cases, small bowel atresia in 11 cases (jejunal; 3 cases, ileal; 8 cases), colonic atresia in 2 cases, Hirschsprung's disease in 9 cases, ano-rectal anomaly in 6 cases, midgut volvulus in 2 cases, and Meckel's diverticulum in 1 case. Vomiting was noted in the all cases. The abdominal distension was not noted in the cases of gastric atresia, duodenal atresia, and proximal jejunal atresia. The meconium passage was noted in 2 cases of ileal atresia and 3 cases of Hirschsprung's disease. On barium study, site of obstruction was predicted accurately in gastric atresia, duodenal atresia, proximal jejunal atresia, and colonic atresia but it was not possible in distal jejunal atresia and ileal atresia. The microcolon was noted in 2 cases of jejunal atresia, 4 cases of ileal atresia, and 2 cases of colonic atresia. Out of 9 Hirschsprung's disease transition zones were seen on rectum or rectosigmoid junction in 7 cases and barium study was normal in 2 cases. In the diagnosis of neonatal intestinal obstruction, the basic radiologic studies such as simple abdominal radiography and gastrointestinal contrast study was useful for the differential diagnosis of the proximal bowel loop atresia colonic atresia, and midgut volvulus.

  18. Radiologic evaluation of intestinal obstruction in the neonates

    International Nuclear Information System (INIS)

    Kim, Jin Hee; Kim, Dong Woo; Lee, Eun Suk; Kwon, Sun Young; Lee, Sang Young; Kang, Hye Jeong

    1995-01-01

    The purpose of this study is to evaluate the radiologic findings of the intestinal obstruction in the neonate according to the causes and to determine the findings useful for the differential diagnosis. The materials consisted of 29 neonates with surgically proven gastrointestinal tract obstruction. We analyzed simple abdominal radiography and barium study comparing with the operative findings. The causes of intestinal obstruction were gastric atresia in 1 case, duodenal atresia in 3 cases, small bowel atresia in 11 cases (jejunal; 3 cases, ileal; 8 cases), colonic atresia in 2 cases, Hirschsprung's disease in 9 cases, ano-rectal anomaly in 6 cases, midgut volvulus in 2 cases, and Meckel's diverticulum in 1 case. Vomiting was noted in the all cases. The abdominal distension was not noted in the cases of gastric atresia, duodenal atresia, and proximal jejunal atresia. The meconium passage was noted in 2 cases of ileal atresia and 3 cases of Hirschsprung's disease. On barium study, site of obstruction was predicted accurately in gastric atresia, duodenal atresia, proximal jejunal atresia, and colonic atresia but it was not possible in distal jejunal atresia and ileal atresia. The microcolon was noted in 2 cases of jejunal atresia, 4 cases of ileal atresia, and 2 cases of colonic atresia. Out of 9 Hirschsprung's disease transition zones were seen on rectum or rectosigmoid junction in 7 cases and barium study was normal in 2 cases. In the diagnosis of neonatal intestinal obstruction, the basic radiologic studies such as simple abdominal radiography and gastrointestinal contrast study was useful for the differential diagnosis of the proximal bowel loop atresia colonic atresia, and midgut volvulus

  19. Safety evaluation of advance street name signs

    Science.gov (United States)

    2009-06-01

    The Federal Highway Administration (FHWA) organized a pooled fund study of 26 States to evaluate low-cost safety strategies as part of its strategic highway safety effort. The objective of the pooled fund study was to estimate the safety effectivenes...

  20. 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)

  1. 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)

  2. 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

  3. Status of Nuclear Safety evaluation in China

    International Nuclear Information System (INIS)

    Tian Jiashu

    1999-01-01

    Chinese nuclear safety management and control follows international practice, the regulations are mainly from IAEA with the Chinese condition. The regulatory body is National Nuclear Safety Administration (NNSA). The nuclear safety management, surveillance, safety review and evaluation are guided by NNSA with technical support by several units. Beijing Review Center of Nuclear Safety is one of these units, which was founded in 1987 within Beijing Institute of nuclear Engineering (BINE), co-directed by NNSA and BINE, it is the first technical support team to NNSA. Most of the safety reviews and evaluations of Chinese nuclear installations has been finished by this unit. It is described briefly in this paper that the NNSA's main function and organization, regulations on the nuclear safety, procedure of application and issuing of license, the main activities performed by Beijing Review Center of Nuclear Safety, the situation of severe accident analyses in China, etc. (author)

  4. 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.

  5. 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)

  6. Common carotid artery thrombosis; Clinical and radiological evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Ito, Yasuhiro; Yasuda, Takeshi; Hakusui, Shigetaka; Yanagi, Tsutomu (Nagoya Daini Red Cross Hospital (Japan)); Ito, Eiichi

    1994-02-01

    Common carotid artery thrombosis (CCAT) is not common. We studied 4 patients with CCAT to clarify the clinical and radiological features of this disorder. Case 1 had only episodes of TIA. Case 2 was diagnosed by chance as having CCAT at the time of admission due to cerebellar infarction. On the contrary, Cases 3 and 4 were admitted because of disturbance of consciousness and hemiparesis. Case 4 died soon after his stroke because of complications. We evaluated cases 1, 2 and 3 using head CT, head MRI, neck MRI, MR angiography, SPECT and cerebral angiography. Case 4, who was evaluated with head CT and cerebral angiography, was autopsied to confirm the occlusion of the common carotid artery. The clinical severity of CCAT varies from asymptomatic to severe, because each case differs in the time taken for complete occlusion of the common carotid artery; the development of collateral circulation; and hemodynamics of the brain. As for the collaterals their contribution is variable; for example, the thyrocervical and other arteries function as the bypass. We can diagnose CCAT easily and noninvasively using MR angiography and neck MRI based on disappearance of the flow void in the common carotid artery or internal carotid artery. On physical examination, it is important to detect faded pulsation of the superficial temporal artery that is ipsilateral to the occluded common carotid artery. (author).

  7. RADIOLOGICAL EVALUATION OF OBSTRUCTIVE JAUNDICE BY ULTRASOUND AND CT

    Directory of Open Access Journals (Sweden)

    Padmalatha

    2015-10-01

    Full Text Available INTRODUCTION: The goals of any radiologic procedure in obstructive Jaundice are to confirm the presence of bile duct obstruction, its location, its extent & the probable cause. It should also attempt to obtain a map of the biliary tree that will help the surgeon to det ermine the best approach to each individual case. OBJECTIVES: 1. To evaluate the role of Ultrasound and CT in patients presenting with clinical features of obstructive jaundice. 2. To evaluate the causes of obstructive jaundice by Ultrasound and CT. PATIENTS AND METHODS: The study was carried with 45 patients from January 2006 to September 2007 who were attending the surgical and Gastroenterology Departments, Govt. General Hospital, Kurnool, which is an attached hospital to Kurnool Medical College, Kurnool. O BSERVATIONS AND RESULTS: In our study, there is female predominance with male: female ratio 1: 1.6.Majority of patients are in age group of 41 - 50 years. Jaundice was the commonest presentation in all patients followed by pruritis in 72% and pain abdomen in 67% of patients. Ultrasound identified the benign cause of biliary obstruction in 79.1% cases and the malignant cause in 61.9% cases. CT identified the benign cause of biliary obstruction in 91.6% of patients and the malignant cause in 80.9% cases.

  8. 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

  9. 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

  10. National Institute for Radiological Protection and Nuclear Safety - IRSN. Annual Report 2016, Financial Report 2016

    International Nuclear Information System (INIS)

    2017-01-01

    IRSN is the nation's public service expert in nuclear and radiation risks, and its activities cover all the related scientific and technical issues in France and in the international arena. Its work therefore concerns a wide range of complementary fields, including environmental monitoring, radiological emergency response, radiation protection and human health in normal and accident situations, prevention of major accidents, and safety and security relating to nuclear reactors, plants, laboratories, transportation, and waste. It also carries out assessments in the nuclear defense field. In addition, IRSN contributes to government policy in nuclear safety, the protection of human health and the environment against ionizing radiation, and measures aimed at safeguarding nuclear materials, facilities and transportation operations against the risk of malicious acts. Within this context, it interacts with all the organizations concerned including public authorities, in particular nuclear safety and security authorities, local authorities, businesses, research organizations, and stakeholder associations. This document is IRSN's annual and financial report for 2016. Content: 1 - Activity Key Figures; 2 - Strategy; 3 - Panorama 2016; 4 - Activities: safety (Safety of civil nuclear facilities, Experimental reactors, Nuclear fuel cycle facilities, Human and organizational factors, Reactor aging, Severe accidents, Fuel, Criticality, Fire and containment, Natural hazards, Defense-related facilities and activities, Radioactive waste management, Geological disposal of radioactive waste); security and nonproliferation (Nuclear security, Nuclear nonproliferation, Chemical weapons ban); radiation protection - human and environment health (Environmental monitoring, Radon and polluted sites, Radiation protection in the workplace, Effects of chronic exposure, Protection in health care); emergency and post-accident situations (Emergency preparedness and response, Post

  11. TAPS safety evaluation criteria for reload fueling

    International Nuclear Information System (INIS)

    Mahendra Nath; Veeraraghavan, N.

    1976-01-01

    To improve operating performance of Tarapur reactors, several proposals are under consideration such as core expansion, change-over to an improved fuel design with lower heat rating, extension of fuel cycle lengths etc., which have a bearing on overall plant operating characteristics and reactor safety. For evaluating safety implications of the various proposals, it is necessary to formulate safety evaluation criteria for reload fuelling. Salient features of these criteria are discussed. (author)

  12. Parameters Evaluation of PLC Dependability and Safety

    Directory of Open Access Journals (Sweden)

    Juraj Zdansky

    2006-01-01

    Full Text Available This paper is focused on evaluation of dependability and safety parameters of PLC (Programmable Logic Controller. Achievement of requested level of these parameters is an application assumption for using PLC in control of safety critical processes. Evaluation of these parameters can be made on the base of suitable model and it can be influenced by system architecture when necessary.

  13. Evaluation of Van Lake (Turkey) about radiological and hydrogeological risk

    International Nuclear Information System (INIS)

    Akyil, S.; Aytas, S.; Yusan, S.; Aslani, M. A. A.; Aycan, H. A.; Eral, M.; Tuerkoezue, D. A.; Isik, M. A.; Oelgen, M. K.

    2009-01-01

    Basins which are grow in the continent and not discharge to open sea are named as a close basin. Lead, uranium and thorium are high levels in respect to open basins. Lake of Van is a close basin. In the lake basins, rivers which are discharge basin are the most important source of the heavy metal concentration. In this study, surface water, coast and deep sediments of Van Lake and Inci Kefal (fish) were analyzed as a radiological and evaluated in terms of hydrogeological. Data was obtained for natural radioactivity concentration of this lake and evaluated using geostatistical methods in a geographical information system environment and fitted for isoradioactivity contour maps. The concentration and distribution of natural radionuclides in Van Lake were investigated with the aim of evaluating the environmental radioactivity. Sixty three coastal and deep sediments, 228 lake surface waters and 12 fish samples were taken in Van Lake over the time period 2005-2008 and the distribution pattern of the measured radionuclides was presented. The mean concentrations of gross alpha and beta, eU, eTh and K-40 activities in sediments were 207±96, 1046±60, 207±96, 70±29 and 399±231 Bq/kg, respectively. On the other hand, water samples from Van Lake had mean concentrations of 0.74±0.46 Bq/L for gross alpha activity concentration, 0.02±0.01 Bq/L for gross beta activity concentration, 0.06±0.04 Bq/L for gross radium isotopes, respectively. The mean gross alpha and beta, eU, eTh and K-40 activities in fish samples were 47±18, 470±12, 0.57±0.22, 0.022±0.006, 319±11 Bq/kg, respectively. An average annual effective dose equivalent (mSv/y) was calculated.

  14. 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

  15. 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.

  16. Radiological data acquisition, investigation and evaluation of mining relics

    International Nuclear Information System (INIS)

    1992-01-01

    Within the scope of a Federal Project, the environmental radioactivity and the radon concentration in buildings caused by mining relics in the new Federal Lands of Germany are investigated. In the first phase of the project, about 8000 relics of former mining were identified by analysing existing documents, categorised, and recorded in a special data bank. Thereby, 'areas of suspicion' of 1500 km 2 spaciously defined in the beginning could be reduced to 'areas of investigation' of 250 km 2 now to be examined in close coordination with the land and district authorities by a programme gradually adapted to the radiological significance of the relics. Experience with site-specific measuring programmes have already been gained through three pilot projects at typical sites of former mining activities. Recommendations of the German Radiation Protection Commission serve for the evaluation of the results. By the measuring programme for radon in buildings of mining and geological predestined regions more than 25000 buildings of 210 communities have been investigated. The results confirm the expected prevailing influence of the geologic underground on the radon concentration. Extreme values are observed where direct connections additionally exist to mining relics in the ground. (orig./HP) With 11 figs. in annex [de

  17. Radioisotopic and Radiological Evaluation in Patient with Stress Fracture

    International Nuclear Information System (INIS)

    Ko, Kwang Seop; Kim, Jai Young; Kang, Sung Koo; Kim, So Yon; Lee, Gwon Jun

    1987-01-01

    The stress fracture is a disease caused by and abnormal stress to the normal bone with constant, repeated pull. Early detection of stress fracture plays an important role in treatment and prevention of its complication. Bone scintigraphy was performed to evaluate 18 patients with stress fracture of the lower extremities from May, 1985 to April, 1987, in the Department of Internal Medicine of National Police Hospital. The results were as follows: 1) Seventeen of the 18 cases showed positive bone scans at the initial study performed from 1 week to 5 months after the onset of symptom. 2) Ten of the 18 patients had findings of stress fracture at the initial X-ray film. Two out of 8 negative case revealed positive findings in the follow-up studies. 3) The bone scans in the 2 cases taken 5 months after the onset of symptom; the one showed only slightly increased radio uptake, the other showed no abnormal findings. In conclusion, bone scanning is a more sensitive indicator of early stress fracture than radiologic study, The healing phase is characterized by a gradual decline in radioactivity at the fracture site in concordance with subsidence of symptom.

  18. Radiological evaluation of the chronic venous stasis syndrome

    International Nuclear Information System (INIS)

    Train, J.S.; Schanzer, H.; Peirce, E.C. II; Dan, S.J.; Mitty, H.A.

    1987-01-01

    Chronic venous stasis is an extremely complex clinical syndrome of pain and changes in the skin that can involve the superficial, deep, and perforating veins. This syndrome is commonly referred to as the postphlebitic syndrome, implying that thrombophlebitis is its sole etiology. To test this hypothesis, the authors performed ascending venography on 51 limbs of patients with the chromic venous stasis syndrome and demonstrated that 32 had no radiological evidence of recent or old thrombophlebitis. Instead, they had normal-appearing veins, suggesting primary incompetence of the deep and/or perforating venous valves rather than thrombophlebitis as the etiology. Since various operations have recently been proposed to correct or bypass malfunctioning valves, precise demonstration of pathological change is required to choose the appropriate procedure and to evaluate results. Descending venograms were combined with the ascending studies in 42 limbs for this purpose. In addition to outlining the abnormalities responsible for chronic venous stasis syndrome in individual cases, interesting conclusions regarding the syndrome itself were reached

  19. Preliminary radiological safety assessment for decommissioning of thoria dissolver of the 233U pilot plant, Trombay

    International Nuclear Information System (INIS)

    Priya, S.; Srinivasan, P.; Gopalakrishnan, R. K.

    2012-01-01

    The thoria dissolver, used for separation of 233 U from reactor-irradiated thorium metal and thorium oxide rods, is no longer operational. It was decided to carry out assessment of the radiological status of the dissolver cell for planning of the future decommissioning/dismantling operations. The dissolver interiors are expected to be contaminated with the dissolution remains of irradiated thorium oxide rods in addition to some of the partially dissolved thoria pellets. Hence, 220 Rn, a daughter product of 228 Th is of major radiological concern. Airborne activity of thoron daughters 212 Pb (Th-B) and 212 Bi (Th-C) was estimated by air sampling followed by high-resolution gamma spectrometry of filter papers. By measuring the full-energy peaks counts in the energy windows of 212 Pb, 212 Bi and 208 Tl, concentrations of thoron progeny in the sampled air were estimated by applying the respective intrinsic peak efficiency factors and suitable correction factors for the equilibration effects of 212 Pb and 212 Bi in the filter paper during the delay between sampling and counting. Then the thoron working level (TWL) was evaluated using the International Commission on Radiological Protection (ICRP) methodology. Finally, the potential effective dose to the workers, due to inhalation of thoron and its progeny during dismantling operations was assessed by using dose conversion factors recommended by ICRP. Analysis of filter papers showed a maximum airborne thoron progeny concentration of 30 TWLs inside the dissolver. (authors)

  20. 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.)

  1. 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

  2. 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)

  3. 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.)

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

    International Nuclear Information System (INIS)

    Palsson, S.E.

    2002-11-01

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

  5. Operation Aqueduct: Onsite radiological safety report for announced nuclear tests, October 1989--September 1990

    International Nuclear Information System (INIS)

    Hernandez, G.M.; Jacklin, A.K.

    1992-01-01

    Aqueduct was the name assigned to the series of underground nuclear weapons tests conducted at the Nevada Test Site (NTS) from October 1, 1989, through September 30, 1990. This report includes those experiments publicly announced. Remote radiation measurements were taken during and after each nuclear event by a telemetry system. Reynolds Electrical ampersand Engineering Co., Inc. (REECO) Health Protection Department (HPD) Radiation Protection Technicians (RPTS) with portable radiation detection instruments surveyed reentry routes into ground zeros (GZ) 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 (IH) 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

  6. Operation Grenadier. Onsite radiological safety report for announced nuclear tests, October 1984-September 1985

    International Nuclear Information System (INIS)

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

    1986-09-01

    Grenadier was the name assigned to the series of underground nuclear experiments conducted at the Nevada Test Site from October 1, 1984 through September 30, 1985. This report includes those experiments publicly announced. 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

  7. Operation fusileer onsite radiological safety report for announced nuclear tests, October 1983-September 1984

    International Nuclear Information System (INIS)

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

    1985-08-01

    Fusileer was the name assigned to the series of underground nuclear experiments conducted at the Nevada Test Site from October 1, 1983 through September 30, 1984. This report is limited to announced nuclear tests. 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

  8. Evaluation of radiological doses to the terrestrial plants around Trombay

    International Nuclear Information System (INIS)

    Ajay Kumar; Singhal, R.K.; Preetha, J.; Joshi, S.N.; Hegde, A.G.

    2005-01-01

    Existing policies for radiation protection do not provide explicit criteria for the protection of species other than humans, i.e. not for flora and fauna. Concern over this omission is now being widely expressed and moves are under way to evaluate the doses to terrestrial and aquatic biota. During the present work radiological doses (external and internal) to the terrestrial plants were evaluated by estimating the concentration of anthropogenic ( 137 Cs, 90 Sr) and natural radionuclides ( 238 U, 232 Th and 40 K) in the plant leaves and by measuring the external gamma radiation due to different radionuclide. The soil and vegetation sample were collected from fifteen sampling locations around the different locations at Trombay. The samples were processed as per IAEA (International Atomic Energy Agency) protocol for the estimation of naturally occurring and anthropogenic radionuclides in soil and terrestrial plants. The gamma emitting radionuclides were measured by high resolution gamma (HPGe) spectrometry system. Maximum exposure (external + internal) to the terrestrial plants was observed due to 232 Th while 238 U showed minimum exposure. The average value of radiation exposure to the terrestrial plants for 40 K, 137 Cs, 90 Sr, 238 U and 232 Th was 1555.2 ± 92.4, 691.2 ± 54.3, 2564.1 ± 534.9, 82.5 ±5.2, and 4419.6 ± 1165.5 μGy/y respectively. The radiation exposure (external + internal ) to the terrestrial plants due to all radionuclides was found within the permissible limits (i.e. 10 mGy/d) as per recommended by the United States, Department of Energy (DOE). (author)

  9. 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)

  10. 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)

  11. 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)

  12. Drug safety evaluation of defibrotide.

    Science.gov (United States)

    Richardson, Paul G; Corbacioglu, Selim; Ho, Vincent Trien-Vinh; Kernan, Nancy A; Lehmann, Leslie; Maguire, Craig; Maglio, Michelle; Hoyle, Margaret; Sardella, Marco; Giralt, Sergio; Holler, Ernst; Carreras, Enric; Niederwieser, Dietger; Soiffer, Robert

    2013-01-01

    Hepatic veno-occlusive disease (VOD), also known as sinusoidal obstruction syndrome (SOS), is a potentially life-threatening complication of chemotherapeutic conditioning used in preparation for hematopoietic stem-cell transplantation (SCT). Defibrotide (DF) has been shown in Phase II and III trials to improve complete response in patients with severe VOD (sVOD). None of the articles, to date, provide a comprehensive review of the safety of DF in VOD and/or a range of other conditions. This article reviews current clinical findings on DF, primarily in terms of safety for use in treatment and prophylaxis of VOD, and relevant safety data for its use in other diseases. The literature review was conducted using a PubMed search with the fixed term 'defibrotide' in combination with ≥ 1 of 'safety', 'veno-occlusive disease' (with and without 'treatment', 'prevention'), 'oncology', 'myeloma', 'microangiopathy', 'anti-thrombotic' and 'peripheral vascular disorder'. Related articles from the EBMT and ASH conference websites were also included. DF was well tolerated in majority of the studies. The safety profile of DF is largely favourable with toxicities comparable to control populations in the setting of SCT complicated by sVOD.

  13. 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

  14. 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)

  15. Non-retrieval of inferior vena cava filters as a patient safety concern: evaluation of a new process improvement project to increase retrieval rates in a vascular and interventional radiology clinic.

    Science.gov (United States)

    Brown, Joshua; Talbert, Jeffery; Pennington, Ryan; Han, Qiong; Raissi, Driss

    2018-01-01

    Retrieval of inferior vena cava filters (IVCFs) is important to decrease the long-term risk of complications associated with indwelling devices. Our hospital experienced low retrieval rates and implemented a low-cost intervention and evaluation for quality improvement. The working hypothesis was that a simple, mailed letter intervention could increase retrieval rates by increasing patient and primary care provider knowledge of the need for retrieval. For all prospective patients who received a retrievable IVCF during the intervention period from January 1, 2014 to February 29, 2016, patients and their primary care providers were mailed letters encouraging contact with the clinic for evaluation of eligibility for retrieval. The main outcome was retrieval of the IVCF if clinically indicated with a secondary outcome of time-to-retrieval. A pre-intervention control group from October 1, 2011 to December 31, 2013 was used to evaluate the impact of the intervention. Competing risks, time-to-event analysis was used to compare the pre- and post-intervention period retrieval rates correcting for patients who died during follow-up. Between the pre- and post-intervention periods, crude retrieval rates increased from 4.4% to 8.1% with a 12-fold change at comparable time points. The time-to-retrieval in the pre-intervention period was a mean (SD) of 503 (207) days with a median (IQR) of 505 (301-742). In the post-intervention period, time-to-retrieval was a mean (SD) of 119 (83) days and with median (IQR) of 128 (38-164) days. This low-cost intervention significantly increased retrieval rates in a single clinic. However, retrieval rates remain low and can be further improved. Ongoing interventions, including improved patient follow-up and physician education, are being implemented to further improve retrieval and use of inferior vena cava filters. Implanting clinics should implement quality improvement initiatives to improve patient care and follow-up with IVCFs to ensure

  16. Approach to uncertainty evaluation for safety analysis

    International Nuclear Information System (INIS)

    Ogura, Katsunori

    2005-01-01

    Nuclear power plant safety used to be verified and confirmed through accident simulations using computer codes generally because it is very difficult to perform integrated experiments or tests for the verification and validation of the plant safety due to radioactive consequence, cost, and scaling to the actual plant. Traditionally the plant safety had been secured owing to the sufficient safety margin through the conservative assumptions and models to be applied to those simulations. Meanwhile the best-estimate analysis based on the realistic assumptions and models in support of the accumulated insights could be performed recently, inducing the reduction of safety margin in the analysis results and the increase of necessity to evaluate the reliability or uncertainty of the analysis results. This paper introduces an approach to evaluate the uncertainty of accident simulation and its results. (Note: This research had been done not in the Japan Nuclear Energy Safety Organization but in the Tokyo Institute of Technology.) (author)

  17. 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)

  18. Clinical and Radiological Evaluation of Children with Subacute Sclerosan Panencephalitis

    Directory of Open Access Journals (Sweden)

    Ahmet İrdem

    2004-01-01

    Full Text Available A total of 65 children with Subacute Sclerosing Panencephalitis (SSPE who admittedto our clinic between September 1998 and December 2002 were retrospectively evaluated interms of clinical and radiological findings.The most common symptoms and findings at admission were myoklonia (31 patients, 47%, behaveral changes (18 patients, 27.7 % and convulsion (8 patients, 12 %. There was atrauma history initiating symptoms in 14 patients (21.5 %. Neurological symptoms presentedsignificantly earlier in patients who had measles before 2 years of age compared to others(p0.05. The clinical stage of the patients at admission was determined based on Risk veHaddad classification. The most frequent stage was IIA (21 patients, 32.2%, IIC (17patients, 26.2% and IIB (16 patients, 24.6%. At the follow-up period, 46 (71% patients wasdepended to bed. The mean time interval between SSPE initiation age and bed dependencywas 4.68 ± 4.05 months (1-17 months.Of the 31 patients who underwent cranial magnetic rezonans imaging (MRI, 15patients (48.38% had pathological findings, the most frequent findings were cortical vesubcortical lesions. Of the 24 patients who underwent cranial tomographi, 22 (91.6% werenormal. Of the remaining two, one had atrophy and the other had increase in contrast. All ofthe patients underwent rutine EEG test. Fifty-four (83.1% of these had periodic complexhigh slow wave activity.The clinical findings and Electro Encephalographi results are important parameters inthe diagnosis of SSPE. Cranial tomographi is not useful in the diagnosis of SSPE. However,cranial MRI findings is pathologic only in the half of the patients.

  19. 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

  20. Radiologic evaluation of facial injury; Avaliacao radiologica dos traumatismos faciais

    Energy Technology Data Exchange (ETDEWEB)

    Souza, Ricardo Pires de; Volpato, Richard [Complexo Hospitalar Heliopolis, Sao Paulo, SP (Brazil). Servico de Diagnostico por Imagem]. E-mail: richard_volpato@uol.com.br; Nascimento, Lia Paula [Complexo Hospitalar Heliopolis, Sao Paulo, SP (Brazil)

    2003-03-01

    A detailed radiological investigation of the maxillofacial injuries is essential to achieve good treatment results. The images should identify every lesion and guide the treatment, thus improving esthetic and functional results. With the aim of simplifying the diagnostic task, the face may be seen as a five regions structure that may suffer a regional fracture or combined fractures involving the adjacent regions. These regions represent areas of focus for pre surgical planning and are as follows: nasal, orbital, zygomatic, maxillary, and mandibular. In order to understand the injury mechanisms and their consequences it is useful to know the supporting buttresses, which are divided in five sagittal planes, three horizontal planes and two coronal planes. We reviewed the cases of patients with facial trauma treated at Complexo Hospitalar Heliopolis, Sao Paulo, Brazil. A review of the relevant issues concerning radiological investigation of these injuries is presented. This study allowed standardization and ordering of the radiological investigation in patients with facial trauma. (author)

  1. 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

  2. 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

  3. 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

  4. 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)

  5. 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.

  6. 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

  7. 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

  8. Radiologic evaluation of coronary artery fistula in adult

    International Nuclear Information System (INIS)

    Je, Eun Kyoung; Kim, Yang Min; Choi, Ik Joon; Kim, Seong Bae; Lee, Jae Young; Han, Sang Wook; Cho, Sung Hwui; Park, Jae Hyung; Choi, Yonug Hi

    1997-01-01

    To evaluate the clinical and radiologic findings of coronary artery fistula (CAF) by reviwing adult patients in whom this condition had been diagnosed by coronary angiogram. We retrospectively analysed the clinical findings, chest X-rays and angiographic findings of 37 adult CAF patients treated at three institutes over a period of is 15 years. On coronary angiogram, the origin of CAF was found to be the left coronary artery (LCA) in 20 cases(54%), the right coronary artery (RCA) in five (14%), and both in 12(32%). By subdividing the coronary artery into four segments [RCA, left main coronary artery, left anterior descending artery(LAD), and left circumflex artery(LCX)], the origin of CAF (total 55 cases) was found to be the LAD in 23 cases(42%), the LCX in 12(22%), the left main coronary artery in three (5%), and the RCA in 17(31%). The draining site of CAF was the right heart [right atrium, right ventricle, and main pulmonary artery(MPA)] in 28 cases(75%) the left heart(left atrium and left ventricle) in 8(22%), and both in one (3%). The fistula drained to the cardiac chamber in 12 cases (33%), the MPA in 23(62%), and both in 2(5%). Among 55 cases, the total number of fistulas to the MPA was 35, and their origin was the RCA in nine instances (26%), and the left coronary artery in 26(74%). CAF to the MPA was classified into four types:Type I(single, tortuous and not dilated) was seen in six patients (17%), type II(single, tortuous and dilated) in three (9%), type III(multiple and fine plexus) in 21(60%), and type IV(multiple and dilated plexus)in five (14%). Eighteen cases (49%) were associated with the other cardiac disease. In these Korean adults, CAF originated most commonly from the LCA, especially from the LAD segment of this artery, and most frequently drained to the right cardic chamber, especially to the MPA. The morphology of the CAF to the MPA was mostly multiple and fine plexus. We suggest that to ensure the most suitable treatment, and for better

  9. 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)

  10. 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)

  11. 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)

  12. Common Pediatric Urological Disorders: Clinical and radiological evaluation

    OpenAIRE

    Robson, Wm. Lane M.; Leung, Alexander K.C.; Boag, Graham S.

    1991-01-01

    The clinical and radiological presentations of 12 pediatric urological disorders are described. The described disorders include pyelonephritis, vesicoureteral reflux, ureteropelvic obstruction, ureterovesical obstruction, ectopic ureterocele, posterior urethral valves, multicystic dysplastic kidney, polycystic kidney disease, ectopic kidney, staghorn calculi, urethral diverticulum, and urethral meatal stenosis.

  13. Radiological Evaluation of phosphate fertilizers used in Tunisia

    International Nuclear Information System (INIS)

    Jemli, Khaoula

    2010-01-01

    The need of control of natural radioactivity in the environment and the radiological impact of the use of chemical fertilizers has led us in this work to measure the natural radioactivity of the phosphate fertilizers in Tunisia. The distribution of various radionuclides during their manufacturing process of fertilizers is also part of this work.

  14. 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

  15. 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).

  16. 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.

  17. Experiment on safety software evaluation

    International Nuclear Information System (INIS)

    Soubies, B.; Henry, J.Y.

    1994-06-01

    The licensing procedures process of nuclear plants includes compulsory steps which bring about a thorough exam of the commands control system. In this context the IPSN uses a tool called MALPAS to carry out an analysis of the quality of the software involved in safety control. The IPSN also try to obtain the automation of the generation of test games necessary for dynamical analysis. The MALPAS tool puts forward the particularities of programing which can influence the testability and the upholding of the studied software. (TEC). 4 refs

  18. Radiological Safety Aspects of the operation of the Electron Linear Accelerator Linac CIRCE III 10 MeV

    International Nuclear Information System (INIS)

    Naceur, Ahmed

    2014-01-01

    This document is a report about safety and security for the electron accelerator Linac-CIRCE III of the National Center for Nuclear Sciences and Technologies of Tunis. The paper aims to introduce the standards of the International Atomic Energy Agency (IAEA) to the installation in question. Overall, it draws its profit from the official security reports of the IAEA. First, we study the anatomy of the accelerator by breaking it down into various compartments and examining the case of leaks that may arise. This part introduces the particularity of this installation and allows us to meet and provide procedures for some typical scenarios of mechanical malfunction. Second, we recall and adapt some theoretical concepts related to the quantification of the radioactivity, the thickness of the armoring, the utilization factor, and the quality factor. Thus, we become able to list of types of these radiations, dangers, risks and their sources. We also examine the phenomenon of compartments activation, toxic gases production (including ozone), the process of elimination, the danger associated with X-rays generated by high voltage system and the risk of electrocution. In light of this study, we handle mathematically the question of the armoring and the concept of radiation protection. Therefore, we present a practical methodology to implement a monitoring system and a technicality in the interpretation of the measurements. Finally, we discuss the practical aspect by introducing security governance to CIRCE III, and establishing a program of general, radiological and specific security. Then, we evaluate the areas of typical security, and present a comparative radiological study between the results obtained by the IAEA standards and those by the German DIN 6847 standard for direct Bremsstrahlung radiation and scattered radiation.

  19. Source term derivation and radiological safety analysis for the TRICO II research reactor in Kinshasa

    International Nuclear Information System (INIS)

    Muswema, J.L.; Ekoko, G.B.; Lukanda, V.M.; Lobo, J.K.-K.; Darko, E.O.; Boafo, E.K.

    2015-01-01

    Highlights: • Atmospheric dispersion modeling for two credible accidents of the TRIGA Mark II research reactor in Kinshasa (TRICO II) was performed. • Radiological safety analysis after the postulated initiating events (PIE) was also carried out. • The Karlsruhe KORIGEN and the HotSpot Health Physics codes were used to achieve the objectives of this study. • All the values of effective dose obtained following the accident scenarios were below the regulatory limits for reactor staff members and the public, respectively. - Abstract: The source term from the 1 MW TRIGA Mark II research reactor core of the Democratic Republic of the Congo was derived in this study. An atmospheric dispersion modeling followed by radiation dose calculation were performed based on two possible postulated accident scenarios. This derivation was made from an inventory of peak radioisotope activities released in the core by using the Karlsruhe version of isotope generation code KORIGEN. The atmospheric dispersion modeling was performed with HotSpot code, and its application yielded to radiation dose profile around the site using meteorological parameters specific to the area under study. The two accident scenarios were picked from possible accident analyses for TRIGA and TRIGA-fueled reactors, involving the case of destruction of the fuel element with highest activity release and a plane crash on the reactor building as the worst case scenario. Deterministic effects of these scenarios are used to update the Safety Analysis Report (SAR) of the reactor, and for its current version, these scenarios are not yet incorporated. Site-specific meteorological conditions were collected from two meteorological stations: one installed within the Atomic Energy Commission and another at the National Meteorological Agency (METTELSAT), which is not far from the site. Results show that in both accident scenarios, radiation doses remain within the limits, far below the recommended maximum effective

  20. Source term derivation and radiological safety analysis for the TRICO II research reactor in Kinshasa

    Energy Technology Data Exchange (ETDEWEB)

    Muswema, J.L., E-mail: jeremie.muswem@unikin.ac.cd [Faculty of Science, University of Kinshasa, P.O. Box 190, KIN XI (Congo, The Democratic Republic of the); Ekoko, G.B. [Faculty of Science, University of Kinshasa, P.O. Box 190, KIN XI (Congo, The Democratic Republic of the); Lukanda, V.M. [Faculty of Science, University of Kinshasa, P.O. Box 190, KIN XI (Congo, The Democratic Republic of the); Democratic Republic of the Congo' s General Atomic Energy Commission, P.O. Box AE1 (Congo, The Democratic Republic of the); Lobo, J.K.-K. [Faculty of Science, University of Kinshasa, P.O. Box 190, KIN XI (Congo, The Democratic Republic of the); Darko, E.O. [Radiation Protection Institute, Ghana Atomic Energy Commission, P.O. Box LG 80, Legon, Accra (Ghana); Boafo, E.K. [University of Ontario Institute of Technology, 2000 Simcoe St. North, Oshawa, ONL1 H7K4 (Canada)

    2015-01-15

    Highlights: • Atmospheric dispersion modeling for two credible accidents of the TRIGA Mark II research reactor in Kinshasa (TRICO II) was performed. • Radiological safety analysis after the postulated initiating events (PIE) was also carried out. • The Karlsruhe KORIGEN and the HotSpot Health Physics codes were used to achieve the objectives of this study. • All the values of effective dose obtained following the accident scenarios were below the regulatory limits for reactor staff members and the public, respectively. - Abstract: The source term from the 1 MW TRIGA Mark II research reactor core of the Democratic Republic of the Congo was derived in this study. An atmospheric dispersion modeling followed by radiation dose calculation were performed based on two possible postulated accident scenarios. This derivation was made from an inventory of peak radioisotope activities released in the core by using the Karlsruhe version of isotope generation code KORIGEN. The atmospheric dispersion modeling was performed with HotSpot code, and its application yielded to radiation dose profile around the site using meteorological parameters specific to the area under study. The two accident scenarios were picked from possible accident analyses for TRIGA and TRIGA-fueled reactors, involving the case of destruction of the fuel element with highest activity release and a plane crash on the reactor building as the worst case scenario. Deterministic effects of these scenarios are used to update the Safety Analysis Report (SAR) of the reactor, and for its current version, these scenarios are not yet incorporated. Site-specific meteorological conditions were collected from two meteorological stations: one installed within the Atomic Energy Commission and another at the National Meteorological Agency (METTELSAT), which is not far from the site. Results show that in both accident scenarios, radiation doses remain within the limits, far below the recommended maximum effective

  1. Researches on nuclear criticality safety evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Okuno, Hiroshi; Suyama, Kenya; Nomura, Yasushi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2003-10-01

    For criticality safety evaluation of burnup fuel, the general-purpose burnup calculation code, SWAT, was revised, and its precision was confirmed through comparison with other results from OECD/NEA's burnup credit benchmarks. Effect by replacing the evaluated nuclear data from JENDL-3.2 to ENDF/B-VI and JEF-2.2 was also studied. Correction factors were derived for conservative evaluation of nuclide concentrations obtained with the simplified burnup code ORIGEN2.1. The critical masses of curium were calculated and evaluated for nuclear criticality safety management of minor actinides. (author)

  2. Researches on nuclear criticality safety evaluation

    International Nuclear Information System (INIS)

    Okuno, Hiroshi; Suyama, Kenya; Nomura, Yasushi

    2003-01-01

    For criticality safety evaluation of burnup fuel, the general-purpose burnup calculation code, SWAT, was revised, and its precision was confirmed through comparison with other results from OECD/NEA's burnup credit benchmarks. Effect by replacing the evaluated nuclear data from JENDL-3.2 to ENDF/B-VI and JEF-2.2 was also studied. Correction factors were derived for conservative evaluation of nuclide concentrations obtained with the simplified burnup code ORIGEN2.1. The critical masses of curium were calculated and evaluated for nuclear criticality safety management of minor actinides. (author)

  3. Prospective safety performance evaluation on construction sites.

    Science.gov (United States)

    Wu, Xianguo; Liu, Qian; Zhang, Limao; Skibniewski, Miroslaw J; Wang, Yanhong

    2015-05-01

    This paper presents a systematic Structural Equation Modeling (SEM) based approach for Prospective Safety Performance Evaluation (PSPE) on construction sites, with causal relationships and interactions between enablers and the goals of PSPE taken into account. According to a sample of 450 valid questionnaire surveys from 30 Chinese construction enterprises, a SEM model with 26 items included for PSPE in the context of Chinese construction industry is established and then verified through the goodness-of-fit test. Three typical types of construction enterprises, namely the state-owned enterprise, private enterprise and Sino-foreign joint venture, are selected as samples to measure the level of safety performance given the enterprise scale, ownership and business strategy are different. Results provide a full understanding of safety performance practice in the construction industry, and indicate that the level of overall safety performance situation on working sites is rated at least a level of III (Fair) or above. This phenomenon can be explained that the construction industry has gradually matured with the norms, and construction enterprises should improve the level of safety performance as not to be eliminated from the government-led construction industry. The differences existing in the safety performance practice regarding different construction enterprise categories are compared and analyzed according to evaluation results. This research provides insights into cause-effect relationships among safety performance factors and goals, which, in turn, can facilitate the improvement of high safety performance in the construction industry. Copyright © 2015 Elsevier Ltd. All rights reserved.

  4. 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.

  5. 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

  6. 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)

  7. Plutonium Finishing Plant safety evaluation report

    International Nuclear Information System (INIS)

    1995-01-01

    The Plutonium Finishing Plant (PFP) previously known as the Plutonium Process and Storage Facility, or Z-Plant, was built and put into operation in 1949. Since 1949 PFP has been used for various processing missions, including plutonium purification, oxide production, metal production, parts fabrication, plutonium recovery, and the recovery of americium (Am-241). The PFP has also been used for receipt and large scale storage of plutonium scrap and product materials. The PFP Final Safety Analysis Report (FSAR) was prepared by WHC to document the hazards associated with the facility, present safety analyses of potential accident scenarios, and demonstrate the adequacy of safety class structures, systems, and components (SSCs) and operational safety requirements (OSRs) necessary to eliminate, control, or mitigate the identified hazards. Documented in this Safety Evaluation Report (SER) is DOE's independent review and evaluation of the PFP FSAR and the basis for approval of the PFP FSAR. The evaluation is presented in a format that parallels the format of the PFP FSAR. As an aid to the reactor, a list of acronyms has been included at the beginning of this report. The DOE review concluded that the risks associated with conducting plutonium handling, processing, and storage operations within PFP facilities, as described in the PFP FSAR, are acceptable, since the accident safety analyses associated with these activities meet the WHC risk acceptance guidelines and DOE safety goals in SEN-35-91

  8. Quantitative evaluation of risks for individuals in diagnostic radiology

    Energy Technology Data Exchange (ETDEWEB)

    Iinuma, T A; Tateno, Y; Hashizume, T [National Inst. of Radiological Sciences, Chiba (Japan)

    1980-05-01

    A method to estimate quantitatively risks of individual patients due to exposure to diagnostic radiation (carcinogenetic and genetic effects of radiation) was proposed on the basis of ICRP-26. Carcinogenetic effect of radiation was calculated by multiplying mean dose equivalent for each organ per each radiological examination by shortening of average life-expectancy which was calculated from incidence of fetal carcinoma of each organ, latent period of carcinoma, and incidence period of carcinoma. Genetic effect of radiation was calculated by multiplying mean dose equivalent for gonad per each radiological examination by incidence of genetically severe radiation damages due to parent's exposure and child expectancy rate. Three examples were shown on calculations of risks in the photofluorographic examinations of the stomach and chest, and mammography. The same method of calculation could be applied to the in-vivo nuclear medicine examinations. Further investigation was required to calculate the risks quantitatively for various types of diagnostic procedures using radiation.

  9. Radiation exposure and dose evaluation in intraoral dental radiology

    International Nuclear Information System (INIS)

    Poppe, B.; Looe, H. K.; Pfaffenberger, A.; Eenboom, F.; Chofor, N.; Sering, M.; Ruehmann, A.; Poplawski, A.; Willborn, K.

    2007-01-01

    In this study, dose area product measurements have been performed to propose diagnostic reference levels (DRLs) in intraoral dental radiology. Measurements were carried out at 60 X-ray units for all types of intraoral examinations performed in clinical routine. The third quartile values calculated range from 26.2 to 87.0 mGy cm 2 . The results showed that there exists a large difference between the patient exposures among different dental facilities. It was also observed that dentists working with faster film type or higher tube voltage are not always associated with lower exposure. The study demonstrated the necessity to have the DRLs laid out as guidelines in dental radiology. (authors)

  10. Quantitative evaluation of risks for individuals in diagnostic radiology

    International Nuclear Information System (INIS)

    Iinuma, T.A.; Tateno, Yukio; Hashizume, Tadashi

    1980-01-01

    A method to estimate quantitatively risks of individual patients due to exposure to diagnostic radiation (carcinogenetic and genetic effects of radiation) was proposed on the basis of ICRP-26. Carcinogenetic effect of radiation was calculated by multiplying mean dose equivalent for each organ per each radiological examination by shortening of average life-expectancy which was calculated from incidence of fetal carcinoma of each organ, latent period of carcinoma, and incidence period of carcinoma. Genetic effect of radiation was calculated by multiplying mean dose equivalent for gonad per each radiological examination by incidence of genetically severe radiation damages due to parent's exposure and child expectancy rate. Three examples were shown on calculations of risks in the photofluorographic examinations of the stomach and chest, and mammography. The same method of calculation could be applied to the in-vivo nuclear medicine examinations. Further investigation was required to calculate the risks quantitatively for various types of diagnostic procedures using radiation. (Tsunoda, M.)

  11. Clinical and radiological evaluation in vertebral artery dissections

    Directory of Open Access Journals (Sweden)

    Murat Çabalar

    2013-04-01

    Full Text Available In recent years, vertebral artery dissection (VAD is reported more frequently as a cause of young cerebrovascular accidents. It can occur spontaneously or following a neck manipulation and trauma. The patients were 3 females (mean age: 35±26 years and 7 males (mean age: 37.71±4.96 years. Only 2 patients described neck trauma. Cerebellar findings were prominent in all cases. On radiological investigation, vascular changes of vertebral arteries were detected bilaterally in 2 cases, right in 5 and left in 3 cases. All the cases were treated with anticoagulant therapy and cured but 1 with sequela. Prognosis of vertebral artery dissection is generally good by early diagnosis and treatment. In this article, we reported clinical and radiological properties of 10 vertebral artery dissection cases.

  12. Evaluation of the detector response function digital conventional radiology

    International Nuclear Information System (INIS)

    Arino Gil, A.; Hernandez Rodriguez, J.; Mateos Salvador, P.; Rodriguez Lopez, B.; Font Gelabert, J. C.

    2013-01-01

    The objective of this work is to obtain the response function that relates the air kerma at the entrance of the detector and pixel value, for a series of digital detectors of conventional Radiology model Optimus DigitalDiagnost Philips () and 6000 Definium General Electric. From the set of measurements is obtained a response function for each reference type of detector, and compared with those published in the literature for these teams. (Author)

  13. Evaluation system for the analysis of the radiological consequences (RASCAL)

    International Nuclear Information System (INIS)

    Miguel Martinez, M. J. de

    2011-01-01

    The code currently employed by the Spanish Nuclear power is the IRDAM (Interactive Rapid Dose Assessment Model). This code will now be replaced by the RASCAL (Radiological Assessment System for Consequence Analysis) version 4.0. This is a significant improvement in dose calculation for escapes to the atmosphere for radioactive emergencies. The main objective is to highlight the most significant changes introduced in the RASCAL when performing these dose estimates.

  14. Optimized Evaluation System to Athletic Food Safety

    OpenAIRE

    Shanshan Li

    2015-01-01

    This study presented a new method of optimizing evaluation function in athletic food safety information programming by particle swarm optimization. The process of food information evaluation function is to automatically adjust these parameters in the evaluation function by self-optimizing method accomplished through competition, which is a food information system plays against itself with different evaluation functions. The results show that the particle swarm optimization is successfully app...

  15. SGHWR safety design and evaluation

    International Nuclear Information System (INIS)

    Smith, D.R.; Merrett, D.J.; Ward, D.A.

    1977-01-01

    The paper discusses the characteristic features of the S.G.H.W.R. and identifies the single channel concept as of considerable importance. The unique feature of the design is the provision of individual spray cooling E.C.C.S. to each channel. This spray cooling occupies a prominent position in the main line safety arguments. The reliance on this form of spray cooling leads to provision of a comprehensive E.C.C.S. system of high reliability. Duplicate systems with diverse power and water sources cover the complete pressure range to give very high confidence that spray cooling is available in all major L.O.C.A.s. On the other hand hydraulic analysis of the blowdown phase demonstrates that significant convective flow is available as an alternative/supplementary cooling regime for most faults. The reactor shutdown mechanisms have also been duplicated and will be designed to high reliabilities to give surety of reactor trip in all credible faults. The comparative performance of the two systems is considered. Extent of diversity and redundancy in trip parameters is also discussed. A feature of channel concept is that the pipe sizes can be made relatively small thus restricting rates of blowdown, and the paper discusses effects of this upon long term cooling and flooding arguments. The quantities of pipework in the primary circuit introduce considerations of integrity and the paper goes on to list the measures introduced to improve segregation and protection of individual sections of the plant so that the extent of possible L.O.C.A.s is minimised. The achievement of high standards of reliability by use of in-service inspection is covered, with particular reference to the steam drums. The impact of these inspection requirements upon the very low man-rem exposures required by U.K. utilities is also included. Finally, it is noted that the provision of containment in common with other L.W.R. practice also provides a valuable engineered safety feature. The principles of

  16. Radiological safety experience in nuclear fuel cycle operations at Bhabha Atomic Research Center, Trombay, Mumbai, India

    International Nuclear Information System (INIS)

    Pushparaja; Gopalakrishnan, R.K.; Subramaniam, G.

    2000-01-01

    Activities at Bhabha Atomic Research Centre (BARC), Mumbai, cover nuclear fuel cycle operations based on natural uranium as the fuel. The facilities include: plant for purification and production of nuclear grade uranium metal, fuel fabrication, research reactor operation, fuel reprocessing and radioactive waste management in each stage. Comprehensive radiation protection programmes for assessment and monitoring of radiological impact of these operations, both in occupational and public environment, have been operating in BARC since beginning. These programmes, based on the 1990 ICRP Recommendations as prescribed by national regulatory body, the Atomic Energy Regulatory Board (AERB), are being successfully implemented by the Health, Safety and Environment Group, BARC. Radiation Hazards Control Units attached to the nuclear fuel cycle facilities provide radiation safety surveillance to the various operations. The radiation monitoring programme consists of measurement and control of external exposures by thermoluminescent dosimeters (TLDs), hand-held and installed instruments, and internal exposures by bioassay and direct whole body counting using shadow shield counter for beta gamma emitters and phoswich detector based system for plutonium. In addition, an environmental monitoring programme is in place to assess public exposures resulting from the operation of these facilities. The programme involves analysis of various matrices in the environment such as bay water, salt, fish, sediment and computation of resulting public exposures. Based on the operating experience in these plants, improved educating and training programmes for plant operators, have been designed. This, together with the application of new technologies have brought down individual as well as average doses of occupational workers. The environmental releases remain a small fraction of the authorised limits. The operating health physics experience in some of these facilities is discussed in this paper

  17. Medical management of radiation safety and radiological protection of patients in Armenia

    International Nuclear Information System (INIS)

    Hovhannisyan, N.M.

    2001-01-01

    The events of the last 10 years, Spitak earthquake (1988) and collapse of the Former Soviet Union, brought forth the changes of the political situation in Armenia and significant disorder in economy, industry, relations, environmental and public health, including the radiation safety (RS) and control of patients in general diagnostic radiology. In Armenia there are about 750 X-ray rooms, 10 radionuclide diagnostic laboratories, 20 gamma and X-ray units. 95 enterprises in industry, science and technology use the Ionizing Radiation Sources (IRSs) with different purposes; there are 5 electron particle accelerators of different power capacity. About 6,000 individuals have constant contact to IRS: the roentgenologists, radiologists, the staff of Armenian Nuclear Power Plant and that of the accelerators, etc. Besides, more than 3,000 liquidators of the Chernobyl NPP disaster live in Armenia. Nowadays, the precise infrastructure of RS is established in Armenia. The regulating body is the 'State Atom Authority', performing the control, coordination and licensing of both enterprises and specialists. Ministry of Health, Ministry of Internal Affairs, and Ministry of Ecology perform the control of IRSs' delivery into the Republic of Armenia and then their proper use and waste disposal in Armenia. (author)

  18. Mechanical analysis of flying robot for nuclear safety and security control by radiological monitoring

    International Nuclear Information System (INIS)

    Cho, Hyo Sung; Woo, Tae Ho

    2016-01-01

    Highlights: • Radiological monitoring of the NPPs site is performed by the flying robot. • The mechanics of drone is investigated in the NPPs. • Yaw and Pitch motions are simulated for the robotic behaviors. • The flying robot is analyzed for the nuclear safety and security successfully. - Abstract: The flying robot is investigated for the nuclear accident and security treatment. Several mechanics are introduced for the movement of the drone. The optimized motion of the drone should cover all areas of Nuclear Power Plants (NPPs) over the site where the circular and surmounting motions are needed with traverse of zigzag shapes. There is the Yaw motion in the circular moving and the Pitch motion in the climbing and downing against reactor facility. The fallout is calculated from the radiation concentration in the breaking part of the NPPs where the radioactive material leaks from the containment, coolant loop, plant facility and so on. The dose equivalents are obtained where the values are changeable following the random values of the y value, average wind speed, and dispersed concentration in the detection position. The simulation of new positions of x, y, and z are normalized from 0.0 to 1.0. The mechanics of flying robot produces the multidisciplinary converged technology incorporated with the aerial radiation monitoring information.

  19. Safety evaluation of large ventilation networks

    International Nuclear Information System (INIS)

    Barrocas, M.; Pruchon, P.; Robin, J.P.; Rouyer, J.L.; Salmon, P.

    1981-01-01

    For large ventilation networks, it is necessary to make a safety evaluation of their responses to perturbations such as blower failure, unexpected transfers, local pressurization. This evaluation is not easy to perform because of the many interrelationships between the different parts of the networks, interrelationships coming from the circulations of workers and matetials between cells and rooms and from the usefulness of air transfers through zones of different classifications. This evaluation is all the more necessary since new imperatives in energy savings push for minimizing the air flows, which tends to render the network more sensitive to perturbations. A program to evaluate safety has been developed by the Service de Protection Technique in cooperation with operators and designers of big nuclear facilities and the first applications presented here show the weak points of the installation studied from the safety view point

  20. Squale: evaluation criteria of functioning safety

    International Nuclear Information System (INIS)

    Deswarte, Y.; Kaaniche, M.; Benoit, P.

    1998-05-01

    The SQUALE (security, safety and quality evaluation for dependable systems) project is part of the ACTS (advanced communications, technologies and services) European program. Its aim is to develop confidence evaluation criteria to test the functioning safety of systems. All industrial sectors that use critical applications (nuclear, railway, aerospace..) are concerned. SQUALE evaluation criteria differ from the classical evaluation methods: they are independent of the application domains and industrial sectors, they take into account the overall functioning safety attributes, and they can progressively change according to the level of severity required. In order to validate the approach and to refine the criteria, a first experiment is in progress with the METEOR automatic underground railway and another will be carried out on a telecommunication system developed by Bouygues company. (J.S.)

  1. Safety culture management and quantitative indicator evaluation

    International Nuclear Information System (INIS)

    Mandula, J.

    2002-01-01

    This report discuses a relationship between safety culture and evaluation of quantitative indicators. It shows how a systematic use of generally shared operational safety indicators may contribute to formation and reinforcement of safety culture characteristics in routine plant operation. The report also briefly describes the system of operational safety indicators used at the Dukovany plant. It is a PC database application enabling an effective work with the indicators and providing all users with an efficient tool for making synoptic overviews of indicator values in their links and hierarchical structure. Using color coding, the system allows quick indicator evaluation against predefined limits considering indicator value trends. The system, which has resulted from several-year development, was completely established at the plant during the years 2001 and 2002. (author)

  2. Safety evaluation of synthetic β-carotene

    NARCIS (Netherlands)

    Woutersen, R.A.; Wolterbeek, A.P.M.; Appel, M.J.; Berg, H. van den; Goldbohm, R.A.; Feron, V.J.

    1999-01-01

    The safety of β-carotene was reassessed by evaluating the relevant literature on the beneficial and adverse effects of β-carotene on cancer and, in particular, by evaluating the results of toxicity studies. β- Carotene appeared neither genotoxic nor reprotoxic or teratogenic, and no signs of organ

  3. 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.)

  4. 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.)

  5. 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.

  6. 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)

  7. 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.

  8. 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)

  9. The responsible by the radiological safety in the industry. Between the occupational environment and the today technology

    International Nuclear Information System (INIS)

    Truppa, Walter A.

    2006-01-01

    In industrial applications of the sealed radioactive sources, there are two clearly definite branches for which these materials are utilized: radioactive sources utilized in fixed and in portable equipment. These devices are utilized in an endless number of applications and each time with more advanced technological systems. This requires a permanent improvement in the training of the responsible, and at the same time introduces an obligatory change to other intervention groups during the useful life of the device. The risks of accident, to the ones associated with the use of these equipment, though their rate of occurrence is low, they are errors during the operation, undue use, maintenance by personnel without knowledge, human type failures or carelessness and incidents occurred during the transportation. All these risks are surrounded by different groups of factors that influence during the sure use of the radioactive material inside the installation. Therefore the importance to establish aspects of Safety Culture, aptitude evaluations of the radiological security responsible, improvements introduction in quality and risks communication aspects, in agreement with the Argentine Republic regulations and the international requests, is emphasized. In the present paper all concepts about the radioactive material responsible election, the training, the factors that intervene during the operation, the installation obligations, insecurity situations and the changes or improvements that technology introduces, are referenced. (author) [es

  10. 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

  11. Evaluation of the lacrimal system by radiological methods

    International Nuclear Information System (INIS)

    Francisco, Fabiano Celli; Francisco, Vivian Frida Murta; Mendonca Junior, Adhemar Azevedo de; Carvalho, Antonio Carlos Pires; Fonseca, Lea Mirian Barbosa da; Gutfilen, Bianca; Francisco, Marina Celli

    2007-01-01

    The authors perform a revisional and iconographic study of the lacrimal system by means of radiological methods, namely, conventional radiography, linear tomography, computed tomography and magnetic resonance imaging. Image methods are essential to define diagnosis and therapy, considering that besides demonstrating alterations of the lacrimal system, they may indicate the patients with better prognosis associated with the surgical approach. Considering the lower cost, lower radiation dose, low rate of complications, and level of information that can be obtained dacryocystography by means of linear tomography is recommended as the initial investigation method. (author)

  12. Organ doses in interventional radiology procedures: Evaluation of software

    International Nuclear Information System (INIS)

    Tort, I.; Ruiz-Cruces, R.; Perez-Martinez, M.; Carrera, F.; Ojeda, C.; Diez de los Rios, A.

    2001-01-01

    Interventional Radiology (IR) procedures require large fluoroscopy times and important number of radiological images, so the levels of radiation to patient are high, which leads us to calculate the organ doses. The objective of this work is to estimate and make a comparison of the results given by the different software that we have to do the calculation of organ doses in complex procedures of IR. To do this, 28 patients have been selected, distributed in the 3 procedures with highest doses. The determination of organ doses and effective doses has been made using the projections utilized and different software based on Monte Carlo Methods: Eff-dose, PCXMC and Diasoft. We have obtained very high dispersion in the average organ dose between the 3 programs. In many cases, it is higher than 25% and in some particular cases, it is greater than 100%. Dispersion obtained in effective doses is not so high, being under 20% in all cases. This shows that a better solution is needed to solve the problem of the organ doses calculation; a more accurate method is necessary that brings us to a trustworthy approach to reality, and, at the moment, that we do not dispose of it. (author)

  13. EURISOL-DS Multi‐MW Target: Radiological Protection, Radiation Safety and Shielding Aspects

    CERN Document Server

    Y. Romanets and R. Luís (ITN)

    The objective of this work was to carry out a detailed study and analysis of all aspects related toradioprotection and radiation safety of the spallation target area and the whole spaces reservedfor the fission targets and spallation target maintenance. Operational and no‐operationalconditions were considered for an evaluation of the radiation safety conditions.An analysis of the proposed shielding dimensions and configuration was performed for thesystem during operation time. Parameters as activation, dose rate, energy deposition, etc. aremore important for the no‐operation period, in order to evaluate the hazard level anddetermine the staff access type to the maintenance areas (direct or remote control).Such elements as the fission targets and the whole structure involved on it were studied in moredetail because of the disposal issues, after operation. Activation, dose rate and residual nuclideswere studied for each element of the assembly. All parameters were analyzed according to their...

  14. The Interagency Nuclear Safety Review Panel's Galileo safety evaluation report

    International Nuclear Information System (INIS)

    Nelson, R.C.; Gray, L.B.; Huff, D.A.

    1989-01-01

    The safety evaluation report (SER) for Galileo was prepared by the Interagency Nuclear Safety Review Panel (INSRP) coordinators in accordance with Presidential directive/National Security Council memorandum 25. The INSRP consists of three coordinators appointed by their respective agencies, the Department of Defense, the Department of Energy (DOE), and the National Aeronautics and Space Administration (NASA). These individuals are independent of the program being evaluated and depend on independent experts drawn from the national technical community to serve on the five INSRP subpanels. The Galileo SER is based on input provided by the NASA Galileo Program Office, review and assessment of the final safety analysis report prepared by the Office of Special Applications of the DOE under a memorandum of understanding between NASA and the DOE, as well as other related data and analyses. The SER was prepared for use by the agencies and the Office of Science and Technology Policy, Executive Office of the Present for use in their launch decision-making process. Although more than 20 nuclear-powered space missions have been previously reviewed via the INSRP process, the Galileo review constituted the first review of a nuclear power source associated with launch aboard the Space Transportation System

  15. 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

  16. Critical evaluation of German regulatory specifications for calculating radiological exposure

    Energy Technology Data Exchange (ETDEWEB)

    Koenig, Claudia; Walther, Clemens [Hannover Univ. (Germany). Inst. of Radioecology; Smeddinck, Ulrich [Technische Univ. Braunschweig (Germany). Inst. of Law

    2015-07-01

    The assessment of radiological exposure of the public is an issue at the interface between scientific findings, juridical standard setting and political decision. The present work revisits the German regulatory specifications for calculating radiological exposure, like the already existing calculation model General Administrative Provision (AVV) for planning and monitoring nuclear facilities. We address the calculation models for the recent risk assessment regarding the final disposal of radioactive waste in Germany. To do so, a two-pronged approach is pursued. One part deals with radiological examinations of the groundwater-soil-transfer path of radionuclides into the biosphere. Processes at the so-called geosphere-biosphere-interface are examined, especially migration of I-129 in the unsaturated zone. This is necessary, since the German General Administrative Provision does not consider radionuclide transport via groundwater from an underground disposal facility yet. Especially data with regard to processes in the vadose zone are scarce. Therefore, using I-125 as a tracer, immobilization and mobilization of iodine is investigated in two reference soils from the German Federal Environment Agency. The second part of this study examines how scientific findings but also measures and activities of stakeholders and concerned parties influence juridical standard setting, which is necessary for risk management. Risk assessment, which is a scientific task, includes identification and investigation of relevant sources of radiation, possible pathways to humans, and maximum extent and duration of exposure based on dose-response functions. Risk characterization identifies probability and severity of health effects. These findings have to be communicated to authorities, who have to deal with the risk management. Risk management includes, for instance, taking into account acceptability of the risk, actions to reduce, mitigate, substitute or monitor the hazard, the setting of

  17. The clinical and radiological evaluation of pyogenic arthritis

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Young Jun; Kim, Kyung Joo; Yoo, Jung Keun; Kim, Young Chul; Hur, Don [Chosun University College of Medicine, Gwangju (Korea, Republic of)

    1984-12-15

    Pyogenic arthritis remain a difficult problem, despite the availability of a wide range of powerful modern antibiotics. Early and correct diagnosis is imperative to assure the prompt initiation of an effective therapeutic regimen and the prevent of late sequela. Careful clinical, laboratory and roentgenological analysis are fundamental to early and precise diagnosis. Therefore, plain roentgenogram should not be overlooked. A radiological and clinical observation was made in 51 cases of pyogenic arthritis admitted to Chosun University Hospital during the period from January 1976 to December 1983 and following results were obtained. 1. Among the 51 cases, 36 cases (70.6%) were male and 15 cases (29.4%) were females. The most prevalent age was 5 to 9 (27.6%). 2. Symptom duration less than 5 days was in 21 cases (41.2%) and more than 31 days was in 6 cases (11.7%). 3. The most common symptom on admission was pain around the involved joint and others are limitation of motion, swelling, tenderness, fever, local heating and erythema. 4. The underlying causes were composed of unknown in 21 cases (41.2%), trauma in 18 cases (35.3%), infections focus in 8 cases (15.7%) and iatrogenic reason 4 cases (7.8%). 5. The most commonly affected joint was hip joint (45.1%). The other affected sites in order of frequency were knee, ankle, shoulder, S-I and elbow joint. In infants and children, hip and knee joint are commonly affected: in adults, knee joint is most is most commonly affected. 6. In laboratory findings, the number of W.B.C and E.S.R were increased in 56.9%. Symptom duration more than 31 days in 5 cases were increased E.S.R only. Causative microorganism was isolated in 31 cases: the most common microorganism was Staphylococcus aureus in 22 cases. Others are B-hemolytics Stretoocccus, Enterobacteriaceae species and Pseudomonas aeruginosa. 7. In 26 cases (50.9%) of the patients, roentgenographic findings was negative. The most common radiological findings was soft tissue

  18. The clinical and radiological evaluation of pyogenic arthritis

    International Nuclear Information System (INIS)

    Cho, Young Jun; Kim, Kyung Joo; Yoo, Jung Keun; Kim, Young Chul; Hur, Don

    1984-01-01

    Pyogenic arthritis remain a difficult problem, despite the availability of a wide range of powerful modern antibiotics. Early and correct diagnosis is imperative to assure the prompt initiation of an effective therapeutic regimen and the prevent of late sequela. Careful clinical, laboratory and roentgenological analysis are fundamental to early and precise diagnosis. Therefore, plain roentgenogram should not be overlooked. A radiological and clinical observation was made in 51 cases of pyogenic arthritis admitted to Chosun University Hospital during the period from January 1976 to December 1983 and following results were obtained. 1. Among the 51 cases, 36 cases (70.6%) were male and 15 cases (29.4%) were females. The most prevalent age was 5 to 9 (27.6%). 2. Symptom duration less than 5 days was in 21 cases (41.2%) and more than 31 days was in 6 cases (11.7%). 3. The most common symptom on admission was pain around the involved joint and others are limitation of motion, swelling, tenderness, fever, local heating and erythema. 4. The underlying causes were composed of unknown in 21 cases (41.2%), trauma in 18 cases (35.3%), infections focus in 8 cases (15.7%) and iatrogenic reason 4 cases (7.8%). 5. The most commonly affected joint was hip joint (45.1%). The other affected sites in order of frequency were knee, ankle, shoulder, S-I and elbow joint. In infants and children, hip and knee joint are commonly affected: in adults, knee joint is most is most commonly affected. 6. In laboratory findings, the number of W.B.C and E.S.R were increased in 56.9%. Symptom duration more than 31 days in 5 cases were increased E.S.R only. Causative microorganism was isolated in 31 cases: the most common microorganism was Staphylococcus aureus in 22 cases. Others are B-hemolytics Stretoocccus, Enterobacteriaceae species and Pseudomonas aeruginosa. 7. In 26 cases (50.9%) of the patients, roentgenographic findings was negative. The most common radiological findings was soft tissue

  19. The evaluation of radiological and clinical findings of bronchiectasis

    International Nuclear Information System (INIS)

    Yoo, Jung Keun; Kang, Sung Ihn; Kim, Kil Jung; Ko, Seung Sook; Kim, Young Sook; Kim, Young Chul

    1985-01-01

    Bronchiectasis means a permanent abnormal dilatation off one or more large bronchi owing to destruction of the elastic and muscular components of the bronchial wall. Radiological study is the most important and mandatory procedure. Especially bronchography is essential for the definitive diagnosis of bronchiectasis and for the precise delineation of the type and extent of the disease. The radiological and clinical findings of 48 cases of bronchiectasis diagnosed by bronchography and treated at Chosun University Hospital during the 5 years from January 1980 to December 1984 were analyzed retrospectively. The results were as follows; 1. Among the 48 cases, 34 cases (70.8%) were male and 14 cases (29.2%) were female. Peak incidence was in second decade. 2. Chronic cough productive sputum and hemoptysis are main symptoms and others are chest pain, dyspnea and recurrent bouts of pneumonia. The most common physical sign is persistent moist rales over the involved area in 23 cases (47.9%). Others are no sign in 17 cases (35.4%), wheezing in 11 cases (22.9%) and digit clubbing in 3 cases (6.3%). 3. The presumed causes were composed of not known in 30 cases (62.5%)> and complications of measles in 7 cases (14.6%), pertussis in 5 cases (10.4%) and pneumonia in 4 cases (8.3%). Two cases were Kartagener's syndrome and unilateral hyperlucent lung. 4. Plain chest common radiological findings was accentuation of lung marking in 36 cases (85.7%), the others are include in order of frequency; pneumonic infiltration, linear radiolucencies, cystic radiolucencies, decreased affected lung volume, air-fluid, level and pleural thickening. 5. Bilateral bronchiectasis was demonstrated in 11 cases (22.9%) and the disease was much more often involved left lung than right. The most commonly involved lobe is left lower lobe, and the most common site of involvement was the posterior basal segment of the lower lobe. The type of bronchiectasis is cylindrical in 22 cases (45.8%), varicose in 11

  20. Problems of nuclear power plant safety evaluation

    International Nuclear Information System (INIS)

    Suchomel, J.

    1977-01-01

    Nuclear power plant safety is discussed with regard to external effects on the containment and to the human factor. As for external effects, attention is focused on shock waves which may be due to explosions or accidents in flammable material transport and storage, to missiles, and to earthquake effects. The criteria for evaluating nuclear power plant safety in different countries are shown. Factors are discussed affecting the reliability of man with regard to his behaviour in a loss-of-coolant accident in the power plant. Different types of PWR containments and their functions are analyzed, mainly in case of accident. Views are discussed on the role of destructive accidents in the overall evaluation of fast reactor safety. Experiences are summed up gained with the operation of WWER reactors with respect to the environmental impact of the nuclear power plants. (Z.M.)

  1. Radiological safety aspects during handling of adjuster rod (cobalt-60) samples at Cirus

    International Nuclear Information System (INIS)

    Yadav, R.K.B.; Prasad, S.K.; Khuspe, R.R.; Babu, K.S.; Kamble, M.K.; Deshpande, S.B.; Srivastava, Alok; Ramesh, N.; Sharma, R.C.

    2008-01-01

    Cobalt -60 produced from the irradiation of the 59 Co capsules in adjuster rod of Cirus is used in many medical and industrial applications such as radiation therapy, sterilization of agricultural products, sterilization of medical equipment, industrial gamma exposure devices, nucleonic gauging sources etc. Two adjuster rods used for adjusting small reactivity loads (3.5 mk at 40 MW) in reactor contain thirty 59 Co slugs each. The 59 Co slugs are in the form of small capsules. These slugs were irradiated for nearly 3 years of full power operation. Since the amount of activity handled in the adjuster rod is very high (35 - 40 kCi), adequate radiological safety coverage is to be provided during the transfer of adjuster rod from the reactor pile to Tray Rod Facility (TRF) and during remote handling and loading of adjuster rod samples in shipping flask at TRF. Radiation fields observed are 0.4 - 3.0 Gy/h. In Cirus, falling of Adjuster rod from vertical flask at top of pile could result in declaration of evacuation emergency due to potential hazards associated with the high radiation field (∼26 Gy/h at 1m) of 60 Co slugs. Entire process of remote handling is viewed through lead glass and movement of samples is carried out with the help of a pair of master slave manipulator (MSM) arms. TRF with full samples give a radiation background of 0.2 - 20 mGy/h, requiring control of movement of personnel in the area. This paper explains in detail about the health physics aspects during handling of adjuster rod from reactor pile to TRF and back to pile, unloading and loading of radioisotope samples, operational radiation protection experience gained and collective dose consumed for the above transfer and loading job. The collective dose consumed in the handling of two adjuster rods is 8.7 per-mSv. (author)

  2. Joint WHO/ISH workshop on efficacy and radiation safety in interventional radiology

    International Nuclear Information System (INIS)

    Baeuml, A.; Bauer, B.; Bernhardt, J.H.; Stieve, F.E.; Veit, R.; Zeitlberger, I.

    1997-02-01

    With the constantly developing technology and the opening of new fields of application, the implementation of Interventional Radiology (IR) is increasing considerably. These sophisticated procedures can frequently replace open surgery, and this is of enormous benefit for the patient. On the other hand, IR involves prolonged application of fluoroscopy and - due to the need for excellent image quality - partly very high dose-rate levels. Additionally, cine-series, and alsogreat numbers of single radiographs are necessary. Accordingly, the levels of exposure to patients and staff are very high. In order to consider possible reduction of the radiation risks of IR procedures interdiciplinary talks between representatives of manufacturers of X-ray equipment, hospital physicists and the clinical community would seem necessary in order to find ways of avoiding unproductive radiation exposure to the patient and to clinical staff. This was the aim of a workshop on IR, which was jointly organized by the World Health Organization and the Institute of Radiation Hygiene of the Federal Office for Radiation Protection in Germany in October 1995. It was intended as a forum for the discussion of issues related to IR, and to forster improved application, that is to say as an opportunity: To present the state of the art; to work out proposals for more efficient clinical protocols; to discuss on schemes of education and training and on equipment-related developments. Improvement of radiation safety for both patients and staff, was the general aim of the workshop. This volume contains the presentations given on the first day of the workshop. (orig./DG) [de

  3. 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

  4. 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

  5. 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.

  6. Ionising radiations. Joint consultative document. Supplementary proposals for provision on radiological protection and draft advice from the National Radiological Protection Board to the Health and Safety Commission

    International Nuclear Information System (INIS)

    1979-01-01

    The consultative document is in two parts. Part 1 indicates the amendments to the first consultative document which would be required in order to implement (in the United Kingdom) the 1978 Draft Euratom Directive (on Basic Safety Standards for the health protection of the general public and workers against the dangers of ionising radiations). Part 2 deals with the system of dose limitation contained within the Euratom Directive. This aspect is discussed, in relation to the Articles of the Directive, under the following headings: limitation of doses for controllable exposures, limits of doses for exposed workers, limitation of doses for apprentices and students, planned special exposures, dose limits for members of the public. The Commission of the European Communities proposals for a draft Directive on Radiological Protection are reproduced as an Appendix, without Annexes. (U.K.)

  7. 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, ...

  8. 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)

  9. Operational safety evaluation for minor reactor accidents

    International Nuclear Information System (INIS)

    Wang, O.S.

    1981-01-01

    The purpose of this paper is to address a concern of applying conservatism in analysing minor reactor incidents. A so-called ''conservative'' safety analysis may exaggerate the system responses and result in a reactor scram tripped by the reactor protective system (RPS). In reality, a minor incident may lead the reactor to a new thermal hydraulic steady-state without scram, and the mitigation or termination of the incident may entirely depend on operator actions. An example on a small steamline break evaluation for a pressurized water reactor recently investigated by the staff at the Washington Public Power Supply System is presented to illustrate this point. A safety evaluation using mainly the safety-related systems to be consistent with the conservative assumptions used in the Safety Analysis Report was conducted. For comparison, a realistic analysis was also performed using both the safety- and control-related systems. The analyses were performed using the RETRAN plant simulation computer code. The ''conservative'' safety analysis predicts that the incident can be turned over by the RPS scram trips without operator intervention. However, the realistic analysis concludes that the reactor will reach a new steady-state at a different plant thermal hydraulic condition. As a result, the termination of the incident at this stage depends entirely on proper operator action. On the basis of this investigation it is concluded that, for minor incidents, ''conservative'' assumptions are not necessary, sometimes not justifiable. A realistic investigation from the operational safety point of view is more appropriate. It is essential to highlight the key transient indications for specific incident recognition in the operator training program

  10. Preclosure radiological safety analysis for the exploratory shaft facilities; Yucca Mountain Site Characterization Project

    Energy Technology Data Exchange (ETDEWEB)

    Ma, C.W.; Miller, D.D.; Jardine, L.J. [Bechtel National, Inc., San Francisco, CA (United States)

    1992-06-01

    This study assesses which structures, systems, and components of the exploratory shaft facility (ESF) are important to safety when the ESF is converted to become part of the operating waste repository. The assessment follows the methodology required by DOE Procedure AP-6.10Q. Failures of the converted ESF during the preclosure period have been evaluated, along with other underground accidents, to determine the potential offsite radiation doses and associated probabilities. The assessment indicates that failures of the ESF will not result in radiation doses greater than 0.5 rem at the nearest unrestricted area boundary. Furthermore, credible accidents in other underground facilities will not result in radiation doses larger than 0.5 rem, even if any structure, system, or component of the converted ESF fails at the same time. Therefore, no structure, system, or component of the converted ESF is important to safety.

  11. 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.)

  12. Evaluation of the radiological situation of the remedied areas - 30 years after the radiological accident with Cesium-137

    International Nuclear Information System (INIS)

    Correa, R. da S.; Santos, E.E. dos; Barbosa, R.C.; Borges, A.F. de Almeida; Costa, H.F.; Pimenta, L.

    2017-01-01

    In September 1987, the radiation accident resulting from the removal and dismantling of a sealed source containing Cesium-137 chloride happened in Goiânia, GO, Brazil. Due to its high solubility and the weather conditions of the time, there were dispersion in the environment around seven main concentrations, located in the central region. This study aimed to present the evaluation of the radiological situation of the remedied areas - 30 years after the radiation accident with cesium-137. The three main focuses were studied, being the plot of land at the 57 street, Scrap Metal I and II. Radiometric surveys were performed using a SPP2 detector, 10 cm from the floor to evaluate the integrity of the concrete and 1 m from the soil, using the IDENTIFIDER detector model NG + , to compare with the values of background radiation. A 2 x 2m pre-fixed sampling loop was used. In the plot of land at the 57 street, measurements were made at 154 points, at 10 cm from the floor, at a mean of 150 ± 121 cps, while at 1 m from the soil, the average was 0.19 ± 0.10 μSv / h. In the Scrap Metal I were 262 measurements and the average at 10 cm of the floor was 147 ± 113 cps and the 1 meter of the soil was of 0.18 ± 0.12 μSv / h. In Scrap Metal II the average of the 66 measurements carried out at 10 cm was 117 ± 58 cps and at 1 meter it was 0.13 ± 0.03 μSv / h. Currently the radiological situation of the lots, are below the limits established by the norms of CNEN

  13. 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

  14. Evaluating fuel cycle safety for CITa

    International Nuclear Information System (INIS)

    Longhurst, G.R.; Reilly, H.J.; Piet, S.J.

    1987-01-01

    A safety concern in the design of the Compact Ignition Tokamak (CIT) currently being designed in the U. S. is the accidental release of tritium. To evaluate the basis for that concern, an assessment of the risk to the public posed by CIT was conducted that made use of probabilistic risk assessment (PRA) techniques. These include both frequency and consequence elements of risk. This analysis concluded that the tritium systems on the CIT could be designed and operated as planned with negligible safety impact, well within the established guidelines. (author)

  15. 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

  16. 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

  17. Bluish granites from Extremadura (Spain): a radiological evaluation.

    Science.gov (United States)

    Pereira, Dolores; Neves, Luís.; Peinado, Mercedes; Pereira, Alcides; Rodríguez, Leticia; António Blanco, José

    2010-05-01

    We have found in the area of Trujillo (Extremadura, Spain) a variety of striking bluish granites, outcropping within the Plasenzuela pluton. They are all quarried under different names and are characterized by leucocratic minerals such as quartz, feldspar (both potassium and plagioclase), sometimes giving a fenocrystic texture and muscovite, with some biotite. As accessory phases, idiomorphic tourmaline is found. Recently a bluish phosphate distributed in the whole rock was detected, included within most mineral phases and fillings from stressed structures that are cutting the rock. We attribute the bluish color of the granites to this phosphate. Although biotite is almost always transformed to chlorite, the rock gives an excellent response to be polished. Physico-mechanical properties make this bluish granite a perfect option for most applications. Absorption coefficient is rather low and alteration by thermal changes has not been observed. A secondary facies with yellow colour also occurs, spatially close to the topographic surface, and probably represents an alteration product of the original granite. This facies is also commercialized as ornamental stone. A radiological survey was carried out in the field, using a gamma ray spectrometer. The radiological background is quite homogeneous in the pluton, without significant differences between gamma ray fluxes of both facies (altered and non altered). The average contents of U, Th and K2O determined in situ with the spectrometer are 7.4 ppm, 0.8 ppm and 3.67%, respectively (n=15). Using U as a Ra proxy, the I index of the EU technical document 112 can be determined, and results in a value of 0.64 for the referred composition. This implies that the rock can be used without any restrictions for building purposes. However, a marked difference was observed in radon exhalation tests carried out in laboratorial facilities. The dominant blue variety shows radon exhalation rates comprised between 0.02 and 0.04 Bq.kg-1.h-1

  18. A radiologic evaluation of obstructive jaundice using percutaneous transhepatic cholangiography

    International Nuclear Information System (INIS)

    Schim, G. T.; Kim, T. H.; Zeon, S. K.; Ra, W. Y.

    1980-01-01

    Percutaneous transhepatic cholangiography (P.T.C.) is a most valuable procedure in differentiation of obstructive jaundice, whether benign (chiefly stone) or malignant condition. Authors present the clinical and P.T.C. findings of 30 cases of obstructive jaundice which were experienced from December 1975 to May 1977, at Department of Radiology, Kyung Pook National University Hospital. The summarized results were as follows. 1. The incidence of malignancy beyond the age of 40 was high compared with stone, which revealed relatively equal age distribution. 2. The stone showed as concave cupping in all cases (11 cases), but the malignancy showed as nipple formation (10 cases) and irregular narrowings (9 cases). 3. The dilation of the intrahepatic bile duct appeared 10 cases on malignancy among 19 cases of malignancy (52.6%) and 4 caes on stone which were multiple intrahepatic or common hepatic duct stones. 4. The dilation of the justproximal bile duct was severe on malignancy compared with stone. 5. The mean bilirubin level was high on malignancy (12.8 mg-%) compared with stone (10.3 mg-%).

  19. Radiological evaluation of tuberculous spondylitis with computed tomography

    International Nuclear Information System (INIS)

    Lim, Seung Soo; Kim, Chung Hyun; Cho, June Sik; Rhee, Byung Chull

    1986-01-01

    Spinal tuberculosis is curable disease, and early diagnosis is mandatory for early treatment. We reviewed conventional radiographers and computed tomograms (CT) from Histopathologically confirmed 30 cases of spinal tuberculosis, and compared these findings with radiologic findings from 2 cases of pyogenic spondylitis and 4 cases of metastasis. The results were as follows: 1. The frequent site of involvement were thromboembolic junction and low lumbar vertebrae, and the most frequent type is multisegmented subligamentous type (93.3%). 2. CT was not of great use in the differential diagnosis of the tuberculosis. Dominant CT findings of tuberculous spondylitis were anterior vertebral body destruction, paravertebral soft-tissue mass and thick walled abscess formation occasionally containing calcification and disc space narrowing in the setting of an indolent or relatively benign course. 3. CT is the best modality for imaging the extent and anatomy of the destructive process, the degree of canal encroachment, and the change of adjacent vital structure. So CT was particularly useful in pre-operative planning of debridement and stabilization surgery. 4. The most common causes of neurologic manifestations in tuberculous spondylitis were the compression of spinal cord by sequestrated bony fragments and disc material, granulation tissue or abscess in the spinal canal.

  20. Evaluating variability and uncertainty in radiological impact assessment using SYMBIOSE

    International Nuclear Information System (INIS)

    Simon-Cornu, M.; Beaugelin-Seiller, K.; Boyer, P.; Calmon, P.; Garcia-Sanchez, L.; Mourlon, C.; Nicoulaud, V.; Sy, M.; Gonze, M.A.

    2015-01-01

    SYMBIOSE is a modelling platform that accounts for variability and uncertainty in radiological impact assessments, when simulating the environmental fate of radionuclides and assessing doses to human populations. The default database of SYMBIOSE is partly based on parameter values that are summarized within International Atomic Energy Agency (IAEA) documents. To characterize uncertainty on the transfer parameters, 331 Probability Distribution Functions (PDFs) were defined from the summary statistics provided within the IAEA documents (i.e. sample size, minimal and maximum values, arithmetic and geometric means, standard and geometric standard deviations) and are made available as spreadsheet files. The methods used to derive the PDFs without complete data sets, but merely the summary statistics, are presented. Then, a simple case-study illustrates the use of the database in a second-order Monte Carlo calculation, separating parametric uncertainty and inter-individual variability. - Highlights: • Parametric uncertainty in radioecology was derived from IAEA documents. • 331 Probability Distribution Functions were defined for transfer parameters. • Parametric uncertainty and inter-individual variability were propagated

  1. Radiological evaluation of G-I tract diverticulum in Korean

    International Nuclear Information System (INIS)

    Sung, Ki Jun; Park, Joong Wha; Hong, In Soo; Kim, Myung Soon

    1986-01-01

    We reviewed 887 cases of esophagogram, 8863 cases of UGI series, 174 cases of small bowel series and 1926 cases of double contrast barium enema performed at the department of Radiology, Wonju College of Medicine from Jan. 1982 to Dec. 1984 to analyzed diverticular disease pattern of the GI tract in Korean. The results were as follows: 1. Esophageal diverticular. The incidence was 3.27% and the sex ratio of male to female was 2.22:1 Age distribution was relatively even and most common in 5th decade. Most of them showed single in number, above 6mm sized and common in middle one third of both lateral side of esophagus. 2. Stomach diverticular. The incidence was 0.07% and the sex ratio of male to female was equal. Multiplicity was single in all cases. Most of them were above 11mm sized and common in gastric fundic area of greater curvature site of stomach. 3. Duodenal diverticular. The incidence was 1.51% and relatively even distribution in sex and age and common in after 5th decade. Most of them showed single in number, 11-30mm sized and common in medial margin of 2nd portion of duodenum. 4. Colonic diverticular. The incidence was 2.34% and predominant in male and common in 5th. and 6th. decade. Most of them showed single in number, below 5mm sized and common in right sided colon.

  2. Radiological evaluation of G-I tract diverticulum in Korean

    Energy Technology Data Exchange (ETDEWEB)

    Sung, Ki Jun; Park, Joong Wha; Hong, In Soo; Kim, Myung Soon [Yeonsei University Wonju College of Medicine, Wonju (Korea, Republic of)

    1986-12-15

    We reviewed 887 cases of esophagogram, 8863 cases of UGI series, 174 cases of small bowel series and 1926 cases of double contrast barium enema performed at the department of Radiology, Wonju College of Medicine from Jan. 1982 to Dec. 1984 to analyzed diverticular disease pattern of the GI tract in Korean. The results were as follows: 1. Esophageal diverticular. The incidence was 3.27% and the sex ratio of male to female was 2.22:1 Age distribution was relatively even and most common in 5th decade. Most of them showed single in number, above 6mm sized and common in middle one third of both lateral side of esophagus. 2. Stomach diverticular. The incidence was 0.07% and the sex ratio of male to female was equal. Multiplicity was single in all cases. Most of them were above 11mm sized and common in gastric fundic area of greater curvature site of stomach. 3. Duodenal diverticular. The incidence was 1.51% and relatively even distribution in sex and age and common in after 5th decade. Most of them showed single in number, 11-30mm sized and common in medial margin of 2nd portion of duodenum. 4. Colonic diverticular. The incidence was 2.34% and predominant in male and common in 5th. and 6th. decade. Most of them showed single in number, below 5mm sized and common in right sided colon.

  3. Skin decontamination cream for radiological contaminants: Formulation development and evaluation.

    Science.gov (United States)

    Khan, Abdul Wadood; Kotta, Sabna; Rana, Sudha; Ansari, Shahid Husain; Sharma, Rakesh Kumar; Ali, Javed

    2013-01-01

    Increased use of the radioactive materials in the field of research, medical, nuclear power plant, and industry has increased the risk of accidental exposure. Intentional use of the radioisotopes by terrorist organizations could cause exposure/contamination of a number of the population. In view of the accidental contamination, there is a need to develop self-usable decontamination formulations that could be used immediately after contamination is suspected. Present work was planned to optimize and develop self-usable radiation decontamination cream formulation. Various pharmaceutical parameters were characterized. (99m)Tc-sodium pertechnetate was used as radiocontaminant. Static counts were recorded before and after decontamination using single photon emission computed tomography. Decontamination efficacy of the cream was found to be 42% ± 3% at 0-0.5 h after the exposure. Primary skin irritancy test was satisfactory as no erythema or edema was observed visually after 2 weeks of the formulation application. The decontamination studies proved the potential of EDTA to remove the radiological contaminants effectively.

  4. 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)

  5. 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.)

  6. 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)

  7. Safety insights from forensics evaluations at Daiichi

    Directory of Open Access Journals (Sweden)

    J. Rempe

    2017-01-01

    Information obtained from Daiichi is required to inform Decontamination and Decommissioning activities, improving the ability of the Tokyo Electric Power Company (TEPCO to characterize potential hazards and to ensure the safety of workers involved with cleanup activities. This paper reports initial results from the US Forensics Effort to utilize examination information obtained by TEPCO to enhance the safety of existing and future nuclear power plant designs. In this paper, three examples are presented in which examination information, such as visual images, dose surveys, sample evaluations, and muon tomography examinations, along with data from plant instrumentation, are used to obtain significant safety insights in the areas of component performance, fission product release and transport, debris end-state location, and combustible gas generation and transport. In addition to reducing uncertainties related to severe accident modeling progression, these insights confirm actions, such as the importance of water addition and containment venting, that are emphasized in updated guidance for severe accident prevention, mitigation, and emergency planning.

  8. The International Criticality Safety Benchmark Evaluation Project

    International Nuclear Information System (INIS)

    Briggs, B. J.; Dean, V. F.; Pesic, M. P.

    2001-01-01

    In order to properly manage the risk of a nuclear criticality accident, it is important to establish the conditions for which such an accident becomes possible for any activity involving fissile material. Only when this information is known is it possible to establish the likelihood of actually achieving such conditions. It is therefore important that criticality safety analysts have confidence in the accuracy of their calculations. Confidence in analytical results can only be gained through comparison of those results with experimental data. The Criticality Safety Benchmark Evaluation Project (CSBEP) was initiated in October of 1992 by the US Department of Energy. The project was managed through the Idaho National Engineering and Environmental Laboratory (INEEL), but involved nationally known criticality safety experts from Los Alamos National Laboratory, Lawrence Livermore National Laboratory, Savannah River Technology Center, Oak Ridge National Laboratory and the Y-12 Plant, Hanford, Argonne National Laboratory, and the Rocky Flats Plant. An International Criticality Safety Data Exchange component was added to the project during 1994 and the project became what is currently known as the International Criticality Safety Benchmark Evaluation Project (ICSBEP). Representatives from the United Kingdom, France, Japan, the Russian Federation, Hungary, Kazakhstan, Korea, Slovenia, Yugoslavia, Spain, and Israel are now participating on the project In December of 1994, the ICSBEP became an official activity of the Organization for Economic Cooperation and Development - Nuclear Energy Agency's (OECD-NEA) Nuclear Science Committee. The United States currently remains the lead country, providing most of the administrative support. The purpose of the ICSBEP is to: (1) identify and evaluate a comprehensive set of critical benchmark data; (2) verify the data, to the extent possible, by reviewing original and subsequently revised documentation, and by talking with the

  9. Software Dependability and Safety Evaluations ESA's Initiative

    Science.gov (United States)

    Hernek, M.

    ESA has allocated funds for an initiative to evaluate Dependability and Safety methods of Software. The objectives of this initiative are; · More extensive validation of Safety and Dependability techniques for Software · Provide valuable results to improve the quality of the Software thus promoting the application of Dependability and Safety methods and techniques. ESA space systems are being developed according to defined PA requirement specifications. These requirements may be implemented through various design concepts, e.g. redundancy, diversity etc. varying from project to project. Analysis methods (FMECA. FTA, HA, etc) are frequently used during requirements analysis and design activities to assure the correct implementation of system PA requirements. The criticality level of failures, functions and systems is determined and by doing that the critical sub-systems are identified, on which dependability and safety techniques are to be applied during development. Proper performance of the software development requires the development of a technical specification for the products at the beginning of the life cycle. Such technical specification comprises both functional and non-functional requirements. These non-functional requirements address characteristics of the product such as quality, dependability, safety and maintainability. Software in space systems is more and more used in critical functions. Also the trend towards more frequent use of COTS and reusable components pose new difficulties in terms of assuring reliable and safe systems. Because of this, its dependability and safety must be carefully analysed. ESA identified and documented techniques, methods and procedures to ensure that software dependability and safety requirements are specified and taken into account during the design and development of a software system and to verify/validate that the implemented software systems comply with these requirements [R1].

  10. 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

  11. Nuclear safety culture evaluation model based on SSE-CMM

    International Nuclear Information System (INIS)

    Yang Xiaohua; Liu Zhenghai; Liu Zhiming; Wan Yaping; Peng Guojian

    2012-01-01

    Safety culture, which is of great significance to establish safety objectives, characterizes level of enterprise safety production and development. Traditional safety culture evaluation models emphasis on thinking and behavior of individual and organization, and pay attention to evaluation results while ignore process. Moreover, determining evaluation indicators lacks objective evidence. A novel multidimensional safety culture evaluation model, which has scientific and completeness, is addressed by building an preliminary mapping between safety culture and SSE-CMM's (Systems Security Engineering Capability Maturity Model) process area and generic practice. The model focuses on enterprise system security engineering process evaluation and provides new ideas and scientific evidences for the study of safety culture. (authors)

  12. Evidence-based radiology: a new approach to evaluate the clinical practice of radiology; Evidenzbasierte Radiologie: Ein neuer Ansatz zur Bewertung von klinisch angewandter radiologischer Diagnostik und Therapie

    Energy Technology Data Exchange (ETDEWEB)

    Puig, S. [Univ.Klinik fuer Radiodiagnostik, Medizinische Univ. Wien (Austria); Forschungsprogramm fuer Evidenzbasierte Medizinische Diagnostik, Inst. fuer Public Health, Paracelsus Medizinische Privatuniversitaet, Salzburg (Austria); Felder-Puig, R. [Ludwig-Boltzmann-Inst. fuer Health Technology Assessment, Vienna (Austria)

    2006-07-15

    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.)

  13. 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.

  14. Radiological evaluation of intestinal obstruction in neonate and infant

    Energy Technology Data Exchange (ETDEWEB)

    Jeon, D. S.; Lim, K. Y.; Kim, S. J.; Kim, J. D.; Rhee, H. S. [Presbyterian Medical Center, Jeonju (Korea, Republic of)

    1980-12-15

    281 cases of neonatal and infantile intestinal obstruction confirmed by clinical and surgical procedure from 1975 till 1979 were reviewed radiologically. The result was as follows; 1. Intussusception was the most common cause of intestinal obstruction under one year of age (173/281: 61.56%), and other causes of descending order were infantile hypertrophic pyloric stenosis (20: 7.11%), congenital megacolon (19: 6.76%), anorectal malformation (17: 6.05%), meconium plug syndrome (17: 6.05%), hernia (12: 4.27%), band adhesion (8: 2.85%), rotation anomaly (5: 1.78%), small bowel atresia (3: 1.07%), Meckel's diverticulum (3: 1.07%), duodenal atresia (2: 0.71%), meconium ileus (1: 0.36%) and annular pancreas (1: 0.36%). Congenital type of intestinal obstruction (we classified intussusception acquired and others congenital) occupied 38.44%. 2. The ratio of male to female was 3: 1, congenital type 4.69 : 1 and acquired 2.39 : 1. 3. Vomiting, bloody stool, fever and abdominal distention were the most 4 symptoms. 4. The frequency of typical mechanical ileus pattern on plain abdomen films was 226 cases(80.43%) paralytic ileus or normal finding was 52 cases (18.51%) and pneumoperitoneum with ileus sign was 3 cases (1.06%). 5. Barium meal or enema was performed in 228 cases and narrowing or obstructed site was found in 213 cases of them (93.42%); intussusception 100% (173/173), infantile hypertrophic pyloric stenosis 93.33% (14/15) and congenital megacolon 82.35% (14/17). 6. Only 10 cases had associated disease such as Mongolism, thoracic kyphosis and scoliosis, microcolon, prematurity, ileocolic fistula, undescended testicle and hydrocele. 7. Meconium plug syndrome, duodenal atresia, small bowel atresia, mecondium ileus and annular pancreas were developed early after birth with average onset age of 3.6 days.

  15. Radiological evaluation of intestinal obstruction in neonate and infant

    International Nuclear Information System (INIS)

    Jeon, D. S.; Lim, K. Y.; Kim, S. J.; Kim, J. D.; Rhee, H. S.

    1980-01-01

    281 cases of neonatal and infantile intestinal obstruction confirmed by clinical and surgical procedure from 1975 till 1979 were reviewed radiologically. The result was as follows; 1. Intussusception was the most common cause of intestinal obstruction under one year of age (173/281: 61.56%), and other causes of descending order were infantile hypertrophic pyloric stenosis (20: 7.11%), congenital megacolon (19: 6.76%), anorectal malformation (17: 6.05%), meconium plug syndrome (17: 6.05%), hernia (12: 4.27%), band adhesion (8: 2.85%), rotation anomaly (5: 1.78%), small bowel atresia (3: 1.07%), Meckel's diverticulum (3: 1.07%), duodenal atresia (2: 0.71%), meconium ileus (1: 0.36%) and annular pancreas (1: 0.36%). Congenital type of intestinal obstruction (we classified intussusception acquired and others congenital) occupied 38.44%. 2. The ratio of male to female was 3: 1, congenital type 4.69 : 1 and acquired 2.39 : 1. 3. Vomiting, bloody stool, fever and abdominal distention were the most 4 symptoms. 4. The frequency of typical mechanical ileus pattern on plain abdomen films was 226 cases(80.43%) paralytic ileus or normal finding was 52 cases (18.51%) and pneumoperitoneum with ileus sign was 3 cases (1.06%). 5. Barium meal or enema was performed in 228 cases and narrowing or obstructed site was found in 213 cases of them (93.42%); intussusception 100% (173/173), infantile hypertrophic pyloric stenosis 93.33% (14/15) and congenital megacolon 82.35% (14/17). 6. Only 10 cases had associated disease such as Mongolism, thoracic kyphosis and scoliosis, microcolon, prematurity, ileocolic fistula, undescended testicle and hydrocele. 7. Meconium plug syndrome, duodenal atresia, small bowel atresia, mecondium ileus and annular pancreas were developed early after birth with average onset age of 3.6 days

  16. Atmospheric dispersion modeling and radiological safety analysis for a hypothetical accident of Ghana Research Reactor -1 (GHARR-1)

    International Nuclear Information System (INIS)

    Lunguya, J. M.

    2013-06-01

    This work presents the environmental impact analysis of some selected radionuclides released from the Ghana Research Reactor- 1 (GHARR-1) after a hypothetical postulated accidents scenario. The source term was identified and generated from an inventory of radioisotopes released during the accident. Atmospheric transport model was then applied to calculate the total effective dose and how it would be distributed to different organs of the human body as a function of distance downwind. All accident scenarios were selected from GHARR-1 Safety Analysis Report. After the source term was identified the MCNPX code was used to perform the core burnup/depletion analysis. The assumption was made that the activities were released to the atmosphere under a horse design basis accident scenario. The gaussian dose calculation method was applied, coded in Hotspot, a Healthy Physics computer code. This served as the computational tool to perform the atmospheric dispersion modeling and was used to calculate radionuclide concentration at downwind location. Based upon predominant meteorological conditions at the site, the adopted strategy was to use site-specific meteorological data and dispersion modeling to analyze the hypothetical release to the environment of radionuclides and evaluate to what extent such a release may have radiological effects on the public. Final data were processed and presented as Total Effective Dose Equivalent as a function of time and distance of deposition. The results indicate that all the values of Effective dose obtained are far below the regulatory limits, making the use of the reactor safe, even in the case of worst accident scenario where all the fission products were released into the atmosphere. (au)

  17. 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.

  18. 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)

  19. 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

  20. 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.

  1. EVALUATION OF THE ADA TECHNOLOGIES' ELECTRO-DECON PROCESS TO REMOVE RADIOLOGICAL CONTAMINATION

    International Nuclear Information System (INIS)

    Pao, Jenn-Hai; Demmer, Rick L.; Argyle, Mark D.; Veatch, Brad D.

    2003-01-01

    A surface decontamination system featuring the use of ADA's electrochemical process was tested and evaluated. The process can be flexibly deployed by using an electrolyte delivery system that has been demonstrated to be reliable and effective. Experimental results demonstrate the effectiveness of this system for the surface decontamination of radiologically contaminated stainless steel

  2. Radiological investigation of renovascular hypertension from IVU to digital subtraction angiography. A critical evaluation

    International Nuclear Information System (INIS)

    Amiel, M.; Froment, A.; Pinet, F.; Huguet, M.

    1986-01-01

    For the last 20 years, the value of radiology in renovascular hypertension (RVH) is well established from diagnostic and therapeutic points of view. However things are changing now due to a better appraisal of the incidence of RVH, new antihypertensive drugs, and new radiological procedures (digital angiography, percutaneous transluminal angioplasty). The approach now takes in account the mode of imaging for a better evaluation of the renal artery stenosis and costs of the proceedings as well. Finally a new strategy has been set up for RVH patients management [fr

  3. 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)

  4. Evaluation of BOR-60 operation safety

    International Nuclear Information System (INIS)

    Minakov, A.A.; Antipin, G.K.; Efimov, V.N.; Kuzin, G.G.; Eschenko, L.V.; Eschenko, S.N.

    1987-12-01

    In this communication, BOR-60 reactor operation anomalies capable to produce a dangerous overheating of the core (SDC) is examined. On bases of calculations and reactor operation experience an event tree for SDC is built. Evaluations of probable anomalies entering in the event tree and reactor parameters modifications in case of anomalies are presented. In conclusion BOR-60 agree with the sovietic nuclear safety [fr

  5. 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)

  6. 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)

  7. 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.

  8. Preliminary evaluation of the radiological quality of the water on Bikini and Eneu Islands

    International Nuclear Information System (INIS)

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

    1975-01-01

    In June of 1975 a survey was conducted to determine the residual radioactivity in the terrestrial environment on the two main islands (Eneu and Bikini) of Bikini Atoll. The objective was to evaluate the potential radiation doses that could be received by the Bikinians scheduled to return to their atoll. This report describes the radiological quality of the groundwater during June 1975 (from data obtained from water samples collected at old and new well sites on both islets) and the cistern water on Bikini island. Based on the analyses of these samples, the cistern water from Bikini Island is both chemically and radiologically acceptable as drinking water in accordance with standard limits established by the U. S. Public Health Service. On both islands the quality of the ground water varies from one site to another. At some wells both chemical and radiological quality are acceptable; at others one or both is unacceptable according to U. S. Public Health Standards

  9. Analysis and evaluation of the radiological aspects of scoliosis

    International Nuclear Information System (INIS)

    Vargas Gonzalez, Paula

    2012-01-01

    The theme of scoliosis is proposed from the radiological perspective. An extensive literature review is realized, extracting the most relevant information for research. The initiation and evolution of scoliosis has been silent, therefore, to meet this condition has been important to detect it early and opportunely, before that curvatures have progressed and become structured, forcing the surgical treatment. The timely correction of curvatures in the spine has generated significant conditions in the patient's life. The early diagnosis has been fundamental to realize an opportune treatment of orthopedic type. A great variety of congenital and developmental disorders have been evident in the spine. The causes and patterns of the abnormal curvature of the spine have been varied. Precise diagnosis of these alterations is supported on a careful clinical assessment and is aided by imaging explorations, such as conventional radiography, computed tomography, ultrasound and magnetic resonance. Imaging methods to detect scoliosis are mentioned. The measurement procedures of the angle of spine curve are determined. The classification of scoliosis according to King-Lenke are cited to facilitate objective assessment of a disease for examiners, making that the results are presented in shape uniform and comparable possible. The types of scoliosis are explained. The characterization of the deformities of the axis of the spine, quantification and estimation of the degree of skeletal maturity has been the principal objective of the spine radiography. In an radiography has been important to be included all the thoracolumbar spine from C7. The Cobb and Ferguson measurements are used to measure angles, Risser for skeletal maturation, Nas and Moe for vertical rotation. Congenital deformities should be taken into account in radiographs of spine. Each vertebra is examined minutely in search of malformations of fusion, etc., that explain scoliosis. In neurological disorders, to take

  10. Safety evaluation of cation-exchange resins

    International Nuclear Information System (INIS)

    Kalkwarf, D.R.

    1977-08-01

    Results are presented of a study to evaluate whether sufficient information is available to establish conservative limits for the safe use of cation-exchange resins in separating radionuclides and, if not, to recommend what new data should be acquired. The study was also an attempt to identify in-line analytical techniques for the evaluation of resin degradation during radionuclide processing. The report is based upon a review of the published literature and upon discussions with many people engaged in the use of these resins. It was concluded that the chief hazard in the use of cation-exchange resins for separating radionuclides is a thermal explosion if nitric acid or other strong oxidants are present in the process solution. Thermal explosions can be avoided by limiting process parameters so that the rates of heat and gas generation in the system do not exceed the rates for their transfer to the surroundings. Such parameters include temperature, oxidant concentration, the amounts of possible catalysts, the radiation dose absorbed by the resin and the diameter of the resin column. Current information is not sufficient to define safe upper limits for these parameters. They can be evaluated, however, from equations derived from the Frank-Kamenetskii theory of thermal explosions provided the heat capacities, thermal conductivities and rates of heat evolution in the relevant resin-oxidant mixtures are known. It is recommended that such measurements be made and the appropriate limits be evaluated. A list of additional safety precautions are also presented to aid in the application of these limits and to provide additional margins of safety. In-line evaluation of resin degradation to assess its safety hazard is considered impractical. Rather, it is recommended that the resin be removed from use before it has received the limiting radiation dose, evaluated as described above

  11. 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

  12. 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...

  13. Multinational Design Evaluation Programme (MDEP) - Safety Goals

    International Nuclear Information System (INIS)

    Vaughan, G.J.

    2011-01-01

    One of the aims of the NEA's Multinational Design Evaluation Programme (MDEP) is to work towards greater harmonisation of regulatory requirements. To achieve this aim, it is necessary that there is a degree of convergence on the safety goals that are required to be met by designers and operators. The term 'safety goals' is defined to cover all health and safety requirements which must be met: these may be deterministic rules and/or probabilistic targets. They should cover the safety of workers, public and the environment in line with the IAEA's Basic Safety Objective; encompassing safety in normal operation through to severe accidents. MDEP is also interested in how its work can be extended to future reactors, which may use significantly different technology to the almost ubiquitous LWRs used today and in the next generation, building on the close co-operation within MDEP between the regulators who are currently engaged in constructing or carrying out design reviews on new designs. For two designs this work has involved several regulators sharing their safety assessments and in some cases issuing statements on issues that need to be addressed. Work is also progressing towards joint regulatory position statements on specific assessment areas. Harmonisation of safety goals will enhance the cooperation between regulators as further developments in design and technology occur. All regulators have safety goals, but these are expressed in many different ways and exercises in comparing them frequently are done at a very low level eg specific temperatures in the reactor vessel of a specific reactor type. The differences in the requirements from different regulators are difficult to resolve as the goals are derived using different principles and assumptions and are often for a specific technology. Therefore a different approach is being investigated, starting with the top-level safety goals and try to derive a structure and means of deriving lower tier

  14. 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)

  15. The responsible for the radiological safety in the industry. Between the environment work and the technology

    International Nuclear Information System (INIS)

    Truppa, Walter Adrian

    2005-01-01

    Within the industrial applications of sealed radioactive sources, there are two clearly defined branches for which these materials are used: radioactive sources used in fixed and mobile equipment. These devices are used in a myriad of applications and each time with more technological advanced systems. This requires a permanent improvement on the training of the responsible, and introduces a mandatory exchange to other groups of intervention during the useful life of the device. Accident risks during the use of the equipment, although its rate of occurrence is low, are related to mistakes during operation, improper use, maintenance performed by staff without knowledge, human failures or oversights and incidents occurring during transport. All these risks are surrounded by different groups of factors that influence during the safe use of radioactive material within the installation. So, it is evidenced the importance of implementing aspects of the 'Safety Culture' and evaluations of suitability of the person responsible for radiation safety. In this paper we will refer to all the concepts that surround the election of the head of radioactive material, the factors involved during the operation, their training, the obligations of the installation, and responsible for environment and the technology

  16. A probabilistic bridge safety evaluation against floods.

    Science.gov (United States)

    Liao, Kuo-Wei; Muto, Yasunori; Chen, Wei-Lun; Wu, Bang-Ho

    2016-01-01

    To further capture the influences of uncertain factors on river bridge safety evaluation, a probabilistic approach is adopted. Because this is a systematic and nonlinear problem, MPP-based reliability analyses are not suitable. A sampling approach such as a Monte Carlo simulation (MCS) or importance sampling is often adopted. To enhance the efficiency of the sampling approach, this study utilizes Bayesian least squares support vector machines to construct a response surface followed by an MCS, providing a more precise safety index. Although there are several factors impacting the flood-resistant reliability of a bridge, previous experiences and studies show that the reliability of the bridge itself plays a key role. Thus, the goal of this study is to analyze the system reliability of a selected bridge that includes five limit states. The random variables considered here include the water surface elevation, water velocity, local scour depth, soil property and wind load. Because the first three variables are deeply affected by river hydraulics, a probabilistic HEC-RAS-based simulation is performed to capture the uncertainties in those random variables. The accuracy and variation of our solutions are confirmed by a direct MCS to ensure the applicability of the proposed approach. The results of a numerical example indicate that the proposed approach can efficiently provide an accurate bridge safety evaluation and maintain satisfactory variation.

  17. Environmental Health Impacts of Nuclear Fuel Cycle With Emphasis to Monitoring and Radiological Safety Control System

    International Nuclear Information System (INIS)

    Gad Allah, A.A.; El- Shanshory, A.I.

    2010-01-01

    facilities, as well as their health impacts instruments and monitors systems for radiological control have been reviewed and evaluated

  18. Application gives the technique the analytic tree in the evaluation the effectiveness programs to radiological protection

    International Nuclear Information System (INIS)

    Perez Gonzalez, F.; Perez Velazquez, R.S.; Fornet Rodriguez, O.; Mustelier Hechevarria, A.; Miller Clemente, A.

    1998-01-01

    In the work we develop the IAEA recommendations in the application the analytic tree as instrument for the evaluation the effectiveness the occupational radiological protection programs. Is reflected like it has been assimilated and converted that technique in daily work istruments in the evaluation process the security conditions in the institutions that apply the nuclear techniques with a view to its autorization on the part of the regulatory organ

  19. Injuries of the spine: Current concepts of radiological evaluation

    International Nuclear Information System (INIS)

    Du Mesnil de Rochemont, R.; Lanfermann, H.; Heindel, W.

    1997-01-01

    This review discusses the usefulness of plain radiography, computed tomography (CT), and magnetic resonance imaging (MRI) in the evaluation of spinal trauma. The indications for the different imaging modalities in dependence on the specific pattern of injury are explored. Plain radiography still remains the prime method in the diagnosis of acute spinal trauma but there are substantial deficits, especially in the evaluation of the occipitocervical and the cervicothoracic junction as well as in the evaluation of the integrity of posterior vertebral body line. If injury in these regions is suspected CT should follow plain radiography immediately. In the case of spinal trauma with unexplained neurologic deficits MRI is the method of choice for the detection of spinal cord injury. Recommendations with regard to instability and the classification of specific injuries, including examples of typical findings are presented. (orig.) [de

  20. Barrier performance researches for the safety evaluation

    International Nuclear Information System (INIS)

    Niibori, Yuichi

    2004-01-01

    So far, many researches were conducted to propose a scientific evidence (a safety case) for the realization of geological disposal in Japan. In order to regulate the geological disposal system of radioactive wastes, on the other hand, we need also a holistic approach to integrate various data related for the performance evaluations of the engineered barrier system and the natural barrier system. However, the scientific bases are not sufficient to establish the safety regulation for such a natural system. For example, we often apply the specific probability density function (PDF) to the uncertainty of barrier system due to the essential heterogeneity. However, the applicability is not clear in the regulation point of view. A viewpoint to understand such an applicability of PDFs has been presented. (author)

  1. A cascade method of training for the revised CEGB Radiological Safety Rules and the Ionising Radiations Regulations 1985

    International Nuclear Information System (INIS)

    Jackson, J.R.; John, P.G.L.

    1986-01-01

    In order to achieve compliance with the Ionising Radiations Regulations 1985 the CEGB has introduced a revised set of Radiological Safety Rule. These Rules are for implementation at all sites under the Board's control where ionising radiations are used. It was a requirement that the new Safety Rules be brought into operation on a common date and to a consistent standard of performance throughout the industry; this necessitated a considerable training programme to familiarise and inform some 8,000 staff working at a large number of locations. The training week of identified groups of staff varied widely, according to their different levels of authority and responsibility. The paper sets out the means by which the chosen cascade method of training was selected and developed, and gives details of the modular package of training material which was produced. It also relates how the management objectives were met within the constraints of an uncompromising time schedule. (author)

  2. 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.)

  3. 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.)

  4. Evaluation process radiological in ternopil region method of box models

    Directory of Open Access Journals (Sweden)

    І.В. Матвєєва

    2006-02-01

    Full Text Available  Results of radionuclides Sr-90 flows analyses in the ecosystem of Kotsubinchiky village of Ternopolskaya oblast were analyzed. The block-scheme of ecosystem and its mathematical model using the box models method were made. It allowed us to evaluate the ways of dose’s loadings formation of internal irradiation for miscellaneous population groups – working people, retirees, children, and also to prognose the dynamic of these loadings during the years after the Chernobyl accident.

  5. Radiological evaluation of esophageal speech on total laryngectomee

    International Nuclear Information System (INIS)

    Chung, Tae Sub; Suh, Jung Ho; Kim, Dong Ik; Kim, Gwi Eon; Hong, Won Phy; Lee, Won Sang

    1988-01-01

    Total laryngectomee requires some form of alaryngeal speech for communication. Generally, esophageal speech is regarded as the most available and comfortable technique for alaryngeal speech. But esophageal speech is difficult to train, so many patients are unable to attain esophageal speech for communication. To understand mechanism of esophageal of esophageal speech on total laryngectomee, evaluation of anatomical change of the pharyngoesophageal segment is very important. We used video fluoroscopy for evaluation of pharyngesophageal segment during esophageal speech. Eighteen total laryngectomees were evaluated with video fluoroscopy from Dec. 1986 to May 1987 at Y.U.M.C. Our results were as follows: 1. Peseudoglottis is the most important factor for esophageal speech, which is visualized in 7 cases among 8 cases of excellent esophageal speech group. 2. Two cases of longer A-P diameter at the pseudoglottis have the best quality of esophageal speech than others. 3. Two cases of mucosal vibration at the pharyngoesophageal segment can make excellent esophageal speech. 4. The cases of failed esophageal speech are poor aerophagia in 6 cases, abscence of pseudoglottis in 4 cases and poor air ejection in 3 cases. 5. Aerophagia synchronizes with diaphragmatic motion in 8 cases of excellent esophageal speech.

  6. Evaluation of radiology as a tool to diagnose pulmonic lesions in calves, for example prior to experimental infection studies

    DEFF Research Database (Denmark)

    Tegtmeier, Conny; Arnbjerg, J.

    2000-01-01

    The aim of the study was to evaluate radiology as a technique to visualize pulmonary lesions in young calves, e.g. as a selection criterion for research animals in order to eliminate animals with lung lesions Drier to experimental studies of pneumonia. Five calves with acute clinical signs...... of pneumonia were included in a direct comparative study of radiological and post mortem findings. Also, a number of animals with no signs of pneumonia were included as controls. The study revealed good agreement between the radiological and post mortem findings. Thus, in conclusion, radiology should...

  7. Usability evaluation of Laboratory and Radiology Information Systems integrated into a hospital information system.

    Science.gov (United States)

    Nabovati, Ehsan; Vakili-Arki, Hasan; Eslami, Saeid; Khajouei, Reza

    2014-04-01

    This study was conducted to evaluate the usability of widely used laboratory and radiology information systems. Three usability experts independently evaluated the user interfaces of Laboratory and Radiology Information Systems using heuristic evaluation method. They applied Nielsen's heuristics to identify and classify usability problems and Nielsen's severity rating to judge their severity. Overall, 116 unique heuristic violations were identified as usability problems. In terms of severity, 67 % of problems were rated as major and catastrophic. Among 10 heuristics, "consistency and standards" was violated most frequently. Moreover, mean severity of problems concerning "error prevention" and "help and documentation" heuristics was higher than of the others. Despite widespread use of specific healthcare information systems, they suffer from usability problems. Improving the usability of systems by following existing design standards and principles from the early phased of system development life cycle is recommended. Especially, it is recommended that the designers design systems that inhibit the initiation of erroneous actions and provide sufficient guidance to users.

  8. Radiologic evaluation of the horse relevant to purchase

    International Nuclear Information System (INIS)

    Poulos, P.W. Jr.

    1992-01-01

    Adequate radiographic evaluation of the horse relevant to purchase examination requires the successful integration of technique, interpretation, and reporting. A thorough knowledge of lameness and disease can be masked by incorrect interpretation resulting from poor-quality films or an incomplete examination. Thus, care must be taken to produce an adequate number of high-quality films on which to base a report, which allows you to describe changes that are present. This information, coupled with your physical examination, other laboratory data, and the knowledge of the expressed use of the horse will allow you to advise prospective owners on the decision that they will ultimately make

  9. Radiologic and histopathologic evaluation of various contrast media for bronchography

    International Nuclear Information System (INIS)

    Kang, Eun Young; Hong, Ki Taek; Kim, Jin Hyung; Kim, Hyung Rae; Shin, Bong Kyung; Oh, Yu Whan; Kim, Han Kyeom; Park, Cheol Min; Seol, Hae Young; Cha, In Ho

    1999-01-01

    To determine which contrast media are both efficient and safe for the imaging of airways. We evaluated five contrast media (barium, gastrografin, iotrolan, ioxaglate, iopentol) in terms of image quality and their effects on the lungs of 25 white rabbits. For bronchography 0.5ml of contrast media was used. In each contrast group, HRCT scans were obtained immediately (n=5), 12 hours (n=4), 1 day (n=3), 2 days (n=2), and 1 week (n=1) after bronchography. Histopathologic specimens were obtained immediately, 12 hours, 1 day, 2 days, and 1 week later. Bronchograms were evaluated for image quality by three radiologists working independently, and were scored as 1(poor), 2(moderate), or 3(good) in terms of contrast quality and bronchial coating. HRCT was evaluated by two radiologists who reached a concensus;they determined the presence of contrast media, and then the pattern and extent of pulmonary opacity, and any related changes. Histopatholgic specimens were evaluated by two pathologists who sought consensus as to the extent of inflammation, pulmonary edema, and hemorrhage, and any changes in these aspects. Bronchography indicated that the sum of scores for contrast quality was 45 for barium, 33 for gastrografin, 28 for iotrolan, 30 for ioxaglate, and 28 for iopentol, while for each of these media, the sum of scores for bronchial coating was 39, 19, 25, 23, and 21, respectively. Barium showed the best image quality. In all rabbits, HRCT demonstrated the variable extent of ground-glass attenuation and/or consolidation. Lesions were most extensive at 1-2days and then regressed at 1 week;these HRCT findings correlated well with histologic findings. In histologic studies of all five contrast media groups, variable severe inflammatory reactions were observed, with or without necrosis, congesion, edema, and hemorrhage. It was noted that ioxaglate appeared to cause least tissue reaction. The imaging results of this experimental study indicate that for bronchography, barium is

  10. Safety evaluation for packaging (onsite) SERF cask

    International Nuclear Information System (INIS)

    Edwards, W.S.

    1997-01-01

    This safety evaluation for packaging (SEP) documents the ability of the Special Environmental Radiometallurgy Facility (SERF) Cask to meet the requirements of WHC-CM-2-14, Hazardous Material Packaging and Shipping, for transfer of Type B quantities (up to highway route controlled quantities) of radioactive material within the 300 Area of the Hanford Site. This document shall be used to ensure that loading, tie down, transport, and unloading of the SERF Cask are performed in accordance with WHC-CM-2-14. This SEP is valid until October 1, 1999. After this date, an update or upgrade to this document is required

  11. Safety evaluation for packaging CPC metal boxes

    International Nuclear Information System (INIS)

    Romano, T.

    1995-01-01

    This Safety Evaluation for Packaging (SEP) provides authorization for the use of Container Products Corporation (CPC) metal boxes, as described in this document, for the interarea shipment of radioactive contaminated equipment and debris for storage in the Central Waste Complex (CWC) or T Plant located in the 200 West Area. Authorization is granted until November 30, 1995. The CPC boxes included in this SEP were originally procured as US Department of Transportation (DOT) Specification 7A Type A boxes. A review of the documentation provided by the manufacturer revealed the documentation did not adequately demonstrate compliance to the 4 ft drop test requirement of 49 CFR 173.465(c). Preparation of a SEP is necessary to document the equivalent safety of the onsite shipment in lieu of meeting DOT packaging requirements until adequate documentation is received. The equivalent safety of the shipment is based on the fact that the radioactive contents consist of contaminated equipment and debris which are not dispersible. Each piece is wrapped in two layers of no less than 4 mil plastic prior to being placed in the box which has an additional 10 mil liner. Pointed objects and sharp edges are padded to prevent puncture of the plastic liner and wrapping

  12. Radiological controls and worker and public health and safety: An independent safety assessment of Department of Energy nuclear reactor facilities

    International Nuclear Information System (INIS)

    Tew, J.L.; Miles, M.E.; Knuth, D.; Boyd, R.

    1981-02-01

    DOE has formed a Nuclear Facilities Personnel Qualification and Training (NFPQT) Committee to assess the implications of the Report of the President's Commission on the Accident at Three Mile Island that are applicable to DOE's nuclear reactor operations. Thirteen DOE nuclear reactors were reviewed by the Committee. This report was prepared to provide a measure of how the radiological control and environmental practices at the 13 individual DOE reactor facilities measure up to (1) the recommendations contained in the Report of the President's Commission on the Accident at Three Mile Island, (2) the requirements and guidelines contained, and (3) the requirements of the applicable Title and Part of the Code of Federal Regulations

  13. 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

  14. 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

  15. Preliminary safety evaluation for CSR1000 with passive safety system

    International Nuclear Information System (INIS)

    Wu, Pan; Gou, Junli; Shan, Jianqiang; Zhang, Bo; Li, Xiang

    2014-01-01

    Highlights: • The basic information of a Chinese SCWR concept CSR1000 is introduced. • An innovative passive safety system is proposed for CSR1000. • 6 Transients and 3 accidents are analysed with system code SCTRAN. • The passive safety systems greatly mitigate the consequences of these incidents. • The inherent safety of CSR1000 is enhanced. - Abstract: This paper describes the preliminary safety analysis of the Chinese Supercritical water cooled Reactor (CSR1000), which is proposed by Nuclear Power Institute of China (NPIC). The two-pass core design applied to CSR1000 decreases the fuel cladding temperature and flattens the power distribution of the core at normal operation condition. Each fuel assembly is made up of four sub-assemblies with downward-flow water rods, which is favorable to the core cooling during abnormal conditions due to the large water inventory of the water rods. Additionally, a passive safety system is proposed for CSR1000 to increase the safety reliability at abnormal conditions. In this paper, accidents of “pump seizure”, “loss of coolant flow accidents (LOFA)”, “core depressurization”, as well as some typical transients are analysed with code SCTRAN, which is a one-dimensional safety analysis code for SCWRs. The results indicate that the maximum cladding surface temperatures (MCST), which is the most important safety criterion, of the both passes in the mentioned incidents are all below the safety criterion by a large margin. The sensitivity analyses of the delay time of RCPs trip in “loss of offsite power” and the delay time of RMT actuation in “loss of coolant flowrate” were also included in this paper. The analyses have shown that the core design of CSR1000 is feasible and the proposed passive safety system is capable of mitigating the consequences of the selected abnormalities

  16. Specialized consultant in radiological safety to the Salamanca regional hospital, PEMEX. III. - September 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

    The Salamanca regional hospital, dependent of PEMEX, It request consultant of the ININ to be able to maintain their sanitary license for the use of X-ray equipment for the radiologic diagnostic.The proposal of the ININ was to be a program of technical attendance, schedule monthly to be able to solve the observations that are presented in the use of those equipment, and that the hospital can conserve its respective sanitary license.(Author)

  17. Specialized consultant in radiological safety to the Tula general hospital, 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

    The Tula general hospital, dependent of PEMEX, It request consultant of the ININ to be able to maintain their sanitary license for the use of X-ray equipment for the radiologic diagnostic.The proposal of the ININ was to be a program of technical attendance, schedule monthly to be able to solve the observations that are presented in the use of those equipment, and that the hospital can conserve its respective sanitary license.(Author)

  18. Specialized consultant in radiological safety to the Tula general hospital, PEMEX. IV. - October 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

    The Tula general hospital, dependent of PEMEX, It request consultant of the ININ to be able to maintain their sanitary license for the use of X-ray equipment for the radiologic diagnostic.The proposal of the ININ was to be a program of technical attendance, schedule monthly to be able to solve the observations that are presented in the use of those equipment, and that the hospital can conserve its respective sanitary license.(Author)

  19. Specialized consultant in radiological safety to the Ciudad del Carmen general hospital, PEMEX

    International Nuclear Information System (INIS)

    Angeles C, A.; Hernandez C, J. E.; Rodriguez A, F.; Garcia A, J.

    2003-02-01

    The Ciudad del Carmen general hospital, dependent of PEMEX, It request consultant of the ININ to be able to maintain their sanitary license for the use of X-ray equipment for the radiologic diagnostic.The proposal of the ININ was to be a program of technical attendance, schedule monthly to be able to solve the observations that are presented in the use of those equipment, and that the hospital can conserve its respective sanitary license.(Author)

  20. Specialized consultant in radiological safety to the Salamanca regional hospital, 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

    The Salamanca regional hospital, dependent of PEMEX, It request consultant of the ININ to be able to maintain their sanitary license for the use of X-ray equipment for the radiologic diagnostic.The proposal of the ININ was to be a program of technical attendance, schedule monthly to be able to solve the observations that are presented in the use of those equipment, and that the hospital can conserve its respective sanitary license.(Author)