Transdermal nicotine absorption handling e-cigarette refill liquids.

Science.gov (United States)

Maina, Giovanni; Castagnoli, Carlotta; Passini, Valter; Crosera, Matteo; Adami, Gianpiero; Mauro, Marcella; Filon, Francesca Larese

2016-02-01

The concentrated nicotine in e-cigarette refill liquids can be toxic if inadvertently ingested or absorbed through the skin. Reports of poisonings due to accidental ingestion of nicotine on refill liquids are rapidly increasing, while the evaluation of nicotine dermally absorbed still lacks. For that reason we studied transdermal nicotine absorption after the skin contamination with e-liquid. Donor chambers of eight Franz diffusion cells were filled with 1 mL of 0.8 mg/mL nicotine e-liquid for 24 h. The concentration of nicotine in the receiving phase was determined by high-performance liquid chromatography (LOD:0.1 μg/mL). Nicotine was detectable in receiving solution 2 h after the start of exposure and increased progressively. The medium flux calculated was 4.82 ± 1.05 μg/cm(2)/h with a lag time of 3.9 ± 0.1 h. After 24 h, the nicotine concentration in the receiving compartment was 101.02 ± 22.35 μg/cm(2) corresponding to 3.04 mg of absorbed nicotine after contamination of a skin surface of 100 cm(2). Skin contamination with e-liquid can cause nicotine skin absorption: caution must be paid when handling refill e-liquids. Copyright © 2015 Elsevier Inc. All rights reserved.

Handling of overexposed persons in radiological emergencies

International Nuclear Information System (INIS)

Estrada, E.

2000-01-01

The purpose of this standard procedure of the criteria in case of radiological emergencies is to describe the standard procedures used to define an radiological accident in terms of the doses received, and to describe the medical procedures for diagnoses and treatment of health hazards caused by external and internal irradiation in radiological emergencies

Pediatric radiology for medical-technical radiology assistants/radiologists

International Nuclear Information System (INIS)

Oppelt, Birgit

2010-01-01

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

EvoBot: An Open-Source, Modular Liquid Handling Robot for Nurturing Microbial Fuel Cells

DEFF Research Database (Denmark)

Faina, Andres; Nejatimoharrami, Farzad; Støy, Kasper

2016-01-01

makes it difficult to apply conventional liquid handling robots as they are designed to automate a predefined task. In order to address these issues, we have developed an open source liquid handling robot, EvoBot. It uses a modular approach, which gives us the possibility to reconfigure the robot...... for different experiments and make it possible for users to add functionality by just developing a function specific module. In addition, it provides sensors and extra functionality for monitoring an experiment, which allows researchers to perform interactive experiments with the aim of prolonging non...

Assessment of SRS radiological liquid and airborne contaminants and pathways

International Nuclear Information System (INIS)

Jannik, G.T.

1997-04-01

This report compiles and documents the radiological critical-contaminant/critical-pathway analysis performed for SRS. The analysis covers radiological releases to the atmosphere and to surface water, which are the principal media that carry contaminants off site. During routine operations at SRS, limited amounts of radionuclides are released to the environment through atmospheric and/or liquid pathways. These releases potentially result in exposure to offsite people. Though the groundwater beneath an estimated 5 to 10 percent of SRS has been contaminated by radionuclides, there is no evidence that groundwater contaminated with these constituents has migrated offsite (Arnett, 1996). Therefore, with the notable exception of radiological source terms originating from shallow surface water migration into site streams, onsite groundwater was not considered as a potential exposure pathway to offsite people

Anticipated Radiological Dose to Worker for Plutonium Stabilization and Handling at PFP - Project W-460

International Nuclear Information System (INIS)

WEISS, E.V.

2000-01-01

This report provides estimates of the expected whole body and extremity radiological dose, expressed as dose equivalent (DE), to workers conducting planned plutonium (Pu) stabilization processes at the Hanford Site Plutonium Finishing Plant (PFP). The report is based on a time and motion dose study commissioned for Project W-460, Plutonium Stabilization and Handling, to provide personnel exposure estimates for construction work in the PFP storage vault area plus operation of stabilization and packaging equipment at PFP

Anticipated Radiological Dose to Worker for Plutonium Stabilization and Handling at PFP - Project W-460

CERN Document Server

Weiss, E V

2000-01-01

This report provides estimates of the expected whole body and extremity radiological dose, expressed as dose equivalent (DE), to workers conducting planned plutonium (Pu) stabilization processes at the Hanford Site Plutonium Finishing Plant (PFP). The report is based on a time and motion dose study commissioned for Project W-460, Plutonium Stabilization and Handling, to provide personnel exposure estimates for construction work in the PFP storage vault area plus operation of stabilization and packaging equipment at PFP.

Safety in handling of cryogenic substance (liquid N2) and regulatory aspects

International Nuclear Information System (INIS)

Sharma, M.L.

2009-01-01

Liquid N 2 is at - 196 deg C may cause cold burning and if being used in a confined area/space upon spill can increase N 2 concentration in the environment and deplete O 2 , hence cause danger to the lives of the occupants if not rescued and evacuated from that area. In view of the this danger/unsafe condition while handling liquid N 2 , safety concerns are discussed in detail

Automated Planning Enables Complex Protocols on Liquid-Handling Robots.

Science.gov (United States)

Whitehead, Ellis; Rudolf, Fabian; Kaltenbach, Hans-Michael; Stelling, Jörg

2018-03-16

Robotic automation in synthetic biology is especially relevant for liquid handling to facilitate complex experiments. However, research tasks that are not highly standardized are still rarely automated in practice. Two main reasons for this are the substantial investments required to translate molecular biological protocols into robot programs, and the fact that the resulting programs are often too specific to be easily reused and shared. Recent developments of standardized protocols and dedicated programming languages for liquid-handling operations addressed some aspects of ease-of-use and portability of protocols. However, either they focus on simplicity, at the expense of enabling complex protocols, or they entail detailed programming, with corresponding skills and efforts required from the users. To reconcile these trade-offs, we developed Roboliq, a software system that uses artificial intelligence (AI) methods to integrate (i) generic formal, yet intuitive, protocol descriptions, (ii) complete, but usually hidden, programming capabilities, and (iii) user-system interactions to automatically generate executable, optimized robot programs. Roboliq also enables high-level specifications of complex tasks with conditional execution. To demonstrate the system's benefits for experiments that are difficult to perform manually because of their complexity, duration, or time-critical nature, we present three proof-of-principle applications for the reproducible, quantitative characterization of GFP variants.

Liquid-handling Lego robots and experiments for STEM education and research.

Directory of Open Access Journals (Sweden)

Lukas C Gerber

2017-03-01

Full Text Available Liquid-handling robots have many applications for biotechnology and the life sciences, with increasing impact on everyday life. While playful robotics such as Lego Mindstorms significantly support education initiatives in mechatronics and programming, equivalent connections to the life sciences do not currently exist. To close this gap, we developed Lego-based pipetting robots that reliably handle liquid volumes from 1 ml down to the sub-μl range and that operate on standard laboratory plasticware, such as cuvettes and multiwell plates. These robots can support a range of science and chemistry experiments for education and even research. Using standard, low-cost household consumables, programming pipetting routines, and modifying robot designs, we enabled a rich activity space. We successfully tested these activities in afterschool settings with elementary, middle, and high school students. The simplest robot can be directly built from the widely used Lego Education EV3 core set alone, and this publication includes building and experiment instructions to set the stage for dissemination and further development in education and research.

Liquid-handling Lego robots and experiments for STEM education and research.

Science.gov (United States)

Gerber, Lukas C; Calasanz-Kaiser, Agnes; Hyman, Luke; Voitiuk, Kateryna; Patil, Uday; Riedel-Kruse, Ingmar H

2017-03-01

Liquid-handling robots have many applications for biotechnology and the life sciences, with increasing impact on everyday life. While playful robotics such as Lego Mindstorms significantly support education initiatives in mechatronics and programming, equivalent connections to the life sciences do not currently exist. To close this gap, we developed Lego-based pipetting robots that reliably handle liquid volumes from 1 ml down to the sub-μl range and that operate on standard laboratory plasticware, such as cuvettes and multiwell plates. These robots can support a range of science and chemistry experiments for education and even research. Using standard, low-cost household consumables, programming pipetting routines, and modifying robot designs, we enabled a rich activity space. We successfully tested these activities in afterschool settings with elementary, middle, and high school students. The simplest robot can be directly built from the widely used Lego Education EV3 core set alone, and this publication includes building and experiment instructions to set the stage for dissemination and further development in education and research.

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)

Some information about the radiological protection concerning the TRIGA spent fuel handling at the Medical University of Hanover

International Nuclear Information System (INIS)

Hampel, Gabriele; Harke, Heinrich; Klaus, Uwe; Loercher, Gunther

2008-01-01

The Medical University of Hanover (MHH) returned its 76 spent TRIGA fuel elements to the United States in summer of 1999. For the transportation inside the MHH control areas were installed outside the reactor area, along the transfer route in the department of nuclear medicine and in the temporary building. During fuel handling at MHH a lot of radiation protection measures were necessary. This paper presents methods and results of the radiological protection measurements. (authors)

Efficient handling of high-level radioactive cell waste in a vitrification facility analytical laboratory

International Nuclear Information System (INIS)

Roberts, D.W.; Collins, K.J.

1998-01-01

The Savannah River Site''s (SRS) Defense Waste Processing Facility (DWPF) near Aiken, South Carolina, is the world''s largest and the United State''s first high level waste vitrification facility. For the past 1.5 years, DWPF has been vitrifying high level radioactive liquid waste left over from the Cold War. The vitrification process involves the stabilization of high level radioactive liquid waste into borosilicate glass. The glass is contained in stainless steel canisters. DWPF has filled more than 200 canisters 3.05 meters (10 feet) long and 0.61 meters (2 foot) diameter. Since operations began at DWPF in March of 1996, high level radioactive solid waste continues to be generated due to operating the facility''s analytical laboratory. The waste is referred to as cell waste and is routinely removed from the analytical laboratories. Through facility design, engineering controls, and administrative controls, DWPF has established efficient methods of handling the high level waste generated in its laboratory facility. These methods have resulted in the prevention of undue radiation exposure, wasted man-hours, expenses due to waste disposal, and the spread of contamination. This level of efficiency was not reached overnight, but it involved the collaboration of Radiological Control Operations and Laboratory personnel working together to devise methods that best benefited the facility. This paper discusses the methods that have been incorporated at DWPF for the handling of cell waste. The objective of this paper is to provide insight to good radiological and safety practices that were incorporated to handle high level radioactive waste in a laboratory setting

Worklist handling in workflow-enabled radiological application systems

Science.gov (United States)

Wendler, Thomas; Meetz, Kirsten; Schmidt, Joachim; von Berg, Jens

2000-05-01

For the next generation integrated information systems for health care applications, more emphasis has to be put on systems which, by design, support the reduction of cost, the increase inefficiency and the improvement of the quality of services. A substantial contribution to this will be the modeling. optimization, automation and enactment of processes in health care institutions. One of the perceived key success factors for the system integration of processes will be the application of workflow management, with workflow management systems as key technology components. In this paper we address workflow management in radiology. We focus on an important aspect of workflow management, the generation and handling of worklists, which provide workflow participants automatically with work items that reflect tasks to be performed. The display of worklists and the functions associated with work items are the visible part for the end-users of an information system using a workflow management approach. Appropriate worklist design and implementation will influence user friendliness of a system and will largely influence work efficiency. Technically, in current imaging department information system environments (modality-PACS-RIS installations), a data-driven approach has been taken: Worklist -- if present at all -- are generated from filtered views on application data bases. In a future workflow-based approach, worklists will be generated by autonomous workflow services based on explicit process models and organizational models. This process-oriented approach will provide us with an integral view of entire health care processes or sub- processes. The paper describes the basic mechanisms of this approach and summarizes its benefits.

In situ radiological characterization to support a test excavation at a liquid waste disposal site

International Nuclear Information System (INIS)

Keele, B.D.; Bauer, R.G.; Blewett, G.R.; Troyer, G.L.

1994-05-01

An in situ radiological detection system was developed to support a small test excavation at a liquid waste disposal site at the Hanford Site in Richland, Washington. Instrumentation, calibration and comparisons to samples are discussed

Determination of action zone in the nuclear / radiology handling process

International Nuclear Information System (INIS)

Ade Awalludin

2013-01-01

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

Nuclear fuel handling apparatus

International Nuclear Information System (INIS)

Andrea, C.; Dupen, C.F.G.; Noyes, R.C.

1977-01-01

A fuel handling machine for a liquid metal cooled nuclear reactor in which a retractable handling tube and gripper are lowered into the reactor to withdraw a spent fuel assembly into the handling tube. The handling tube containing the fuel assembly immersed in liquid sodium is then withdrawn completely from the reactor into the outer barrel of the handling machine. The machine is then used to transport the spent fuel assembly directly to a remotely located decay tank. The fuel handling machine includes a decay heat removal system which continuously removes heat from the interior of the handling tube and which is capable of operating at its full cooling capacity at all times. The handling tube is supported in the machine from an articulated joint which enables it to readily align itself with the correct position in the core. An emergency sodium supply is carried directly by the machine to provide make up in the event of a loss of sodium from the handling tube during transport to the decay tank. 5 claims, 32 drawing figures

Flexible automated approach for quantitative liquid handling of complex biological samples.

Science.gov (United States)

Palandra, Joe; Weller, David; Hudson, Gary; Li, Jeff; Osgood, Sarah; Hudson, Emily; Zhong, Min; Buchholz, Lisa; Cohen, Lucinda H

2007-11-01

A fully automated protein precipitation technique for biological sample preparation has been developed for the quantitation of drugs in various biological matrixes. All liquid handling during sample preparation was automated using a Hamilton MicroLab Star Robotic workstation, which included the preparation of standards and controls from a Watson laboratory information management system generated work list, shaking of 96-well plates, and vacuum application. Processing time is less than 30 s per sample or approximately 45 min per 96-well plate, which is then immediately ready for injection onto an LC-MS/MS system. An overview of the process workflow is discussed, including the software development. Validation data are also provided, including specific liquid class data as well as comparative data of automated vs manual preparation using both quality controls and actual sample data. The efficiencies gained from this automated approach are described.

The handling, hazards, and maintenance of heavy liquids in the geologic laboratory

Science.gov (United States)

Hauff, Phoebe L.; Airey, Joseph

1980-01-01

In geologic laboratories the organic heavy liquids bromoform, methylene iodide, tetrabromoethane, and clerici compounds have been used for years in mineral separation processes. Because the volume of use of these compounds is low, insufficient data is available on their toxic properties. This report is an attempt to summarize the known data from published and industry sources. The physical properties, hazards of handling,proper storage facilities, and adequate protective Clothing are discussed for each compound as well as for their common and less-common solvents. Toxicity data for these materials is listed along with exposure symptoms and suggested first aid treatments. Safety for the worker is emphasized. Three reclamation methods which recover the solvent used as a dilutant and purify the heavy liquid are discussed and illustrated. These include: the water cascade, re fluxing-distillation-condensation, and flash evaporation methods. Various techniques for restoration and stabilization of these heavy liquids are also included.

Radiological interpretation: The 'step-child' in radiology

International Nuclear Information System (INIS)

Heilmann, H.P.

1981-01-01

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

Microfluidics on liquid handling stations (μF-on-LHS): an industry compatible chip interface between microfluidics and automated liquid handling stations.

Science.gov (United States)

Waldbaur, Ansgar; Kittelmann, Jörg; Radtke, Carsten P; Hubbuch, Jürgen; Rapp, Bastian E

2013-06-21

We describe a generic microfluidic interface design that allows the connection of microfluidic chips to established industrial liquid handling stations (LHS). A molding tool has been designed that allows fabrication of low-cost disposable polydimethylsiloxane (PDMS) chips with interfaces that provide convenient and reversible connection of the microfluidic chip to industrial LHS. The concept allows complete freedom of design for the microfluidic chip itself. In this setup all peripheral fluidic components (such as valves and pumps) usually required for microfluidic experiments are provided by the LHS. Experiments (including readout) can be carried out fully automated using the hardware and software provided by LHS manufacturer. Our approach uses a chip interface that is compatible with widely used and industrially established LHS which is a significant advancement towards near-industrial experimental design in microfluidics and will greatly facilitate the acceptance and translation of microfluidics technology in industry.

Current US strategy and technologies for spent fuel handling

International Nuclear Information System (INIS)

Bennett, P.C.; Stringer, J.B.

1999-01-01

The United States Department of Energy has recently completed a topical safety analysis report outlining the design and operation of a Centralized Interim Storage Facility for spent commercial nuclear fuel. During the course of the design, dose assessments indicated the need for remote operation of many of the cask handling operations. Use of robotic equipment was identified as a desirable handling solution that is capable of automating many of the operations to maintain throughput, and sufficiently flexible to handle five or more different storage cask designs in varying numbers on a given day. This paper discusses the facility and the dose assessment leading to this choice, and reviews factors to be considered when choosing robotics or automation. Further, a new computer simulation tool to quantify dose to humans working in radiological environments, the Radiological Environment Modeling System (REMS), is introduced. REMS has been developed to produce a more accurate estimate of dose to radiation workers in new activities with radiological hazards. (author)

Hygiene in radiology

International Nuclear Information System (INIS)

Kapp-Schwoerer, A.; Daschner, F.

1987-01-01

A survey is given of the hygienic management in radiological departments with special regard to the handling of injections and infusions. It includes prevention of bacterial as well as viral infections. In radiological departments disinfection of X-ray tables is necessary only in exceptional cases. A special proposal for disinfection is added. A safe method of sterilisation of flexible catheders is included, which proved to prevent bacterial infection. (orig.) [de

Radiological protection when handling plutonium in a laboratory for experimental fuels

International Nuclear Information System (INIS)

Fraser, D.C.

1978-01-01

The laboratory for experimental fuels at AEE Winfrith is a small but adaptable workshop capable of fabricating uranium and plutonium as metal or oxide into a variety of fuel elements including pins, plates and coated particle compacts for reactor physics experiments. Experience gained over fifteen years operation has shown that the external radiation dose received by operators, which arises mainly from low energy gamma and X radiation, can be controlled by the widespread use of simple shielding. The radiation from higher energy neutrons cannot be effectively shielded in simple non-automated plant and it becomes more important if large batches of fuel are handled. Inhalation of plutonium oxide is the potentially most important radiological problem. Normally airborne levels of PuO 2 are insignificant; occasionally very high but localised concentrations of airborne material have arisen in working areas, chiefly from minor damage to the flexible part of the containment system, i.e. the gloves and posting bags in glove boxes. Methods employed to measure radiation and inhalation exposure are described and the implications discussed. A fully integrated biological monitoring, in vivo counting and record system is used to ensure that the best estimate of intake is computed for each individual who may be exposed. (author)

METHODS FOR THE SAFE STORAGE, HANDLING, AND DISPOSAL OF PYROPHORIC LIQUIDS AND SOLIDS IN THE LABORATORY

Energy Technology Data Exchange (ETDEWEB)

Simmons, F.; Kuntamukkula, M.; Alnajjar, M.; Quigley, D.; Freshwater, D.; Bigger, S.

2010-02-02

Pyrophoric reagents represent an important class of reactants because they can participate in many different types of reactions. They are very useful in organic synthesis and in industrial applications. The Occupational Safety and Health Administration (OSHA) and the National Fire Protection Association (NFPA) define Pyrophorics as substances that will self-ignite in air at temperatures of 130 F (54.4 C) or less. However, the U.S. Department of Transportation (DOT) uses criteria different from the auto-ignition temperature criterion. The DOT defines a pyrophoric material as a liquid or solid that, even in small quantities and without an external ignition source, can ignite within five minutes after coming in contact with air when tested according to the United Nations Manual of Tests and Criteria. The Environmental Protection Agency has adopted the DOT definition. Regardless of which definition is used, oxidation of the pyrophoric reagents by oxygen or exothermic reactions with moisture in the air (resulting in the generation of a flammable gas such as hydrogen) is so rapid that ignition occurs spontaneously. Due to the inherent nature of pyrophoric substances to ignite spontaneously upon exposure to air, special precautions must be taken to ensure their safe handling and use. Pyrophoric gases (such as diborane, dichloroborane, phosphine, etc.) are typically the easiest class of pyrophoric substances to handle since the gas can be plumbed directly to the application and used remotely. Pyrophoric solids and liquids, however, require the user to physically manipulate them when transferring them from one container to another. Failure to follow proper safety precautions could result in serious injury or unintended consequences to laboratory personnel. Because of this danger, pyrophorics should be handled only by experienced personnel. Users with limited experience must be trained on how to handle pyrophoric reagents and consult with a knowledgeable staff member prior

Chromosome analyses of nurses handling cytostatic agents

International Nuclear Information System (INIS)

Waksvik, H.; Klepp, O.; Brogger, A.

1981-01-01

A cytogenetic study of ten nurses handling cytostatic agents (average exposure, 2150 hours) and ten female hospital clerks revealed an increased frequency of chromosome gaps and a slight increase in sister chromatid exchange frequency among the nurses. The increase may be due to exposure to cytostatic drugs and points to these agents as a possible occupational health hazard. A second group of 11 nurses handling cytostatic agents for a shorter period of time (average exposure, 1078 hours), and three other groups (eight nurses engaged in therapeutic and diagnostic radiology, nine nurses engaged in anesthesiology, and seven nurses in postoperative ward) did not differ from the office personnel, except for an increased frequency of chromosome gaps in the radiology group

On current US strategy and technologies for spent fuel handling

International Nuclear Information System (INIS)

Bennett, P.C.

1997-01-01

The US Department of Energy has recently completed a topical safety analysis report outlining the design and operation of a Centralized Interim Storage Facility for spent commercial nuclear fuel. During the course of the design, dose assessments indicated the need for remote operation of many of the cask handling operations. Use of robotic equipment was identified as a desirable handling solution that is capable of automating many of the operations to maintain throughput, and sufficiently flexible to handle five or more different storage cask designs in varying numbers on a given day. This paper discusses the facility and the dose assessment leading to this choice, and reviews factors to be considered when choosing robotics or automation. Further, a new computer simulation tool to quantify dose to humans working in radiological environments, the Radiological Environment Modeling System (REMS), is introduced. REMS has been developed to produce a more accurate estimate of dose to radiation workers in new activities with radiological hazards

SMART instruments for radiological surveillance at the back end of nuclear fuel cycle

International Nuclear Information System (INIS)

Pendharkar, K.A.; Jauhri, G.S.; Ganesh, G.; Kulkarni, V.V.

2001-01-01

The back end of Nuclear Fuel Cycle mainly consists of Fuel Reprocessing Plant and Waste Management Plant for treatment of different types of wastes generated during processing of spent fuel. A fuel reprocessing plant handles annually several million curies of fission product activity and few hundred kg of plutonium. A Waste Management Facility associated with a reprocessing plant also handles several million curies of fission product activity. In both the plants several types of radiological measurements have to be carried out to ensure that the individual doses are well below regulatory limits and release of radioactivity to environment (through stack and through liquid effluent) is below the limit stipulated in technical specifications of the plant. The measurements comprise individual external dose, measurement of radiation level in different areas of the plant, assessment of air-borne activity due to plutonium and fission products in different areas of the plant, radioactivity release to environment through liquid effluents and through stack. In order to carry out the above mentioned measurements large number of different types of instruments are required. The existing instruments are analog instruments. These instruments have served well. However they have certain limitations with respect to flexibility and extra functionality. In this respect the 'SMART' instruments have distinct advantages. The advantages, that are offered by the 'SMART' instrument in making the radiological surveillance programme more effective, are brought out in the paper. (author)

Radiological assessment and management of radioactive spill in a liquid waste treatment facility - Case study

International Nuclear Information System (INIS)

Amer, H.A.; Shawky, S.; Ibrahiem, N.

2002-01-01

The radiological assessment and management of radioactive spill from liquid waste treatment facility is presented. The incident contaminated the area surrounding the treatment facility with various radionuclides, which were dispersed into the soil. A method based on the European basic safety standards was used to contain the risks associated with the contaminated site. The introduced case study proceeded up to the stage of simplified risk study, since the site is small and it was relatively easy to remove and store the contaminated soil. According to the obtained results, the removal of the upper 30-cm would be considered as appropriate remedying action to resume background level. One of the most important basic concepts of radiation protection in nuclear facilities is the continuity of monitoring radiological release to the environment. It is known that from nuclear facilities only very small amounts of radioactivity are discharged with the liquid effluents and the exhaust air into the environment. Recent studies screening the natural and artificial radionuclide in soil samples from the investigated area revealed normal background concentrations with no anomalies

Calixarene-mediated liquid membrane transport of choline conjugates 3: The effect of handle variation on neurotransmitter transport.

Science.gov (United States)

Collins, James L; Fujii, Ayu; Roshandel, Sahar; To, Cuong-Alexander; Schramm, Michael P

2017-07-01

Upper rim phosphonic acid functionalized calix[4]arene affects selective transport of multiple molecular payloads through a liquid membrane. The secret is in the attachment of a receptor-complementary handle to the payload. We find that the trimethylammonium ethylene group present in choline is one of several general handles for the transport of drug and drug-like species. Herein we compare the effect of handle variation against the transport of serotonin and dopamine. We find that several ionizable amine termini handles are sufficient for transport and identify two ideal candidates. Their performance is significantly enhanced in HEPES buffered solutions. This inquiry completes a series of 3 studies aimed at optimization of this strategy. In completion a new approach towards synthetic receptor mediated selective small molecule transport has emerged; future work in vesicular and cellular systems will follow. Copyright © 2017 Elsevier Ltd. All rights reserved.

Handling zone dividing method in packed bed liquid desiccant dehumidification/regeneration process

International Nuclear Information System (INIS)

Liu, X.H.; Jiang, Y.

2009-01-01

Dehumidifier and regenerator are the most significant components in liquid desiccant air-conditioning systems, in which air directly contacts liquid desiccant and heat and mass transfer process occurs between the two fluids. Heat transfer process and mass transfer process within dehumidifier/regenerator influence each other and should not be separately considered. Based on the previous reachable handling region analysis, a zonal method is proposed in present study. Four zones are divided in the psychrometric chart according to the relative position of inlet air to inlet desiccant including two dehumidification zones, zone A and zone D, and two regeneration zones, zone B and zone C. In zone A or C, mass transfer is key process, and counter-flow configuration has the best mass transfer performance and parallel-flow is the poorest in the same operating conditions. In zone B or D, heat transfer is governing process, parallel-flow has the best mass transfer performance and counter-flow is the poorest. In order to obtain better mass transfer performance, liquid desiccant should be cooled (in zone A) rather than air (in zone D) in dehumidifier, and liquid desiccant should be heated (in zone C) rather than air (in zone B) in regenerator. The divided zones and the corresponding zonal properties will be helpful to the design and optimization of dehumidifiers and regenerators.

An Open-Source, Low-Cost Robot for Performing Reactive Liquid Handling Experiments

DEFF Research Database (Denmark)

Nejatimoharrami, Farzad; Faina, Andres; Støy, Kasper

vessels in the middle, and 3) a camera as the sensing system at the bottom, providing a view of the experiment. From the raw camera image experiment specific data such as droplet size, position, speed, number, color, and shape are calculated. The computer vision system has an accuracy of 4% for droplet......Bot's application domain is extendable owing to a modular design of hardware, and open source software. Evobot's modular design enables support for different modules, e.g. syringe modules for liquid handling, grippers to reposition reaction vessels or dispose of them, sensor modules including temperature, pH, etc...

Survey of tritiated oil sources and handling practices

International Nuclear Information System (INIS)

Miller, J.M.

1994-08-01

Tritium interactions with oil sources (primarily associated with pumps) in tritium-handling facilities can lead to the incorporation of tritium in the oil and the production of tritiated hydrocarbons. This results in a source of radiological hazard and the need for special handling considerations during maintenance, decontamination, decommissioning and waste packaging and storage. The results of a general survey of tritiated-oil sources and their associated characteristics, handling practices, analysis techniques and waste treatment/storage methods are summarized here. Information was obtained from various tritium-handling laboratories, fusion devices, and CANDU plants. 38 refs., 1 fig

Digital radiology and ultrasound

International Nuclear Information System (INIS)

Todd-Pokropek, A.

1991-01-01

With the access to digital methods for handling and processing images in general, many medical imaging methods are becoming more effectively handled digitally. This applies in particular to basically digital techniques such as CT and MR but also now includes Nuclear Medicine (NM), Ultrasound (US) and a variety of radiological procedures such as Digital Subtraction Angiography (DSA) and Fluoroscopy (DF). The access to conventional projection images by stimulatable plates (CR) or by digitization of film makes all of radiology potentially accessible, and the management of such images by a network is the basic aim of Picture Archiving and Communication Systems (PACS). However, it is suggested that in order for such systems to be of greater value, that way in which such images are treated needs to change, that is, digital images can be used to derive additional clinical value by appropriate processing

Radioactive waste management for a radiologically contaminated hospitalized patient

International Nuclear Information System (INIS)

Pina Jomir, G.; Michel, X.; Lecompte, Y.; Chianea, N.; Cazoulat, A.

2015-01-01

Radioactive waste management in the post-accidental phase following caring for a radiologically contaminated patient in a hospital decontamination facility must be anticipated at a local level to be truly efficient, as the volume of waste could be substantial. This management must comply with the principles set out for radioactive as well as medical waste. The first step involves identification of radiologically contaminated waste based on radioactivity measurement for volume reduction. Then, the management depends on the longest radioactive half-life of contaminative radionuclides. For a half-life inferior to 100 days, wastes are stored for their radioactivity to decay for at least 10 periods before disposal like conventional medical waste. Long-lived radioactive waste management implies treatment of liquid waste and special handling for sorting and packaging before final elimination at the French National Agency for Radioactive Waste Management (ANDRA). Following this, highly specialized waste management skills, financial responsibility issues and detention of non-medical radioactive sources are questions raised by hospital radioactive waste management in the post-accidental phase. (authors)

Basic demands for radiological information systems (RIS)

International Nuclear Information System (INIS)

Traupe, H.; Purgold, S.

1993-01-01

One of the most important problems in medicine today is quality control and the achievement of a cost-benefit analysis in the areas of both treatment and diagnosis. With modern software techniques, complex relations between medical and aministrative data can be shown up and analysed. Preconditions are a vocabulary that can be processed by computer for medical facts and decisions and a database system capable of collecting a large amount of heterogeneous data and costing everything precisely. We have developed an object description language and, on the basis of the relational database approach, a complex system covering most aspects of medical and administrative data handling in radiology. The basic demands and elements of modern information handling in radiology are described and discussed. (orig.) [de

Realization of the low background neutrino detector Double Chooz. From the development of a high-purity liquid and gas handling concept to first neutrino data

Energy Technology Data Exchange (ETDEWEB)

Pfahler, Patrick

2012-12-17

Neutrino physics is one of the most vivid fields in particle physics. Within this field, neutrino oscillations are of special interest as they allow to determine driving oscillation parameters, which are collected as mixing angles in the leptonic mixing matrix. The exact knowledge of these parameters is the main key for the investigation of new physics beyond the currently known Standard Model of particle physics. The Double Chooz experiment is one of three reactor disappearance experiments currently taking data, which recently succeeded to discover a non-zero value for the last neutrino mixing angle {Theta}{sub 13}. As successor of the CHOOZ experiment, Double Chooz will use two detectors with improved design, each of them now composed of four concentrically nested detector vessels each filled with different detector liquid. The integrity of this multi-layered structure and the quality of the used detector liquids are essential for the success of the experiment. Within this frame, the here presented work describes the production of two detector liquids, the filling and handling of the Double Chooz far detector and the installation of all necessary hardware components therefore. In order to meet the strict requirements existing for the detector liquids, all components were individually selected in an extensive material selection process at TUM, which compared samples from different companies for their key properties: density, transparency, light yield and radio purity. Based on these measurements, the composition of muon veto scintillator and buffer liquid were determined. For the production of the detector liquids, a simple surface building close to the far detector site was upgraded into a large-scale storage and mixing facility, which allowed to separately, mix, handle and store 90 m{sup 3} of muon veto scintillator and 110 m{sup 3} of buffer liquid. For the muon veto scintillator, a master-solution composed of 4800 l LAB, 180 kg PPO and 1.8 kg of bis/MSB was

Realization of the low background neutrino detector Double Chooz. From the development of a high-purity liquid and gas handling concept to first neutrino data

International Nuclear Information System (INIS)

Pfahler, Patrick

2012-01-01

Neutrino physics is one of the most vivid fields in particle physics. Within this field, neutrino oscillations are of special interest as they allow to determine driving oscillation parameters, which are collected as mixing angles in the leptonic mixing matrix. The exact knowledge of these parameters is the main key for the investigation of new physics beyond the currently known Standard Model of particle physics. The Double Chooz experiment is one of three reactor disappearance experiments currently taking data, which recently succeeded to discover a non-zero value for the last neutrino mixing angle Θ 13 . As successor of the CHOOZ experiment, Double Chooz will use two detectors with improved design, each of them now composed of four concentrically nested detector vessels each filled with different detector liquid. The integrity of this multi-layered structure and the quality of the used detector liquids are essential for the success of the experiment. Within this frame, the here presented work describes the production of two detector liquids, the filling and handling of the Double Chooz far detector and the installation of all necessary hardware components therefore. In order to meet the strict requirements existing for the detector liquids, all components were individually selected in an extensive material selection process at TUM, which compared samples from different companies for their key properties: density, transparency, light yield and radio purity. Based on these measurements, the composition of muon veto scintillator and buffer liquid were determined. For the production of the detector liquids, a simple surface building close to the far detector site was upgraded into a large-scale storage and mixing facility, which allowed to separately, mix, handle and store 90 m 3 of muon veto scintillator and 110 m 3 of buffer liquid. For the muon veto scintillator, a master-solution composed of 4800 l LAB, 180 kg PPO and 1.8 kg of bis/MSB was produced and

Radiation protection and quality assurance in dental radiology: II. Panoramic radiology

International Nuclear Information System (INIS)

Jodar-Porlan, S.; Alcaraz, M.; Martinez-Beneyto, Y.; Saura-Iniesta, A.M.; Velasco-Hidalgo, E.

2001-01-01

This paper studies 278 official reports on quality assurance in dental radiology in the context of the first revision of these dental clinics, as a result of the entry into force of the regulations establishing the duties for these types of facilities. In the results section we present a quantitative analysis of the facilities equipped with an panoramic radiology apparatus, making a special reference to the brands they have available, as well as their physical features (kV, mA, filtration) and the deviations detected in their operation. Some of their features in the process of obtaining radiological images at those facilities (film control, development time, liquid renewal) are determined, and the average dose of ionising radiation used in order to obtain the same tooth radiological image is presented. This paper shows, in a quantitative way, the characteristic features of panoramic radiology in our medium. The study is intended to be continued during the next years, which would allow the assessment of the prospective improvement in dental radiological performances as a result of the newly established regulations. (author)

Radiological safety aspects associated with the handling, storage and disposal of self power neutron detectors in TAPS - 3 and 4

International Nuclear Information System (INIS)

Parida, B.K.; Mudgal, B.; Ghadigoankar, V.R.; Niraj; Ashok; Pati, C.K.; Patil, P.M.; Pawar, S.K.; Varadhan, R.S.

2006-01-01

At Tarapur Atomic Power Station 3 and 4, 540 MWe Pressurised Heavy Water Reactors, core being large in size requires a continuous in core monitoring for local flux disturbances. Nearly 200 Self Powered Neutron Detectors (SPNDs) of the Straight Individually Replaceable (SIR) type are distributed in the reactor core. For purpose of reactor regulation and protection, cobalt SPNDs that have a prompt response for changes in power is used for in-core flux mapping, vanadium SPNDs that provide accurate measure of neutron flux, even though having slow response is used In core SPNDs are placed in Vertical Flux Units (VFU) and Horizontal Flux Units (HFUs). These SPNDs were to be replaced at regular intervals to meet the design intent. Cobalt SPNDs have dose rates of the order of 1000 Gy/h and the Mineral Insulated (MI) cables of Vanadium SPNDs have dose rates of the order of 100 Gy/h. So far 3 Cobalt SPNDs were removed from HFUs and are being stored in lead shielding inside spent fuel storage facility. These high active components were handled with meticulous planning with lowest exposures to the maintainers. Radiological safety aspects of handling and storage of SPNDs are discussed in this report. (author)

Characterization of aqueous two phase systems by combining lab-on-a-chip technology with robotic liquid handling stations.

Science.gov (United States)

Amrhein, Sven; Schwab, Marie-Luise; Hoffmann, Marc; Hubbuch, Jürgen

2014-11-07

Over the last decade, the use of design of experiment approaches in combination with fully automated high throughput (HTP) compatible screenings supported by robotic liquid handling stations (LHS), adequate fast analytics and data processing has been developed in the biopharmaceutical industry into a strategy of high throughput process development (HTPD) resulting in lower experimental effort, sample reduction and an overall higher degree of process optimization. Apart from HTP technologies, lab-on-a-chip technology has experienced an enormous growth in the last years and allows further reduction of sample consumption. A combination of LHS and lab-on-a-chip technology is highly desirable and realized in the present work to characterize aqueous two phase systems with respect to tie lines. In particular, a new high throughput compatible approach for the characterization of aqueous two phase systems regarding tie lines by exploiting differences in phase densities is presented. Densities were measured by a standalone micro fluidic liquid density sensor, which was integrated into a liquid handling station by means of a developed generic Tip2World interface. This combination of liquid handling stations and lab-on-a-chip technology enables fast, fully automated, and highly accurate density measurements. The presented approach was used to determine the phase diagram of ATPSs composed of potassium phosphate (pH 7) and polyethylene glycol (PEG) with a molecular weight of 300, 400, 600 and 1000 Da respectively in the presence and in the absence of 3% (w/w) sodium chloride. Considering the whole ATPS characterization process, two complete ATPSs could be characterized within 24h, including four runs per ATPS for binodal curve determination (less than 45 min/run), and tie line determination (less than 45 min/run for ATPS preparation and 8h for density determination), which can be performed fully automated over night without requiring man power. The presented methodology provides

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

DOE handbook: Tritium handling and safe storage

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-03-01

The DOE Handbook was developed as an educational supplement and reference for operations and maintenance personnel. Most of the tritium publications are written from a radiological protection perspective. This handbook provides more extensive guidance and advice on the null range of tritium operations. This handbook can be used by personnel involved in the full range of tritium handling from receipt to ultimate disposal. Compliance issues are addressed at each stage of handling. This handbook can also be used as a reference for those individuals involved in real time determination of bounding doses resulting from inadvertent tritium releases. This handbook provides useful information for establishing processes and procedures for the receipt, storage, assay, handling, packaging, and shipping of tritium and tritiated wastes. It includes discussions and advice on compliance-based issues and adds insight to those areas that currently possess unclear DOE guidance.

DOE handbook: Tritium handling and safe storage

International Nuclear Information System (INIS)

1999-03-01

The DOE Handbook was developed as an educational supplement and reference for operations and maintenance personnel. Most of the tritium publications are written from a radiological protection perspective. This handbook provides more extensive guidance and advice on the null range of tritium operations. This handbook can be used by personnel involved in the full range of tritium handling from receipt to ultimate disposal. Compliance issues are addressed at each stage of handling. This handbook can also be used as a reference for those individuals involved in real time determination of bounding doses resulting from inadvertent tritium releases. This handbook provides useful information for establishing processes and procedures for the receipt, storage, assay, handling, packaging, and shipping of tritium and tritiated wastes. It includes discussions and advice on compliance-based issues and adds insight to those areas that currently possess unclear DOE guidance

46 CFR 151.25-2 - Cargo handling space.

Science.gov (United States)

2010-10-01

... 46 Shipping 5 2010-10-01 2010-10-01 false Cargo handling space. 151.25-2 Section 151.25-2 Shipping... BULK LIQUID HAZARDOUS MATERIAL CARGOES Environmental Control § 151.25-2 Cargo handling space. Pump rooms, compressor rooms, refrigeration rooms, heating rooms, instrument rooms or other closed spaces...

Determination of heat capacity of ionic liquid based nanofluids using group method of data handling technique

Science.gov (United States)

Sadi, Maryam

2018-01-01

In this study a group method of data handling model has been successfully developed to predict heat capacity of ionic liquid based nanofluids by considering reduced temperature, acentric factor and molecular weight of ionic liquids, and nanoparticle concentration as input parameters. In order to accomplish modeling, 528 experimental data points extracted from the literature have been divided into training and testing subsets. The training set has been used to predict model coefficients and the testing set has been applied for model validation. The ability and accuracy of developed model, has been evaluated by comparison of model predictions with experimental values using different statistical parameters such as coefficient of determination, mean square error and mean absolute percentage error. The mean absolute percentage error of developed model for training and testing sets are 1.38% and 1.66%, respectively, which indicate excellent agreement between model predictions and experimental data. Also, the results estimated by the developed GMDH model exhibit a higher accuracy when compared to the available theoretical correlations.

Instructional Vignettes in Publication and Journalism Ethics in Radiology Research: Assessment via a Survey of Radiology Trainees.

Science.gov (United States)

Rosenkrantz, Andrew B; Ginocchio, Luke A

2016-07-01

The aim of the present study was to assess the potential usefulness of written instructional vignettes relating to publication and journalism ethics in radiology via a survey of radiology trainees. A literature review was conducted to guide the development of vignettes, each describing a scenario relating to an ethical issue in research and publication, with subsequent commentary on the underlying ethical issue and potential approaches to its handling. Radiology trainees at a single institution were surveyed regarding the vignettes' perceived usefulness. A total of 21 vignettes were prepared, addressing institutional review board and human subjects protection, authorship issues, usage of previous work, manuscript review, and other miscellaneous topics. Of the solicited trainees, 24.7% (16/65) completed the survey. On average among the vignettes, 94.0% of the participants found the vignette helpful; 19.9 received prior formal instruction on the issue during medical training; 40.0% received prior informal guidance from a research mentor; and 42.0% indicated that the issue had arisen in their own or a peer's prior research experience. The most common previously experienced specific issue was authorship order (93.8%). Free-text responses were largely favorable regarding the value of the vignettes, although also indicated numerous challenges in properly handling the ethical issues: impact of hierarchy, pressure to publish, internal politics, reluctance to conduct sensitive conversations with colleagues, and variability in journal and professional society policies. Radiology trainees overall found the vignettes helpful, addressing commonly encountered topics for which formal and informal guidance were otherwise lacking. The vignettes are publicly available through the Association of University Radiologists (AUR) website and may foster greater insights by investigators into ethical aspects of the publication and journalism process, thus contributing to higher quality

Safeness of radiological machinery

International Nuclear Information System (INIS)

Yokoyama, Shun

1979-01-01

The human factors affecting the safeness of radiological machinery, which are often very big and complicated machines, are described from the stand point of handling. 20 to 50% of the troubles on equipments seem to be caused by men. This percentage will become even higher in highly developed equipments. Human factors have a great influence on the safeness of radiological equipments. As the human factors, there are sensory factors and knowledge factors as well as psychological factors, and the combination of these factors causes mishandling and danger. Medical services at present are divided in various areas, and consist of the teamwork of the people in various professions. Good human relationship, education and control are highly required to secure the safeness. (Kobatake, H.)

High-throughput transformation of Saccharomyces cerevisiae using liquid handling robots.

Directory of Open Access Journals (Sweden)

Guangbo Liu

Full Text Available Saccharomyces cerevisiae (budding yeast is a powerful eukaryotic model organism ideally suited to high-throughput genetic analyses, which time and again has yielded insights that further our understanding of cell biology processes conserved in humans. Lithium Acetate (LiAc transformation of yeast with DNA for the purposes of exogenous protein expression (e.g., plasmids or genome mutation (e.g., gene mutation, deletion, epitope tagging is a useful and long established method. However, a reliable and optimized high throughput transformation protocol that runs almost no risk of human error has not been described in the literature. Here, we describe such a method that is broadly transferable to most liquid handling high-throughput robotic platforms, which are now commonplace in academic and industry settings. Using our optimized method, we are able to comfortably transform approximately 1200 individual strains per day, allowing complete transformation of typical genomic yeast libraries within 6 days. In addition, use of our protocol for gene knockout purposes also provides a potentially quicker, easier and more cost-effective approach to generating collections of double mutants than the popular and elegant synthetic genetic array methodology. In summary, our methodology will be of significant use to anyone interested in high throughput molecular and/or genetic analysis of yeast.

Strategy development for anticipating and handling a disruptive technology.

Science.gov (United States)

Chan, Stephen

2006-10-01

The profession of radiology has greatly benefited from the introduction of new imaging technologies throughout its history. Therefore, it would seem reasonable for radiologists to believe that the emergence of a new imaging technology can generally be foreseen with sufficient advance notice to allow the appropriate levels of time, effort, and money to be devoted toward incorporating it into radiology practice. However, in his seminal work, Christiansen characterized a new form of technologic innovation, known as "disruptive technology," whose emergence often heralds the replacement of market leaders in an industry by competitors who are quicker in adopting and deploying the new technology. This article briefly describes the phenomenon of disruptive technology and addresses the challenges that organizations face in dealing with disruptive technology. The article raises 4 questions about the future of radiology: (1) Are health care and radiology vulnerable to disruptive technology? (2) What kinds of change may be in store for the radiology profession? (3) Can the radiology profession prepare itself to recognize and respond to a disruptive innovation among a group of new imaging technologies? and (4) How should a radiology organization decide whether to invest significant resources in a potentially disruptive technology? This article addresses these questions by reviewing key insights from leading "gurus" in the fields of competitive strategy and technology management and applying them to radiology. This illustrates how and why (despite past successes) the radiology profession may still have a blind spot in recognizing and handling disruptive technologies.

Best Available Technology (BAT) guidance for radiological liquid effluents at US Department of Energy Facilities

International Nuclear Information System (INIS)

Wallo, A. III; Peterson, H.T. Jr.; Ikenberry, T.A.; Baker, R.E.

1993-01-01

The US Department of Energy (DOE), in DOE Order 5400.5 (1990), directs operators of DOE facilities to apply the Best Available Technology (BAT) to control radiological liquid effluents from these facilities when specific conditions are present. DOE has published interim guidance to assist facility operators in knowing when a BAT analysis is needed and how such an analysis should be performed and documented. The purpose of the guidance is to provide a uniform basis in determining BAT throughout DOE and to assist in evaluating BAT determinations during programmatic audits. The BAT analysis process involves characterizing the effluent source; identifying and selecting candidate control technologies; evaluating the potential environmental, operational, resource, and economic impacts of the control technologies; developing an evaluation matrix for comparing the technologies; selecting the BAT; and documenting the evaluation process. The BAT analysis process provides a basis for consistent evaluation of liquid effluent releases, yet allows an individual site or facility the flexibility to address site-specific issues or concerns in the most appropriate manner

Preliminary assessment of radiological doses in alternative waste management systems without an MRS facility

International Nuclear Information System (INIS)

Schneider, K.J.; Pelto, P.J.; Daling, P.M.; Lavender, J.C.; Fecht, B.A.

1986-06-01

This report presents generic analyses of radiological dose impacts of nine hypothetical changes in the operation of a waste management system without a monitored retrievable storage (MRS) facility. The waste management activities examined in this study include those for handling commercial spent fuel at nuclear power reactors and at the surface facilities of a deep geologic repository, and the transportation of spent fuel by rail and truck between the reactors and the repository. In the reference study system, the radiological doses to the public and to the occupational workers are low, about 170 person-rem/1000 metric ton of uranium (MTU) handled with 70% of the fuel transported by rail and 30% by truck. The radiological doses to the public are almost entirely from transportation, whereas the doses to the occupational workers are highest at the reactors and the repository. Operating alternatives examined included using larger transportation casks, marshaling rail cars into multicar dedicated trains, consolidating spent fuel at the reactors, and wet or dry transfer options of spent fuel from dry storage casks. The largest contribution to radiological doses per unit of spent fuel for both the public and occupational workers would result from use of truck transportation casks, which are smaller than rail casks. Thus, reducing the number of shipments by increasing cask sizes and capacities (which also would reduce the number of casks to be handled at the terminals) would reduce the radiological doses in all cases. Consolidating spent fuel at the reactors would reduce the radiological doses to the public but would increase the doses to the occupational workers at the reactors

Safety handling manual for high dose rate remote afterloading system

International Nuclear Information System (INIS)

1999-01-01

This manual is mainly for safety handling of 192 Ir-RALS (remote afterloading system) of high dose rate and followings were presented: Procedure and document format for the RALS therapy and for handling of its radiation source with the purpose of prevention of human errors and unexpected accidents, Procedure for preventing errors occurring in the treatment schedule and operation, and Procedure and format necessary for newly introducing the system into a facility. Consistency was intended in the description with the quality assurance guideline for therapy with small sealed radiation sources made by JASTRO (Japan Society for Therapeutic Radiology and Oncology). Use of the old type 60 Co-RALS was pointed out to be a serious problem remained and its safety handling procedure was also presented. (K.H.)

Method for treating radioactive liquids

International Nuclear Information System (INIS)

Komrow, R.R.; Pritchard, J.F.

1980-01-01

A process for treating and handling radioactive liquids and rendering such liquids safe for handling is disclosed. Transportation and disposal, the process comprises adding thereto a small amount of a water-insoluble alkali salt of an aqueous alkali saponified gelatinized-starch-polyacrylonitrile graft polymer, to form a solid, semi-solid or gel product

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

Energy Technology Data Exchange (ETDEWEB)

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

2014-10-15

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

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

International Nuclear Information System (INIS)

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

2014-01-01

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

Release protocol to address DOE moratorium on shipments of waste generated in radiologically controlled areas

International Nuclear Information System (INIS)

Rathbun, L.A.; Boothe, G.F.

1992-10-01

On May 17, 1991 the US DOE Office of Waste Operations issued a moratorium on the shipment of hazardous waste from radiologically contaminated or potentially contaminated areas on DOE sites to offsite facilities not licensed for radiological material. This document describes a release protocol generated by Westinghouse Hanford submitted for US DOE approval. Topics considered include designating Radiological Materials Management Areas (RMMAs), classification of wastes, handling of mixed wastes, detection limits

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

International Nuclear Information System (INIS)

Lopez, Edith; Gonzales, Susana; Zapata, Luis

2008-01-01

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

Mechatronics of fuel handling mechanism for fast experimental reactor 'Joyo'

Energy Technology Data Exchange (ETDEWEB)

Fujiwara, Akikazu (Power Reactor and Nuclear Fuel Development Corp., Oarai, Ibaraki (Japan). Oarai Engineering Center)

1984-01-01

The outline of the fast experimental reactor ''Joyo'' is introduced, and the fuel handling mechanism peculiar to fast reactors is described. The objectives of the construction of Joyo are to obtain the techniques for the design, construction, manufacture, installation, operation and maintenance of sodium-cooled fast reactors independently, and to use it as an irradiation facility for the development of fuel and materials for fast breeder reactors. At present, the reactor is operated at 100 MW maximum thermal output for the second objective. Since liquid sodium is used as the coolant, the atmosphere of the fuel handling course changes such as liquid sodium at 250 deg C, argon gas at 200 deg C and water, in addition, the spent fuel taken out has the decay heat of 2.1 kW at maximum. The fuel handling works in the reactor and fuel transfer works, and the fuel handling mechanism of a fuel exchanger and that of a cask car for fuel handling are described. Relay sequence control system is used for the fuel handling mechanism of Joyo.

Mobile autonomous robot for radiological surveys

International Nuclear Information System (INIS)

Dudar, A.M.; Wagner, D.G.; Teese, G.D.

1992-01-01

The robotics development group at the Savannah River Laboratory (SRL) is developing a mobile autonomous robot that performs radiological surveys of potentially contaminated floors. The robot is called SIMON, which stands for Semi-Intelligent Mobile Observing Navigator. Certain areas of SRL are classified as radiologically controlled areas (RCAs). In an RCA, radioactive materials are frequently handled by workers, and thus, the potential for contamination is ever present. Current methods used for floor radiological surveying includes labor-intensive manual scanning or random smearing of certain floor locations. An autonomous robot such as SIMON performs the surveying task in a much more efficient manner and will track down contamination before it is contacted by humans. SIMON scans floors at a speed of 1 in./s and stops and alarms upon encountering contamination. Its environment is well defined, consisting of smooth building floors with wide corridors. The kind of contaminations that SIMON is capable of detecting are alpha and beta-gamma. The contamination levels of interest are low to moderate

The Pathology of Infection in the Department of Radiology

Energy Technology Data Exchange (ETDEWEB)

Shin, Seong Gyu [Dept. of Radiology, Dong a University Medical Center, Pusan (Korea, Republic of); Lee, Hyo Yeong [Dept. of Nuclear Medicine, Pusan National University Hospital, Pusan (Korea, Republic of)

2012-09-15

This study was performed to understand the bacteriologic contamination level of radiological equipment which have frequent contacts with patients in the Department of Radiology of an university hospital in Busan area. Before sterilizing in-patient of the radiology rooms, MRSA, VRE, acinetobacter baumannii, candida albicans, and enterococcus sp. were detected. After sterilization, all the bacteria were not found. As examine times become longer, more bacteria were detected and after 7 hours, bacillus sp.(GPR), CNS, acinetobacter baumannii, and Enterococcus sp. were detected. After examining infected patients, bacillus sp.(GPR), VRE, enterococcus sp. CNS, and micrococcus sp. were detected and on the hands of radiological technologists, CNS, enterococcus sp. escherichia coli, and enterobacter sp. were detected. Similar species of bacteria were detected from each radiology room, but pseudomonas aeruginosa was detected on the handles of portable radiological equipment and the chair in the waiting room. Therefore, it is the most important to regularly sterilize radiological equipment and devices which have frequent contacts with patients and to sterilize them right after the use of infected patients in order to prevent the spread of infection. Also, thorough hand washing, education on infection and management for the characteristics of Department of Radiology should be performed for the systematic prevention of infection.

The Pathology of Infection in the Department of Radiology

International Nuclear Information System (INIS)

Shin, Seong Gyu; Lee, Hyo Yeong

2012-01-01

This study was performed to understand the bacteriologic contamination level of radiological equipment which have frequent contacts with patients in the Department of Radiology of an university hospital in Busan area. Before sterilizing in-patient of the radiology rooms, MRSA, VRE, acinetobacter baumannii, candida albicans, and enterococcus sp. were detected. After sterilization, all the bacteria were not found. As examine times become longer, more bacteria were detected and after 7 hours, bacillus sp.(GPR), CNS, acinetobacter baumannii, and Enterococcus sp. were detected. After examining infected patients, bacillus sp.(GPR), VRE, enterococcus sp. CNS, and micrococcus sp. were detected and on the hands of radiological technologists, CNS, enterococcus sp. escherichia coli, and enterobacter sp. were detected. Similar species of bacteria were detected from each radiology room, but pseudomonas aeruginosa was detected on the handles of portable radiological equipment and the chair in the waiting room. Therefore, it is the most important to regularly sterilize radiological equipment and devices which have frequent contacts with patients and to sterilize them right after the use of infected patients in order to prevent the spread of infection. Also, thorough hand washing, education on infection and management for the characteristics of Department of Radiology should be performed for the systematic prevention of infection.

Radiological incidents in radiotherapy

International Nuclear Information System (INIS)

Hobzova, L.; Novotny, J.

2008-01-01

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

Radiological Assistance Program, DOE Region 6 response plan

International Nuclear Information System (INIS)

Jakubowski, F.M.

1993-02-01

This program plan meets all the requirements identified in DOE Order 5530.3, Radiological Assistance Program and supports those requirements leading to the establishment of a Federal Radiological Monitoring and Assessment Center (FRMAC) as required by DOE 5530-5. Requests for radiological assistance may come from other DOE facilities, Federal or state agencies, tribal officials, or from any private corporation or individual. Many of the requests will be handled by a telephone call, a conference or a letter, teletype or memorandum. Other requests for assistance may involve radioactive material in serious accidents, fire, personal injuries, contamination or possible hazards to the general public. Some occurrences may require the dispatch of trained personnel equipped with radiation monitoring instruments and related equipment necessary to evaluate, control and neutralize the hazard. The primary responsibility for incidents involving radioactive material always remains with the party having custody of the radioactive materials. In addition, the DOE recognizes that the assistance provided shall not in any way preempt state, tribal, or local authority and/or responsibility on state or tribal properties. Toward this end, DOE assistance for non-DOE radioactive materials, is limited to technical assistance, advice, measurement and other resources as deemed necessary by the local authorities but excludes DOE interface with the public media. This is a function handled by the local or state Incident Commander

Technologies and logistics for handling, transport and distribution of animal manures

Science.gov (United States)

Organizing and managing the whole manure handling chain from the animal house through transport to the point of use (e.g. in the field) is a challenging task requiring consideration of manure type and operating conditions. Solid and liquid manure must be handled differently, using very different tec...

Column Liquid Chromatography.

Science.gov (United States)

Majors, Ronald E.; And Others

1984-01-01

Reviews literature covering developments of column liquid chromatography during 1982-83. Areas considered include: books and reviews; general theory; columns; instrumentation; detectors; automation and data handling; multidimensional chromatographic and column switching techniques; liquid-solid chromatography; normal bonded-phase, reversed-phase,…

Radiologic findings in lesions of the ligamentum bifurcatum of the midfoot

Energy Technology Data Exchange (ETDEWEB)

Nielsen, S.; Agnholt, J.; Christensen, H.

1987-02-01

In a consecutive study of 106 patients presenting with a history of ankle sprain, 40.5% showed clinical signs of damage to the ligamentum bifurcatum. Eighteen of these patients showed 20 radiologic signs related to a lesion of this ligament; these signs included avulsions from the points of insertion and laxity in the lateral part of the transverse tarsal joint. The supplementary radiographs revealing these signs are demonstrated, and a more differentiated radiologic handling of the patient with ankle sprain is suggested.

Radiologic findings in lesions of the ligamentum bifurcatum of the midfoot

International Nuclear Information System (INIS)

Nielsen, S.; Agnholt, J.; Christensen, H.

1987-01-01

In a consecutive study of 106 patients presenting with a history of ankle sprain, 40.5% showed clinical signs of damage to the ligamentum bifurcatum. Eighteen of these patients showed 20 radiologic signs related to a lesion of this ligament; these signs included avulsions from the points of insertion and laxity in the lateral part of the transverse tarsal joint. The supplementary radiographs revealing these signs are demonstrated, and a more differentiated radiologic handling of the patient with ankle sprain is suggested. (orig.)

Cable handling system for use in a nuclear reactor

International Nuclear Information System (INIS)

Crosgrove, R.O.; Larson, E.M.; Moody, E.

1982-01-01

A cable handling system for use in an installation such as a nuclear reactor is disclosed herein along with relevant portions of the reactor which, in a preferred embodiment, is a liquid metal fast breeder reactor. The cable handling system provides a specific way of interconnecting certain internal reactor components with certain external components, through an assembly of rotatable plugs. Moreover, this is done without having to disconnect these components from one another during rotation of the plugs and yet without interfering with other reactor components in the vicinity of the rotating plugs and cable handling system

Potential Indoor Worker Exposure From Handling Area Leakage: Dose Calculation Methodology and Example Consequence Analysis

International Nuclear Information System (INIS)

Nes, Razvan; Benke, Roland R.

2008-01-01

The U.S. Department of Energy (DOE) is currently considering design options for preclosure facilities in a license application for a geologic repository for spent nuclear fuel and high-level radioactive waste at Yucca Mountain, Nevada. The Center for Nuclear Waste Regulatory Analyses (CNWRA) developed the PCSA Tool Version 3.0.0 software for the U.S. Nuclear Regulatory Commission (NRC) to aid in the regulatory review of a potential DOE license application. The objective of this paper is to demonstrate PCSA Tool modeling capabilities (i.e., a generic two-compartment, mass-balance model) for estimating radionuclide concentrations in air and radiological dose consequences to indoor workers in a control room from potential leakage of radioactively contaminated air from an adjacent handling area. The presented model computes internal and external worker doses from inhalation and submersion in a finite cloud of contaminated air in the control room and augments previous capabilities for assessing indoor worker dose. As a complement to the example event sequence frequency analysis in the companion paper, example consequence calculations are presented in this paper for the postulated event sequence. In conclusion: this paper presents a model for estimating radiological doses to indoor workers for the leakage of airborne radioactive material from handling areas. Sensitivity of model results to changes in various input parameters was investigated via illustrative example calculations. Indoor worker dose estimates were strongly dependent on the duration of worker exposure and the handling-area leakage flow rate. In contrast, doses were not very sensitive to handling-area exhaust ventilation flow rates. For the presented example, inhalation was the dominant radiological dose pathway. The two companion papers demonstrate independent analysis capabilities of the regulator for performing confirmatory calculations of frequency and consequence, which assist the assessment of worker

Application of advanced handling techniques to transportation cask design

International Nuclear Information System (INIS)

Bennett, P.C.

1992-01-01

Sandia National Laboratories supports the US Department of Energy (DOE) Office of Civilian Radioactive Waste Management (OCRWM) applying technology to the safe transport of nuclear waste. Part of that development effort includes investigation of advanced handling technologies for automation of cask operations at nuclear waste receiving facilities. Although low radiation levels are expected near transport cask surfaces, cumulative occupational exposure at a receiving facility can be significant. Remote automated cask handling has the potential to reduce both the occupational exposure and the time necessary to process a cask. Thus, automated handling is consistent with DOE efforts to reduce the lifecycle costs of the waste disposal system and to maintain public and occupational radiological risks as low as reasonably achievable. This paper describes the development of advanced handling laboratory mock-ups and demonstrations for spent fuel casks. Utilizing the control enhancements described below, demonstrations have been carried out including cask location and identification, contact and non-contact surveys, impact limiter removal, tiedown release, uprighting, swing-free movement, gas sampling, and lid removal operations. Manually controlled movement around a cask under off-normal conditions has also been demonstrated

Safety in handling helium and nitrogen

International Nuclear Information System (INIS)

Schmauch, G.; Lansing, L.; Santay, T.; Nahmias, D.

1991-01-01

Based upon the authors' industrial experience and practices, they have provided an overview of safety in storage, handling, and transfer of both laboratory and bulk quantities of gaseous and liquid forms of nitrogen and helium. They have addressed the properties and characteristics of both the gaseous and liquid fluids, typical storage and transport containers, transfer techniques, and the associated hazards which include low temperatures, high pressures, and asphyxiation. Methods and procedures to control and eliminate these hazards are described, as well as risk remediation through safety awareness training, personal protective equipment, area ventilation, and atmosphere monitoring. They have included as an example a recent process hazards analysis performed by Air Products on the asphyxiation hazard associated with the use of liquid helium in MRI magnet systems

1980 annual radiological environmental report. Volume 2

International Nuclear Information System (INIS)

1980-01-01

This report describes the Radiological Environmental Monitoring Program conducted during 1980 in the vicinity of the Beaver Valley Power Station and the Shippingport Atomic Power Station. The Radiological Environmental Program consists of on-site sampling of water and gaseous effluents and off-site monitoring of water, air, river sediments, soils, food pathway samples, and radiation levels in the vicinity of the site. This report discusses the results of this monitoring during 1980. The environmental program outlined in the Beaver Valley Power Station Technical Specifications was followed throughout 1980. There were no radioactive liquid effluents released from the Shippingport Atomic Power Station since radioactive liquids are processed and re-cycled within the plant systems. The results of this environmental monitoring program show that Shippingport Atomic Power Station and Beaver Valley Power Station operations have not adversely affected the surrounding environment

Radiological protection objectives for the disposal of solid radioactive wastes

International Nuclear Information System (INIS)

1983-10-01

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

Radiological map evolution in the treatment of 137Cs liquid wastes by a reverse osmosis plant

International Nuclear Information System (INIS)

Arnal, J.M.; Sancho, M.; Verdu, G.; Gozalvez, J.M.

2002-01-01

As a result of an accidental 1 37C s source melting in one of the furnaces of a stainless steel production company located in Spain, a part of the factory was radioactively contaminated. LAINSA (Logistica y Acondicionamientos Industriales S.A.) company took charge of the plant decontamination process, in which 40 m 3 , approximately, of 1 37C s contaminated water with a mean activity of 300 kBq/L were generated. After some preliminary tests in which the efficiency of reverse osmosis (RO) process in the treatment of 1 37C s contaminated effluent was proved, the radioactive liquid waste was treated by a reverse osmosis plant designed by the Chemical and Nuclear Engineering Department of the Polytechnic University of Valencia (UPV), and built by LAINSA company. Membrane techniques (microfiltration, ultrafiltration, nanofiltration and reverse osmosis) have become common in the treatment of radioactive effluents having substitute conventional treatments such as evaporation and ionic exchange. The main advantages of membrane processes used for concentrating radioactive wastes are moderate operating conditions, simple apparatus, high decontamination factors and low energy consumption. The treatment was carried out by the research team UPV-LAINSA, and it consisted in the application of reverse osmosis (RO) process with the main objective of reducing the waste volume to be disposed, obtaining a treated liquid with an activity less than the legal discharge limit for 1 37C s radioisotope (300 Bq/L). When working with radioactive effluents it is very important the radiological vigilance of working areas because it ensures that neither exposed personnel nor general public receive doses above established limits. Radiological vigilance consists in determining (continuously or periodically) radiation and contamination levels in working areas and even in those places where personnel can temporarily stand. The aim of this paper is to assess the evolution of radiation levels of the

Safe Handling of Radioisotopes. Medical Addendum

International Nuclear Information System (INIS)

Hercik, F.; Jammet, H.

1960-01-01

The International Atomic Energy Agency published in 1958 a Manual entitled ''Safe Handling of Radioisotopes'' (Safety Series No. 1 - STI/PUB/1), based on the work of an international panel convened by the Agency. As recommended by that panel and approved by the Agency's Board of Governors, this Addendum has now been prepared, primarily as a supplement to the Manual. It contains information necessary to medical officers concerned with the implementation of the controls given in the Manual. In addition, it is intended to serve as a brief introduction to the medical problems encountered in radiological protection work and to the methods of resolving them. As in the case of the Manual itself, the information given in this Addendum is particularly relevant to the problems encountered by the small user of radioisotopes. Although the basic principles set forth in it apply to all work with radiation sources, the Addendum is not intended to serve as a radiological protection manual for use in reactor installations or large-scale nuclear industry, where more specialized techniques and information are required.

Film traffic queueing model for the DUMC radiology department

International Nuclear Information System (INIS)

Humphrey, L.M.; Ravin, C.E.

1988-01-01

This paper discusses the radiology department traffic model for Duke University Medical Center (DUMC) which simulates the flow of film through the department, and then incorporates the effect of introducing a PACS-type system into present operations. Each Radiology Section is considered separately for queuing of two types of film: old film (from previous exams) and new film (from the present exam). The amount of film in each queue at any time is controlled by controlling hours of operation, service times, delay, and arrival rates. The model also takes into account the use of film in each major radiology area. This gives some idea of the load on a device in that area as well as the amount of storage needed to adequately handle its daily load is local storage at the display device is desired

Soil radiological characterisation and remediation at CIEMAT

International Nuclear Information System (INIS)

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

2012-01-01

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

NDMA guidelines on handling of nuclear and radiological emergencies

Energy Technology Data Exchange (ETDEWEB)

Abani, M C [National Disaster Management Authority, New Delhi (India)

2010-07-01

The vulnerability to the disasters is high in India due to the large population density, fast growing urbanization, industrialization and also because of poor economic conditions of people. Natural disasters have been recurring phenomena in India, leading to extensive loss of life, livelihood and property. The primary reason for such heavy losses can be attributed to the reactive and response-centric approach adopted in the past in handling of the disasters. Based on the Guidelines a holistic approach is to be adopted for Nuclear Emergency Management Framework that assigns the highest priority to prevention, mitigation and compliance to regulatory requirements, while strengthening preparedness, capacity development, response etc. It will be implemented through strengthening of the existing action plans or by preparing new action plans at national, state and district levels by the stakeholders at all levels of administration

NDMA guidelines on handling of nuclear and radiological emergencies

International Nuclear Information System (INIS)

Abani, M.C.

2010-01-01

The vulnerability to the disasters is high in India due to the large population density, fast growing urbanization, industrialization and also because of poor economic conditions of people. Natural disasters have been recurring phenomena in India, leading to extensive loss of life, livelihood and property. The primary reason for such heavy losses can be attributed to the reactive and response-centric approach adopted in the past in handling of the disasters. Based on the Guidelines a holistic approach is to be adopted for Nuclear Emergency Management Framework that assigns the highest priority to prevention, mitigation and compliance to regulatory requirements, while strengthening preparedness, capacity development, response etc. It will be implemented through strengthening of the existing action plans or by preparing new action plans at national, state and district levels by the stakeholders at all levels of administration

Review of radiological problems of floating nuclear power plants

International Nuclear Information System (INIS)

Rodd, T.

1982-01-01

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

Development of remote handling techniques for the HLLW solidification plant

International Nuclear Information System (INIS)

Tosha, Yoshitsugu; Iwata, Toshio; Inada, Eiichi; Nagaki, Hiroshi; Yamamoto, Masao

1982-01-01

To develop the techniques for the remote maintenance of the equipment in a HLLW (high-level liquid waste) solidification plant, the mock-up test facility (MTF) has been designed and constructed. Before its construction, the specific mock-up equipment was manufactured and tested. The results of the test and the outline of the MTF are described. As the mock-up equipment, a denitrater-concentrator, a ceramic melter and a canister handling equipment were selected. Remote operation was performed according to the maintenance program, and the evaluation of the component was conducted on the easiness of operation, performance, and the suitability to remote handling equipment. As a result of the test, four important elements were identified; they were guides, lifting fixtures, remote handling bolts, and remote pipe connectors. Many improvements of these elements were achieved, and reflected in the design of the MTF. The MTF is a steel-framed and slate-covered building (25 mL x 20 mW x 27 mH) with five storys of test bases. It contains the following four main systems: pretreatment and off-gas treatment system, glass melting system, canister handling system and secondary waste liquid recovery system. Further development of the remote maintenance techniques is expected through the test in the MTF. (Aoki, K.)

Radiology and Enterprise Medical Imaging Extensions (REMIX).

Science.gov (United States)

Erdal, Barbaros S; Prevedello, Luciano M; Qian, Songyue; Demirer, Mutlu; Little, Kevin; Ryu, John; O'Donnell, Thomas; White, Richard D

2018-02-01

Radiology and Enterprise Medical Imaging Extensions (REMIX) is a platform originally designed to both support the medical imaging-driven clinical and clinical research operational needs of Department of Radiology of The Ohio State University Wexner Medical Center. REMIX accommodates the storage and handling of "big imaging data," as needed for large multi-disciplinary cancer-focused programs. The evolving REMIX platform contains an array of integrated tools/software packages for the following: (1) server and storage management; (2) image reconstruction; (3) digital pathology; (4) de-identification; (5) business intelligence; (6) texture analysis; and (7) artificial intelligence. These capabilities, along with documentation and guidance, explaining how to interact with a commercial system (e.g., PACS, EHR, commercial database) that currently exists in clinical environments, are to be made freely available.

Radiological conditions and experiences in the TMI-2 Auxiliary Building

International Nuclear Information System (INIS)

Ruhter, P.E.; Zurliene, W.G.

1988-01-01

Although the radiological conditions following the TMI-2 accident were extraordinary, those that had a potential impact on personnel were largely confined to the Auxiliary and Fuel Handling Building. The most significant pathway was the Letdown and Make-Up and Purification System. Dose rates in some locations in the Aux/Fuel Handling Buildings were in excess of 3 mSv/s (1000 R/h) during the first few days following the accident. They decreased after three to four days and stabilized after about one week. Airborne radioactivity levels were initially due to the release of noble gases, and subsequently due to resuspension of surface contamination. During the first month, the mixture of fission products in the reactor coolant change from one of largely cesium to where the strontium and cesium were about equal in radiological importance. This created some very high beta radiation levels. The significant strontium levels caused the contamination control limit to be reduced to one-half of the pre-accident limit. 5 refs., 6 figs

High level radioactive waste repositories. Task 3. Review of underground handling and emplacement. 1. Executive summary

Energy Technology Data Exchange (ETDEWEB)

1981-01-01

A review is presented of proposals for transport, handling and emplacement of high-level radioactive waste in an underground repository appropriate to the U.K. context, with particular reference to waste block size and configuration; self-shielded or partially-shielded block; stages of disposal; transport by road/rail to repository site; handling techniques within repository; emplacement in vertical holes or horizontal tunnels; repository access by adit, incline or shaft; conventional and radiological safety; costs; and major areas of uncertainty requiring research or development.

NDMA guidelines on management of nuclear and radiological emergencies

International Nuclear Information System (INIS)

Abani, M.C.

2011-01-01

The National Disaster Management Authority (NDMA), ever since it's formation as an apex policy making body for the country in the field of disaster management, has formulated a set of guidelines to assist the various ministries, states and stakeholders in preparing their plans to handle different types of disasters. The guidelines on management of nuclear and radiological emergencies assume great importance in the present context, as our country has very ambitious programme to exploit nuclear energy for peaceful uses. Though, we have an enviable and impeccable record of safety and virtually fail-safe operations in all our nuclear establishments, the possibility, however, remote it may be, of human error, systems failure, sabotage, earthquake, floods, terrorist attacks etc leading to the release of radioactive material in the public domain, cannot be entirely ruled out. With this view, it was decided to prepare the national guidelines by NDMA to manage any nuclear/radiological emergency in public domain. Through these guidelines, we aim to further strengthen our existing nuclear/radiological emergency management framework and generate public awareness, which will go a long way in allaying misapprehensions, if any, amongst the public about the country's nuclear programme. Like in all our guidelines for handling of different types of the disasters, in these Guidelines also, maximum emphasis has been laid on the prevention of nuclear and radiological emergencies, along with a detailed consideration of all other elements of the disaster management continuum. The national guidelines have been prepared and a consensus was arrived on various issues, after widespread consultations and elaborates discussions amongst experts as well as stakeholders. It is assumed that once these guidelines are implemented by the stakeholders and converted into action plans followed by SOPs that will further reduce the chances of accidents in the nuclear arena. (author)

Automated calibration of TECAN genesis liquid handling workstation utilizing an online balance and density meter.

Science.gov (United States)

Xie, Iris H; Wang, Michael H; Carpenter, Richard; Wu, Henry Y

2004-02-01

With robotics widely used in bioanalytical assays, accurate system performance is essential to ensure the quality and productivity of the robotics. In our lab, an automated calibration procedure has been developed to evaluate the precision and accuracy of the TECAN (Research Triangle Park, NC, U.S.A.) Genesis liquid handling system in a bioanalytical laboratory setting. The calibrations were performed by transferring and weighing the solvents automatically on a microbalance controlled by a Gemini program. From the data acquired, calibration reports were generated using a template. The novel aspect of this approach is the use of an on-line balance and a density meter, both of which combine to make the calibration process simple, efficient, and precise. For quantitative bioanalysis, a variety of solvents, including methanol, water, mixed solvents, and plasma, are typically used to prepare standards and unknown samples. Density information is usually unknown for the mixed solvents, and the density of plasma can vary from species to species. However, with the use of a universal density meter, the density could be obtained in seconds. The issue of solvent evaporation during the calibration process was also addressed. Calibration curves were set up for various liquid classes. Pipetting volumes ranged from 10 microL to 900 microL. Precision and accuracy results obtained from the semiannual performance evaluations showed this procedure to be reliable and user-friendly. Using the automated calibration procedure, the calibration and performance evaluation of the robotic system is considerably more efficient, and the incidence of unacceptable precision and accuracy is greatly reduced.

Radiological Characterization Methodology for INEEL-Stored Remote-Handled Transuranic (RH TRU) Waste from Argonne National Laboratory-East

International Nuclear Information System (INIS)

Kuan, P.; Bhatt, R.N.

2003-01-01

An Acceptable Knowledge (AK)-based radiological characterization methodology is being developed for RH TRU waste generated from ANL-E hot cell operations performed on fuel elements irradiated in the EBR-II reactor. The methodology relies on AK for composition of the fresh fuel elements, their irradiation history, and the waste generation and collection processes. Radiological characterization of the waste involves the estimates of the quantities of significant fission products and transuranic isotopes in the waste. Methods based on reactor and physics principles are used to achieve these estimates. Because of the availability of AK and the robustness of the calculation methods, the AK-based characterization methodology offers a superior alternative to traditional waste assay techniques. Using the methodology, it is shown that the radiological parameters of a test batch of ANL-E waste is well within the proposed WIPP Waste Acceptance Criteria limits

Radiological departments. Chapter 4.3.5

International Nuclear Information System (INIS)

1983-01-01

The book deals with the problems of health, labor and fire protection in the public health service of the GDR as a whole. A special chapter treats these items concerning the conditions in radiological departments. In this connection the main legal regulations are presented. Introducing remarks on generation and properties of ionizing radiations and on biological radiation effects are outlined. Further, the responsibilities in radiation protection, maximum permissible radiation doses and the handling of X-ray devices, sealed and unsealed radiation sources are discussed

Confinement facilities for handling plutonium

International Nuclear Information System (INIS)

Maraman, W.J.; McNeese, W.D.; Stafford, R.G.

1975-01-01

Plutonium handling on a multigram scale began in 1944. Early criteria, equipment, and techniques for confining contamination have been superseded by more stringent criteria and vastly improved equipment and techniques for in-process contamination control, effluent air cleaning and treatment of liquid wastes. This paper describes the evolution of equipment and practices to minimize exposure of workers and escape of contamination into work areas and into the environment. Early and current contamination controls are compared. (author)

Radiological impacts of spent nuclear fuel management options

International Nuclear Information System (INIS)

Riotte, H.; Lazo, T.; Mundigl, S.

2000-01-01

An important technical study on radiological impacts of spent nuclear fuel management options, recently completed by the NEA, is intended to facilitate informed international discussions on the nuclear fuel cycle. The study compares the radiological impacts on the public and on nuclear workers resulting from two approaches to handling spent fuel from nuclear power plants: - the reprocessing option, that includes the recycling of spent uranium fuel, the reuse of the separated plutonium in MOX fuel, and the direct disposal of spent MOX fuel; and the once-through option, with no reprocessing of spent fuel, and its direct disposal. Based on the detailed research of a group of 18 internationally recognised experts, under NEA sponsorship, the report concludes that: The radiological impacts of both the reprocessing and the non-reprocessing fuel cycles studied are small, well below any regulatory dose limits for the public and for workers, and insignificantly low as compared with exposures caused by natural radiation. The difference in the radiological impacts of the two fuel cycles studied does not provide a compelling argument in favour of one option or the other. The study also points out that other factors, such as resource utilisation efficiency, energy security, and social and economic considerations would tend to carry more weight than radiological impacts in decision-making processes. (authors)

Traumatic Globe Subluxation and Intracranial Injury Caused by Bicycle Brake Handle.

Science.gov (United States)

Poroy, Ceren; Cibik, Cansu; Yazici, Bulent

2016-09-01

Penetration of a bicycle brake handle into the orbit is a rare and serious type of trauma. Globe subluxation due to such trauma has not been previously reported. A 10-year-old girl presented after falling from a bicycle, which resulted in the handbrake penetrating her right upper eyelid. On examination, the globe was subluxated anteriorly, there was no light perception, and the pupilla was fixed and dilated. Radiologic studies revealed orbitonasal fractures, hemorrhage, emphysema in the orbit and cranium, and rupture of the extraocular muscles. The globe was replaced into the orbit with the help of lateral cantholysis and orbital septotomy. During 22 months of follow-up, the globe remained intact, but total loss of vision, blepharoptosis, and extraocular motility restriction persisted. This case and previous reports show that bicycle brake handles can cause severe, penetrating orbital and cerebral traumas that can result in vision loss or fatality. Brake handles should be designed to protect bicyclists from such injuries.

Safe Handling of Radioisotopes. Health Physics Addendum

Energy Technology Data Exchange (ETDEWEB)

Appleton, G J; Krishnamoorthy, P N

1960-07-15

The International Atomic Energy Agency published in 1958 a Manual entitled ''Safe Handling of Radioisotopes'' (Safety Series No. 1 - STI/PUB/1), based on the work of an international panel convened by the Agency. As recommended by that panel and approved by the Agency's Board of Governors, this Addendum has now been prepared, primarily as a supplement to the Manual. It contains technical information necessary for the implementation of the controls given in the Manual. In addition, it is intended to serve as a brief introduction to the technical problems encountered in radiological protection work and to the methods of resolving them. As in the case of the Manual itself, the information given in this Addendum is particularly relevant to the problems encountered by the small user of radioisotopes. Although the basic principles set forth in it apply to all work with radiation sources, the Addendum is not intended to serve as a radiological protection manual for use in reactor installations or large-scale nuclear industry, where more specialized techniques and information are required.

Safe Handling of Radioisotopes. Health Physics Addendum

International Nuclear Information System (INIS)

Appleton, G.J.; Krishnamoorthy, P.N.

1960-01-01

The International Atomic Energy Agency published in 1958 a Manual entitled ''Safe Handling of Radioisotopes'' (Safety Series No. 1 - STI/PUB/1), based on the work of an international panel convened by the Agency. As recommended by that panel and approved by the Agency's Board of Governors, this Addendum has now been prepared, primarily as a supplement to the Manual. It contains technical information necessary for the implementation of the controls given in the Manual. In addition, it is intended to serve as a brief introduction to the technical problems encountered in radiological protection work and to the methods of resolving them. As in the case of the Manual itself, the information given in this Addendum is particularly relevant to the problems encountered by the small user of radioisotopes. Although the basic principles set forth in it apply to all work with radiation sources, the Addendum is not intended to serve as a radiological protection manual for use in reactor installations or large-scale nuclear industry, where more specialized techniques and information are required.

Radiological implications of plutonium recycle and the use of thorium fuels in power reactor operations

Energy Technology Data Exchange (ETDEWEB)

Macdonald, H. F.

1976-01-15

As economically attractive sources of natural uranium are gradually depleted attention will turn to recycling plutonium or to the use of thorium fuels. The radiological implications of these fuel cycles in terms of fuel handling and radioactive waste disposal are investigated in relation to a conventional /sup 235/U enriched oxide fuel. It is suggested that a comparative study of this nature may be an important aspect of the overall optimization of future fuel cycle strategies. It is shown that the use of thorium based fuels has distinct advantages in terms of neutron dose rates from irradiated fuels and long term proportional to decay heating commitment compared with conventional uranium/plutonium fuels. However, this introduces a ..gamma.. dose rate problem in the fabrication and handling of unirradiated /sup 233/U fuels. For both plutonium and thorium fuels these radiological problems increase during storage of the fuel prior to reactor irradiation. The novel health physics problems which arise in the handling and processing of thorium fuels are reviewed in an appendix.

Radiological accidents balance in medicine

International Nuclear Information System (INIS)

Nenot, J.C.

1995-01-01

This work deals with the radiological accidents in medicine. In medicine, the radiation accidents on medical personnel and patients can be the result of over dosage and bad focusing of radiotherapy sealed sources. Sometimes, the accidents, if they are unknown during a time enough for the source to be spread and to expose a lot of persons (in the case of source dismantling for instance) can take considerable dimensions. Others accidents can come from bad handling of linear accelerators and from radionuclide kinetics in some therapies. Some examples of accidents are given. (O.L.). 11 refs

Radiological protection criteria risk assessments for waste disposal options

International Nuclear Information System (INIS)

Hill, M.D.

1982-01-01

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

340 Waste handling Facility Hazard Categorization and Safety Analysis

International Nuclear Information System (INIS)

Rodovsky, T.J.

2010-01-01

The analysis presented in this document provides the basis for categorizing the facility as less than Hazard Category 3. The final hazard categorization for the deactivated 340 Waste Handling Facility (340 Facility) is presented in this document. This hazard categorization was prepared in accordance with DOE-STD-1 027-92, Change Notice 1, Hazard Categorization and Accident Analysis Techniques for Compliance with Doe Order 5480.23, Nuclear Safety Analysis Reports. The analysis presented in this document provides the basis for categorizing the facility as less than Hazard Category (HC) 3. Routine nuclear waste receiving, storage, handling, and shipping operations at the 340 Facility have been deactivated, however, the facility contains a small amount of radioactive liquid and/or dry saltcake in two underground vault tanks. A seismic event and hydrogen deflagration were selected as bounding accidents. The generation of hydrogen in the vault tanks without active ventilation was determined to achieve a steady state volume of 0.33%, which is significantly less than the lower flammability limit of 4%. Therefore, a hydrogen deflagration is not possible in these tanks. The unmitigated release from a seismic event was used to categorize the facility consistent with the process defined in Nuclear Safety Technical Position (NSTP) 2002-2. The final sum-of-fractions calculation concluded that the facility is less than HC 3. The analysis did not identify any required engineered controls or design features. The Administrative Controls that were derived from the analysis are: (1) radiological inventory control, (2) facility change control, and (3) Safety Management Programs (SMPs). The facility configuration and radiological inventory shall be controlled to ensure that the assumptions in the analysis remain valid. The facility commitment to SMPs protects the integrity of the facility and environment by ensuring training, emergency response, and radiation protection. The full scale

ICPP radiological and toxicological sabotage analysis

International Nuclear Information System (INIS)

Kubiak, V.R.; Mortensen, F.G.

1995-01-01

In June of 1993, the Department of Energy (DOE) issued Notice 5630.3A, open-quotes Protection of Departmental Facilities Against Radiological and Toxicological Sabotage,close quotes which states that all significant radiological and toxicological hazards at Department facilities must be examined for potential sabotage. This analysis has been completed at the Idaho Chemical Processing Plant (ICPP). The ICPP radiological and toxicological hazards include spent government and commercial fuels, Special Nuclear Materials (SNM), high-level liquid wastes, high-level solid wastes, and process and decontamination chemicals. The analysis effort included identification and assessment of quantities of hazardous materials present at the facility; identification and ranking of hazardous material targets; development of worst case scenarios detailing possible sabotage actions and hazard releases; performance of vulnerability assessments using table top and computer methodologies on credible threat targets; evaluation of potential risks to the public, workers, and the environment; evaluation of sabotage risk reduction options; and selection of cost effective prevention and mitigation options

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

Lessons learned from radiological accidents at medical exposures in radiotherapy

International Nuclear Information System (INIS)

Fagundes, J.S.; Ferreira, A.F.; Lima, C.M.A.; Silva, F.C.A. da

2017-01-01

An exposure is considered accidental in radiotherapy when there is a substantial deviation in the prescription of treatment. In this work, an analysis of published radiological accidents, both in Brazil and internationally, was performed during medical exposures in radiotherapy treatments, removing the main lessons learned. Of the research carried out, we highlight Brazil with four radiological accidents and one death in the period between 2011 and 2014; the United States of America with 169 accidents with two deaths from 2000 to 2010 and France from 2001 to 2014 had 569 deaths without patients. Lessons learned have been described, for example, that maintenance personnel training should specify limitations or restrictions on the handling or adjustment of critical parts on the accelerator. It is recommended to apply the 10 main lessons learned due to radiological accidents during medical exposures in radiotherapy treatments to avoid future events

340 Waste Handling Facility interim safety basis

International Nuclear Information System (INIS)

Bendixsen, R.B.

1995-01-01

This document establishes the interim safety basis (ISB) for the 340 Waste Handling Facility (340 Facility). An ISB is a documented safety basis that provides a justification for the continued operation of the facility until an upgraded final safety analysis report is prepared that complies with US Department of Energy (DOE) Order 5480.23, Nuclear Safety Analysis Reports. The ISB for the 340 Facility documents the current design and operation of the facility. The 340 Facility ISB (ISB-003) is based on a facility walkdown and review of the design and operation of the facility, as described in the existing safety documentation. The safety documents reviewed, to develop ISB-003, include the following: OSD-SW-153-0001, Operating Specification Document for the 340 Waste Handling Facility (WHC 1990); OSR-SW-152-00003, Operating Limits for the 340 Waste Handling Facility (WHC 1989); SD-RE-SAP-013, Safety Analysis Report for Packaging, Railroad Liquid Waste Tank Cars (Mercado 1993); SD-WM-TM-001, Safety Assessment Document for the 340 Waste Handling Facility (Berneski 1994a); SD-WM-SEL-016, 340 Facility Safety Equipment List (Berneski 1992); and 340 Complex Fire Hazard Analysis, Draft (Hughes Assoc. Inc. 1994)

Relocation tabletop exercise: federal radiological response in the post-accident phase

International Nuclear Information System (INIS)

Grant, K.; Adler, M.V.; Wolff, W.F.

1986-01-01

The federal Radiological Emergency Response Plan (FRERP) was developed to provide the framework for coordinating federal radiological assistance to states and to local authorities faced with a large radiological accident. The Relocation Tabletop Exercise was conducted on December 9-11, 1985 at the Beaver Valley Power Station, the site of the simulated accident. The exercise scenario had postulated a substantial release of radioactive materials from a fuel handling accident at the Beaver Valley Power Station in Shippingport, Pennsylvania, leaving radioactive materisls deposited over part of the surrounding area. The exercise was structured as a sequential series of nice mini-scenarios, each of which focused on one problems. The exercise was intended to identify issues and problems which needed consideration or procedures which might need to be developed for this post-accident phase. It was a ''no-fault'' excercise

WASTE HANDLING BUILDING FIRE PROTECTION SYSTEM DESCRIPTION DOCUMENT

Energy Technology Data Exchange (ETDEWEB)

J. D. Bigbee

2000-06-21

The Waste Handling Building Fire Protection System provides the capability to detect, control, and extinguish fires and/or mitigate explosions throughout the Waste Handling Building (WHB). Fire protection includes appropriate water-based and non-water-based suppression, as appropriate, and includes the distribution and delivery systems for the fire suppression agents. The Waste Handling Building Fire Protection System includes fire or explosion detection panel(s) controlling various detectors, system actuation, annunciators, equipment controls, and signal outputs. The system interfaces with the Waste Handling Building System for mounting of fire protection equipment and components, location of fire suppression equipment, suppression agent runoff, and locating fire rated barriers. The system interfaces with the Waste Handling Building System for adequate drainage and removal capabilities of liquid runoff resulting from fire protection discharges. The system interfaces with the Waste Handling Building Electrical Distribution System for power to operate, and with the Site Fire Protection System for fire protection water supply to automatic sprinklers, standpipes, and hose stations. The system interfaces with the Site Fire Protection System for fire signal transmission outside the WHB as needed to respond to a fire emergency, and with the Waste Handling Building Ventilation System to detect smoke and fire in specific areas, to protect building high-efficiency particulate air (HEPA) filters, and to control portions of the Waste Handling Building Ventilation System for smoke management and manual override capability. The system interfaces with the Monitored Geologic Repository (MGR) Operations Monitoring and Control System for annunciation, and condition status.

WASTE HANDLING BUILDING FIRE PROTECTION SYSTEM DESCRIPTION DOCUMENT

International Nuclear Information System (INIS)

J. D. Bigbee

2000-01-01

The Waste Handling Building Fire Protection System provides the capability to detect, control, and extinguish fires and/or mitigate explosions throughout the Waste Handling Building (WHB). Fire protection includes appropriate water-based and non-water-based suppression, as appropriate, and includes the distribution and delivery systems for the fire suppression agents. The Waste Handling Building Fire Protection System includes fire or explosion detection panel(s) controlling various detectors, system actuation, annunciators, equipment controls, and signal outputs. The system interfaces with the Waste Handling Building System for mounting of fire protection equipment and components, location of fire suppression equipment, suppression agent runoff, and locating fire rated barriers. The system interfaces with the Waste Handling Building System for adequate drainage and removal capabilities of liquid runoff resulting from fire protection discharges. The system interfaces with the Waste Handling Building Electrical Distribution System for power to operate, and with the Site Fire Protection System for fire protection water supply to automatic sprinklers, standpipes, and hose stations. The system interfaces with the Site Fire Protection System for fire signal transmission outside the WHB as needed to respond to a fire emergency, and with the Waste Handling Building Ventilation System to detect smoke and fire in specific areas, to protect building high-efficiency particulate air (HEPA) filters, and to control portions of the Waste Handling Building Ventilation System for smoke management and manual override capability. The system interfaces with the Monitored Geologic Repository (MGR) Operations Monitoring and Control System for annunciation, and condition status

Liquid waste handling facilities for a conceptual LWR spent fuel reprocessing complex

International Nuclear Information System (INIS)

Witt, D.C.; Bradley, R.F.

1978-01-01

The waste evaporator systems and the methods for evaporating the liquid wastes of various radioactivity levels are discussed. After the liquid wastes are evaporated and nitric acid is recovered the high-level liquid waste is incorporated into borosilicate glass and the intermediate-level liquid waste into concrete for final disposal

Quality assurance and assessment of preparedness at DAE-ERCs for handling radiological emergencies in public domain

International Nuclear Information System (INIS)

Sharma, R.; Murali, S.; Singh, Rajvir; Pradeepkumar, K.S.

2014-01-01

The radiological emergencies are very rare in occurrence the mechanism to improve the preparedness can be ensured through conducting mock exercises/drills. Emergency kit comprises of adequate number of radiation monitoring equipments and PPEs required for response is kept in readiness at ERC. There is a need of training modules on radiological emergencies for all stake holders e.g. district officials, Local Police, Medical professionals and National Disaster Response Force (NDRF) to improve the knowledge and response capability. The adaptability to situations is important for ERTs based on the lessons learned from emergency at Mayapuri, Delhi. The role and responsibility of different agencies have been identified and drafted in the preparedness plan to meet the challenges during response

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

OpenAIRE

Talanow, Roland

2010-01-01

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

Radiology

International Nuclear Information System (INIS)

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

1990-01-01

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

Handling and transport problems (1960)

International Nuclear Information System (INIS)

Pomarola, J.; Savouyaud, J.

1960-01-01

I. The handling and transport of radioactive wastes involves the danger of irradiation and contamination. It is indispensable: - to lay down a special set of rules governing the removal and transport of wastes within centres or from one centre to another; - to give charge of this transportation to a group containing teams of specialists. The organisation, equipment and output of these teams is being examined. II. Certain materials are particularly dangerous to transport, and for these special vehicles and fixed installations are necessary. This is the case especially for the evacuation of very active liquids. A transport vehicle is described, consisting of a trailer tractor and a recipient holding 500 litres of liquid of which the activity can reach 1000 C/l; the decanting operation, the route to be followed by the vehicle, and the precautions taken are also described. (author) [fr

Computer imaging of EBR-II handling equipment

International Nuclear Information System (INIS)

Hansen, L.H.; Peters, G.G.

1994-10-01

This paper describes a three-dimensional graphics application used to visualize the positions of remotely operated fuel handling equipment in the EBR-II reactor. The system described in this paper uses actual signals to move a three-dimensional graphics model in real-time in response to movements of equipment in the plant. A three-dimensional (3D) visualization technique is necessary to simulate direct visual observation of the transfers of fuel and experiments into and out of the reactor because the fuel handling equipment is submerged in liquid sodium and therefore is not visible to the operator. This paper will present details on how the 3D model was created and how real-time dynamic behavior was added to each of the moving components

A methodology for radiological accidents analysis in industrial gamma radiography

International Nuclear Information System (INIS)

Silva, F.C.A. da.

1990-01-01

A critical review of 34 published severe radiological accidents in industrial gamma radiography, that happened in 15 countries, from 1960 to 1988, was performed. The most frequent causes, consequences and dose estimation methods were analysed, aiming to stablish better procedures of radiation safety and accidents analysis. The objective of this work is to elaborate a radiological accidents analysis methodology in industrial gamma radiography. The suggested methodology will enable professionals to determine the true causes of the event and to estimate the dose with a good certainty. The technical analytical tree, recommended by International Atomic Energy Agency to perform radiation protection and nuclear safety programs, was adopted in the elaboration of the suggested methodology. The viability of the use of the Electron Gamma Shower 4 Computer Code System to calculate the absorbed dose in radiological accidents in industrial gamma radiography, mainly at sup(192)Ir radioactive source handling situations was also studied. (author)

Musculoskeletal injuries resulting from patient handling tasks among hospital workers.

Science.gov (United States)

Pompeii, Lisa A; Lipscomb, Hester J; Schoenfisch, Ashley L; Dement, John M

2009-07-01

The purpose of this study was to evaluate musculoskeletal injuries and disorders resulting from patient handling prior to the implementation of a "minimal manual lift" policy at a large tertiary care medical center. We sought to define the circumstances surrounding patient handling injuries and to identify potential preventive measures. Human resources data were used to define the cohort and their time at work. Workers' compensation records (1997-2003) were utilized to identify work-related musculoskeletal claims, while the workers' description of injury was used to identify those that resulted from patient handling. Adjusted rate ratios were generated using Poisson regression. One-third (n = 876) of all musculoskeletal injuries resulted from patient handling activities. Most (83%) of the injury burden was incurred by inpatient nurses, nurses' aides and radiology technicians, while injury rates were highest for nurses' aides (8.8/100 full-time equivalent, FTEs) and smaller workgroups including emergency medical technicians (10.3/100 FTEs), patient transporters (4.3/100 FTEs), operating room technicians (3.1/100 FTEs), and morgue technicians (2.2/100 FTEs). Forty percent of injuries due to lifting/transferring patients may have been prevented through the use of mechanical lift equipment, while 32% of injuries resulting from repositioning/turning patients, pulling patients up in bed, or catching falling patients may not have been prevented by the use of lift equipment. The use of mechanical lift equipment could significantly reduce the risk of some patient handling injuries but additional interventions need to be considered that address other patient handling tasks. Smaller high-risk workgroups should not be neglected in prevention efforts.

Order of 2 May 1977 on a proficiency certificate for handling industrial radioscopy and radiography equipment

International Nuclear Information System (INIS)

1977-01-01

This Order lays down that any person handling industrial radioscopy or radiography equipment must obtain a proficiency certificate delivered by a regional jury made up of the regional director for labour and manpower or his representative, a physician competent for industrial medicine and specialized in radiation protection and an expert in industrial radiology. (NEA) [fr

Preliminary criteria for the handling of radioactive tea

International Nuclear Information System (INIS)

Oezemre, A.Y.

1993-01-01

Two years after the Chernobyl accident, tea plantations in northeastern Turkey, at Rize and its surroundings especially, were affected by radioactive fallout. As a radiological countermeasure, the turkish Atomic energy commission (AEC) was called in before tea packing and set up a maximum permissible limit of 12,500 Bq/kg for dry tea in the market; 58,078 t of radioactive tea (≥ 25,000 Bq/kg) were set apart as radioactive waste. In its concern to determine the best solution about the handling of radioactive tea and considering the national conditions, the AEC developed four preliminary criteria that led to select the burial option. (author)

Secondary limits of exposure in facilities handling uranium

International Nuclear Information System (INIS)

Raghavayya, M.

1999-08-01

Annual limits of exposure and intake for radiation workers in nuclear installations have been recommended by the International Commission on Radiological Protection and the same have been adopted by the Indian Atomic Energy Regulatory Board for all the radionuclides of interest. The prescribed limits cannot be directly used for day to day radiation protection work. Hence secondary limits have to be derived for routine applications. The modeling steps may be simple in some situations and more complicated in some others. The limits recommended are for individual radionuclides. But in facilities handling natural or enriched uranium the radionuclides (isotopes of uranium and its decay products) generally occur together in specific ratios. Derivation of secondary limits has to take this into consideration. The present document is an attempt at deriving the secondary limits required for routine application in facilities handling uranium (Mine, mill, refineries and fuel fabrication etc.). Secondary limits of exposure have been derived in this document for air borne activity, activity in water, surface contamination and internal exposures. (author)

Regulatory inspection practices for industrial safety (electrical, mechanical, material handling and conventional aspects)

International Nuclear Information System (INIS)

Agarwal, K.

2017-01-01

Regulatory Inspection (RI) of BARC facilities and projects are carried out under the guidance of BARC Safety Council (BSC) Secretariat. Basically facilities and projects have been divided into two board categories viz. radiological facilities and non-radiological facilities. The Rls of radiological facilities should be carried out under OPSRC and of non-radiological facilities under CFSRC. Periodicity of inspection shall be at least once in a year. The RI of projects is carried out under concerned DSRC. RI practices with industrial safety which includes electrical, mechanical, material handling and conventional aspect for these facilities starts with check lists. The inspection areas are prepared in the form of checklists which includes availability of approved documents, compliance status of previous RIT and various safety committee's recommendations, radiological status of facilities, prompt reporting of safety related unusual occurrences, major incident, site visit for verification of actual status of system/plant. The practices for inspection in the area of electrical safety shall include checking of maintenance procedure for all critical class IV system equipment's such as HT panel, LT panel, transformer and motors. Load testing of Class III system such as D.G. set etc. shall be carried out as technical specification surveillance schedule. Status of aviation lights, number of qualified staff, availability of qualified staff etc. shall be form of inspection

Fertility status of males working in radiology departments of teaching hospitals

International Nuclear Information System (INIS)

Goyal, O.P.; Jain, A.K.; Sankhla, D.K.; Kothari, L.K.; Agarwal, G.R.

1985-01-01

All the 33 male doctors and para-medical staff employed in the radiology departments of two teaching hospitals have been studied for their fertility status. Their mean age was 32.5 years and they had been doing radiological work for 8.6 years on an average. Out of the 33 males, all of whom were married, one had primary infertility with severe oligospermia. He was successfully treated with oral vitamin A and E along with a 3-month off from handling x-ray machines; the child born was healthy and normal. Another 5 subjects had been married for only less than two years and their seminograms were essentially normal. They were classified as 'Unproven fertility'. The remaining 27 persons had fathered 61 children-16 born before the father had started working in radiology and 45 conceived later. There was 1 case of still-birth and 1 of microcephaly. However, the overall incidence of infertility and congenital defects was not significantly different than in the general population. (author)

Risk-Based Radioactive Liquid Effluent Monitoring Requirements at the U. S. Department of Energy's Savannah River Site

International Nuclear Information System (INIS)

Jannik, G.T.

2001-01-01

For Department of Energy (DOE) facilities, clear regulatory guidance exists for structuring radiological air emissions monitoring programs. However, there are no parallel regulations for radiological liquid effluent monitoring programs. In order to bridge this gap and to technically justify liquid effluent monitoring decisions at DOE's Savannah River Site, a graded, risk-basked approach has been established to determine the monitoring and sampling criteria to be applied at each liquid discharge point

Work plan for the radiological survey for the David Witherspoon, Incorporated, Landfill-1630 site, Knoxville, Tennessee

International Nuclear Information System (INIS)

1996-07-01

This work plan establishes the methods and requirements for performing a radiological survey at the David Witherspoon, Incorporated, Landfill-1630 Site, Knoxville, Tennessee (DWI 1630 Site) in accordance with requirements under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). The radiological survey will identify the radiological contamination level of the equipment and debris stored at the DWI 1630 Site. The data generated from the survey activities will support the decisions for characterization of the equipment/debris and aid in subsequent disposition and waste handling. The survey activities to be performed under this work plan include an equipment radiological survey, a walkover survey, and an immunoassay testing for polychlorinated biphenyls (PCBs). This work plan includes a quality assurance (QA)/quality control (QC) project plan, a health and safety (H ampersand S) plan, and a waste management plan

18 CFR 1304.405 - Fuel storage tanks and handling facilities.

Science.gov (United States)

2010-04-01

... used to contain a regulated substance (such as a petroleum product) and has 10 percent or more of its... or remedy pollution or violations of law, including removal of the UST system, with costs charged to... flammable and combustible liquids storage tanks at marine service stations. (d) Fuel handling on private...

High-power liquid-lithium target prototype for accelerator-based boron neutron capture therapy.

Science.gov (United States)

Halfon, S; Paul, M; Arenshtam, A; Berkovits, D; Bisyakoev, M; Eliyahu, I; Feinberg, G; Hazenshprung, N; Kijel, D; Nagler, A; Silverman, I

2011-12-01

A prototype of a compact Liquid-Lithium Target (LiLiT), which will possibly constitute an accelerator-based intense neutron source for Boron Neutron Capture Therapy (BNCT) in hospitals, was built. The LiLiT setup is presently being commissioned at Soreq Nuclear Research Center (SNRC). The liquid-lithium target will produce neutrons through the (7)Li(p,n)(7)Be reaction and it will overcome the major problem of removing the thermal power generated using a high-intensity proton beam (>10 kW), necessary for sufficient neutron flux. In off-line circulation tests, the liquid-lithium loop generated a stable lithium jet at high velocity, on a concave supporting wall; the concept will first be tested using a high-power electron beam impinging on the lithium jet. High intensity proton beam irradiation (1.91-2.5 MeV, 2-4 mA) will take place at Soreq Applied Research Accelerator Facility (SARAF) superconducting linear accelerator currently in construction at SNRC. Radiological risks due to the (7)Be produced in the reaction were studied and will be handled through a proper design, including a cold trap and appropriate shielding. A moderator/reflector assembly is planned according to a Monte Carlo simulation, to create a neutron spectrum and intensity maximally effective to the treatment and to reduce prompt gamma radiation dose risks. Copyright © 2011 Elsevier Ltd. All rights reserved.

Handling and carrying head for nuclear fuel assemblies and installation including this head

International Nuclear Information System (INIS)

Artaud, R.; Cransac, J.P.; Jogand, P.

1986-01-01

The present invention proposes a handling and carrying head ensuring efficiently the cooling of the nuclear fuel asemblies it transports so that any storage in liquid metal in a drum within or adjacent the reactor vessel is suppressed. The invention claims also a nuclear fuel handling installation including the head; it allows a longer time between loading and unloading campaigns and the space surrounding the reactor vessel keeps free without occupying a storage zone within the vessel [fr

Remote, under-sodium fuel handling experience at EBR-II

International Nuclear Information System (INIS)

King, R.W.; Planchon, H.P.

1995-01-01

The EBR-II is a pool-type design; the reactor fuel handling components and entire primary-sodium coolant system are submerged in the primary tank, which is 26 feet in diameter, 26 feet high, and contains 86,000 gallons of sodium. Since the reactor is submerged in sodium, fuel handling operations must be performed blind, making exact positioning and precision control of the fuel handling system components essential. EBR-II operated for 30 years, and the fuel handling system has performed approximately 25,000 fuel transfer operations in that time. Due to termination of the IFR program, EBR-II was shut down on September 30, 1994. In preparation for decommissioning, all fuel in the reactor will be transferred out of EBR-II to interim storage. This intensive fuel handling campaign will last approximately two years, and the number of transfers will be equivalent to the fuel handling done over about nine years of normal reactor operation. With this demand on the system, system reliability will be extremely important. Because of this increased demand, and considering that the system has been operating for about 32 years, system upgrades to increase reliability and efficiency are proceeding. Upgrades to the system to install new digital, solid state controls, and to take advantage of new visualization technology, are underway. Future reactor designs using liquid metal coolant will be able to incorporate imaging technology now being investigated, such as ultraviolet laser imaging and ultrasonic imaging

Dust prevention in bulk material transportation and handling

Science.gov (United States)

Kirichenko, A. V.; Kuznetsov, A. L.; Pogodin, V. A.

2017-10-01

The environmental problem of territory and atmosphere pollution caused by transportation and handling of dust-generating bulk cargo materials is quite common for the whole world. The reducing of weight of fine class coal caused by air blowing reaches the level of 0.5-0.6 t per railcar over the 500 km transportation distance, which is equal to the loss of 1 % of the total weight. The studies showed that all over the country in the process of the railroad transportation, the industry loses 3-5 metric tonnes of coal annually. There are several common tactical measurers to prevent dust formation: treating the dust-producing materials at dispatch point with special liquid solutions; watering the stacks and open handling points of materials; frequent dust removing and working area cleaning. Recently there appeared several new radical measures for pollution prevention in export of ore and coal materials via sea port terminals, specifically: wind-dust protection screens, the container cargo handling system of delivery materials to the hold of the vessels. The article focuses on the discussion of these measures.

Remote technologies for handling spent fuel

International Nuclear Information System (INIS)

Ramakumar, M.S.

1999-01-01

The nuclear programme in India involves building and operating power and research reactors, production and use of isotopes, fabrication of reactor fuel, reprocessing of irradiated fuel, recovery of plutonium and uranium-233, fabrication of fuel containing plutonium-239, uranium-233, post-irradiation examination of fuel and hardware and handling solid and liquid radioactive wastes. Fuel that could be termed 'spent' in thermal reactors is a source for second generation fuel (plutonium and uranium-233). Therefore, it is only logical to extend remote techniques beyond handling fuel from thermal reactors to fuel from fast reactors, post-irradiation examination etc. Fabrication of fuel containing plutonium and uranium-233 poses challenges in view of restriction on human exposure to radiation. Hence, automation will serve as a step towards remotisation. Automated systems, both rigid and flexible (using robots) need to be developed and implemented. Accounting of fissile material handled by robots in local area networks with appropriate access codes will be possible. While dealing with all these activities, it is essential to pay attention to maintenance and repair of the facilities. Remote techniques are essential here. There are a number of commonalities in these requirements and so development of modularized subsystems, and integration of different configurations should receive attention. On a long-term basis, activities like decontamination, decommissioning of facilities and handling of waste generated have to be addressed. While robotized remote systems have to be designed for existing facilities, future designs of facilities should take into account total operation with robotic remote systems. (author)

Computer imaging of EBR-II fuel handling equipment

International Nuclear Information System (INIS)

Peters, G.G.; Hansen, L.H.

1995-01-01

This paper describes a three-dimensional graphics application used to visualize the positions of remotely operated fuel handling equipment in the EBR-II reactor. A three-dimensional (3D) visualization technique is necessary to simulate direct visual observation of the transfers of fuel and experiments into and out of the reactor because the fuel handling equipment is submerged in liquid sodium and therefore is not visible to the operator. The system described in this paper uses actual signals to drive a three-dimensional computer-generated model in real-time in response to movements of equipment in the plant This paper will present details on how the 3D model of the intank equipment was created and how real-time dynamic behavior was added to each of the moving components

Radiology today

International Nuclear Information System (INIS)

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

1981-01-01

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

Silicon MEMS for Detection of Liquid and Solid Fronts

NARCIS (Netherlands)

Wei, J.

2010-01-01

High-precision manipulation of small-size objects is an attractive and challenging topic for both industrial production and fundamental scientific research. The capability of monitoring micro-samples during handling is essential to the accuracy and efficiency of a handling system for both liquid and

Preliminary radiological analysis of the transportation of contact-handled transuranic waste within the state of New Mexico. Revision 1

International Nuclear Information System (INIS)

Tappen, J.; Fredrickson, C.; Daer, G.

1985-06-01

This analysis assesses the potential radiological impacts on the citizens of New Mexico from the transport of CH-TRU waste to WIPP by rail or by truck. Assuming exclusive use of the truck transport mode, the combined annual exposure to the public from accident-free shipment of waste is estimated to be 3.3 person-rem/year. It is estimated that a theoretical member of the public receiving maximum exposure to the combined truck shipments of CH-TRU waste to WIPP would receive an annual whole body dose equivalent of 0.000016 rem. Such an exposure is insignificant in comparison to the average annual whole body dose equivalent to an individual living in the Colorado Plateau area of between 0.075 and 0.140 rem from natural occurring radiation. The combined annual radiological risk to the public living along the new Mexico truck routes to WIPP from potential accidents is projected as 0.031 person-rem/year. Assuming exclusive use of the rail transport mode, the combined annual exposure to the public from accident-free shipment of waste is estimated to be 1.2 person-rem/year. A theoretical member of the public receiving combined maximum exposure to rail shipments of CH-TRU waste to WIPP would receive an annual whole body dose equivalent of 0.000012 rem. The combined annual radiological risk to the public living along the New Mexico rail routes to WIPP from potential accidents is projected as 0.0022 person-rem/year. An estimate of the radiological impacts in a year of maximum waste receipt can be made by multiplying the above results for rail or truck by 2. This estimate is based upon the WIPP design waste throughput rate of 500,000 ft 3 per year. An estimate of the radiological impacts of CH-TRU waste transport to WIPP over the facility life can be made by multiplying the above results by 25

Manual on safe production, transport, handling and storage of uranium hexafluoride

International Nuclear Information System (INIS)

1994-11-01

This document includes a description of the physical, chemical and radiological properties of UF 6 and related products, including information concerning their production, handling, storage and transportation and the management of the wastes which result. All the operations of UF 6 management are considered form a safety point of view. The IAEA organized a series of meetings to consider the hazards of UF 6 transport since considerable quantities of depleted, natural and enriched UF 6 are transported between nuclear fuel sites. Storage of depleted UF 6 is another important issue. Factors affecting long term storage are presented, especially site choice and cylinder corrosion. Other topics such as waste management, quality assurance and emergency preparedness which contribute to the overall safety of UF 6 handling, are included. The intention of this document is to provide analysis of the safety implications of all stages of UF 6 operations and to draw attention to specific features and properties of importance. 38 refs, figs, tabs

Rotor for processing liquids using movable capillary tubes

Science.gov (United States)

Johnson, W.F.; Burtis, C.A.; Walker, W.A.

1987-07-17

A rotor assembly for processing liquids, especially whole blood samples, is disclosed. The assembly includes apparatus for separating non-liquid components of whole blood samples from liquid components, apparatus for diluting the separated liquid component with a diluent and apparatus for transferring the diluted sample to an external apparatus for analysis. The rotor assembly employs several movable capillary tubes to handle the sample and diluents. A method for using the rotor assembly to process liquids is also described. 5 figs.

Air/liquid collectors

DEFF Research Database (Denmark)

Jensen, Søren Østergaard; Olesen, Ole; Kristiansen, Finn Harken

1997-01-01

this kind of collectors. The modified simulation program has been used for the determination of the surplus in performance which solar heating systems with this type of solar collectors for combined preheating of ventilation air and domestic hot water will have. The simulation program and the efficiency......This report determine efficiency equations for combined air/liquid solar collectors by measurements on to different air/liquid collectors. Equations which contain all relevant informations on the solar collectors. A simulation program (Kviksol) has been modified in order to be able to handle...

Needle stick injury in a radiology department: a decade analysis

International Nuclear Information System (INIS)

Sayani, R.; Rajani, A.

2012-01-01

Objectives: To determine the frequency of needle stick injury in health care workers of radiology department. Study type, settings and duration: Cross sectional, observational study conducted at the Radiology department of Aga Khan University hospital from January 2000 to May 2010. Subject and Methods: All self-reported needle stick injuries data of Health care workers of radiology department was recorded. The personnel involved (Radiologist, resident, radiographer, nurses etc), area of working and the causes of injury were identified including the procedural or post procedural details. Patient's status of hepatitis or blood borne infection was also noted. Data was recorded and analyzed in Excel worksheet. Results: A total of 55 health workers reported needle stick injuries at all sections of radiology departments with maximum number needle stick injuries at general radiography, fluoroscopy and IVP section. Radiographers and radiology residents received the maximum number of injuries. Major cause of injury was cannulation however, many injuries occurred during disposing or handling of bin. In majority of cases the patients were not infected with any known blood borne infections. Conclusions: Doctors and nurses get needle-stick injuries while carrying out clinical procedures, while, ancillary staff get infected post procedure during disposal of garbage. Policy message: Good occupational health and safety practices must be promoted to all staff. Safer disposal of needles is an important area where practice and procedure needs to be carefully reviewed. It is necessary to undertake a risk assessment, to offer counseling and Post Exposure Prophylaxis and treatment where necessary. (author)

Consequences of radiological emergencies at Goiania and Mayapuri

International Nuclear Information System (INIS)

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

2012-01-01

, Morocco and Mayapuri etc. demonstrates the requirement of strict regulatory measures for prevention of loss of control on radioactive sources. Based on the lessons learnt, prevention of such radiological emergencies as well as effective response to reduce the consequences requires strengthening of emergency preparedness at national level. Towards this, installation of radiation detectors at major ports and police patrolling vehicles, training of First Responders and medical community for handling radiological emergency etc are proposed

Radiological and hygienic aspects in radioactive waste processing and disposal

International Nuclear Information System (INIS)

Stepanova, V.D.

1978-01-01

The present review of reports deals with radiation-hygienic aspects of treatment and bUrial of radioactive wastes from nuclear power plants (NPP). The main principle of handling these wastes, which has been accepted in the USSR, is the treatment of the wastes directly at NPP with subsequent burial of the concentrates at the site. It is permissible to store wastes with mean specific activity in metal containers only temporarily. The most reliable method for fixing radioactive substances from wastes composition with mean specific activity is the method of consolidation by enclosing them in bitumen. Only excessive (disbalanced waters) that have been subjected to special water treatment may be discharged into NPP cooling ponds - if the content of radionuclides in this water is not in excess of the accepted standard at the point of discharge. An indirect radiological method has been developed for obtaining information on 90 Sr content in water; it may be further accepted for other radionuclides. An improved method is suggested for purification of salt-containing liquid wastes with low specific activity by using filters with ionexchange resins. Evaluation of safety at the Central Station of Radioactive Wastes Burial showed reliability of the methods used for treatment and burial of radioactive wastes. Measures for further decrease in the level of personnel irradiation and for environmental protection are enumerated

Radiological and hygienic aspects in radioactive waste processing and disposal

Energy Technology Data Exchange (ETDEWEB)

Stepanova, V D

1978-01-01

The present review of reports deals with radiation-hygienic aspects of treatment and burial of radioactive wastes from nuclear power plants (NPP). The main principle of handling these wastes, which has been accepted in the USSR, is the treatment of the wastes directly at NPP with subsequent burial of the concentrates at the site. It is permissible to store wastes with mean specific activity in metal containers only temporarily. The most reliable method for fixing radioactive substances from wastes composition with mean specific activity is the method of consolidation by enclosing them in bitumen. Only excessive (disbalanced waters) that have been subjected to special water treatment may be discharged into NPP cooling ponds - if the content of radionuclides in this water is not in excess of the accepted standard at the point of discharge. An indirect radiological method has been developed for obtaining information on /sup 90/Sr content in water; it may be further accepted for other radionuclides. An improved method is suggested for purification of salt-containing liquid wastes with low specific activity by using filters with ionexchange resins. Evaluation of safety at the Central Station of Radioactive Wastes Burial showed reliability of the methods used for treatment and burial of radioactive wastes. Measures for further decrease in the level of personnel irradiation and for environmental protection are enumerated.

Treatment alternatives of liquid radioactive waste containing uranium in phosphoric acid

International Nuclear Information System (INIS)

Bustamante Escobedo, Mauricio

2003-01-01

The UGDR, receives annually 100 [l] of liquid radioactive waste containing, highly acid (pH=0) uranium in phosphoric acid from the Laboratory of Chemical Analysis. This waste must be chemically and radiologically decontaminated before it can be discharged in accordance with local environmental standards. Chemical precipitation and evaporation test were carried out to define the operating conditions for the radiological decontamination of this radioactive waste and to obtain a solid waste that can be conditioned in a cement matrix. The evaporation process generates excellent rates of volume reduction, over 80%, but generates a pulp that is hard handle when submitted to a drying process. Chemical precipitation generates good results for decontaminating these solutions and reducing volume (above 50%) to obtain a uranium free effluent. The treatment with calcium carbonate generated an effluent with a low concentration of polluting agents. A preliminary test was carried out condition these solids in a cement matrix, using ratios of 0.45 waste/cement and 2 of water/cement. The mix prepared with waste from the sodium hydroxide treatment had low mechanical resistance resulting from the saline incrustations. The waste from the calcium carbonate treatment was very porous due to the water evaporation from the highly exothermic reaction between the waste and the cement. The mix of the calcium carbonate generated waste and the cement matrix needs to be optimized, since it generates favorable conditions for adhering with the cement matrix (au)

Fischer-Tropsch Cobalt Catalyst Activation and Handling Through Wax Enclosure Methods

Science.gov (United States)

Klettlinger, Jennifer L. S.; Yen, Chia H.; Nakley, Leah M.; Surgenor, Angela D.

2016-01-01

Fischer-Tropsch (F-T) synthesis is considered a gas to liquid process which converts syn-gas, a gaseous mixture of hydrogen and carbon monoxide, into liquids of various hydrocarbon chain length and product distributions. Cobalt based catalysts are used in F-T synthesis and are the focus of this paper. One key concern with handling cobalt based catalysts is that the active form of catalyst is in a reduced state, metallic cobalt, which oxidizes readily in air. In laboratory experiments, the precursor cobalt oxide catalyst is activated in a fixed bed at 350 ?C then transferred into a continuous stirred tank reactor (CSTR) with inert gas. NASA has developed a process which involves the enclosure of active cobalt catalyst in a wax mold to prevent oxidation during storage and handling. This improved method allows for precise catalyst loading and delivery into a CSTR. Preliminary results indicate similar activity levels in the F-T reaction in comparison to the direct injection method. The work in this paper was supported by the NASA Fundamental Aeronautics Subsonics Fixed Wing Project.

Radiological Worker Training: Radiological Worker 2 study guides

International Nuclear Information System (INIS)

1992-10-01

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

Developing a comprehensive and accountable database after a radiological accident

International Nuclear Information System (INIS)

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

1986-09-01

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

Radiological clerkships as a critical curriculum component in radiology education

International Nuclear Information System (INIS)

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

2011-01-01

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

Bulk handling benefits from ICT

Energy Technology Data Exchange (ETDEWEB)

NONE

2007-11-15

The efficiency and accuracy of bulk handling is being improved by the range of management information systems and services available today. As part of the program to extend Richards Bay Coal Terminal, Siemens is installing a manufacturing execution system which coordinates and monitors all movements of raw materials. The article also reports recent developments by AXSMarine, SunGuard Energy, Fuelworx and Railworx in providing integrated tools for tracking, managing and optimising solid/liquid fuels and rail car maintenance activities. QMASTOR Ltd. has secured a contract with Anglo Coal Australia to provide its Pit to Port.net{reg_sign} and iFuse{reg_sign} software systems across all their Australians sites, to include pit-to-product stockpile management. 2 figs.

Diagnostic radiology 1987

International Nuclear Information System (INIS)

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

1987-01-01

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

Accelerated Metastable Solid-liquid Interdiffusion Bonding with High Thermal Stability and Power Handling

Science.gov (United States)

Huang, Ting-Chia; Smet, Vanessa; Kawamoto, Satomi; Pulugurtha, Markondeya R.; Tummala, Rao R.

2018-01-01

Emerging high-performance systems are driving the need for advanced packaging solutions such as 3-D integrated circuits (ICs) and 2.5-D system integration with increasing performance and reliability requirements for off-chip interconnections. Solid-liquid interdiffusion (SLID) bonding resulting in all-intermetallic joints has been proposed to extend the applicability of solders, but faces fundamental and manufacturing challenges hindering its wide adoption. This paper introduces a Cu-Sn SLID interconnection technology, aiming at stabilization of the microstructure in the Cu6Sn5 metastable phase rather than the usual stable Cu3Sn phase. This enables formation of a void-free interface yielding higher mechanical strength than standard SLID bonding, as well as significantly reducing the transition time. The metastable SLID technology retains the benefits of standard SLID with superior I/O pitch scalability, thermal stability and current handling capability, while advancing assembly manufacturability. In the proposed concept, the interfacial reaction is controlled by introducing Ni(P) diffusion barrier layers, designed to effectively isolate the metastable Cu6Sn5 phase preventing any further transformation. Theoretical diffusion and kinetic models were applied to design the Ni-Cu-Sn interconnection stack to achieve the targeted joint composition. A daisy chain test vehicle was used to demonstrate this technology as a first proof of concept. Full transition to Cu6Sn5 was successfully achieved within a minute at 260°C as confirmed by scanning electron microscope (SEM) and x-ray energy dispersive spectroscopy (XEDS) analysis. The joint composition was stable through 10× reflow, with outstanding bond strength averaging 90 MPa. The metastable SLID interconnections also showed excellent electromigration performance, surviving 500 h of current stressing at 105 A/cm2 at 150°C.

Fuel handling machine and auxiliary systems for a fuel handling cell

International Nuclear Information System (INIS)

Suikki, M.

2013-10-01

This working report is an update for as well as a supplement to an earlier fuel handling machine design (Kukkola and Roennqvist 2006). A focus in the earlier design proposal was primarily on the selection of a mechanical structure and operating principle for the fuel handling machine. This report introduces not only a fuel handling machine design but also auxiliary fuel handling cell equipment and its operation. An objective of the design work was to verify the operating principles of and space allocations for fuel handling cell equipment. The fuel handling machine is a remote controlled apparatus capable of handling intensely radiating fuel assemblies in the fuel handling cell of an encapsulation plant. The fuel handling cell is air tight space radiation-shielded with massive concrete walls. The fuel handling machine is based on a bridge crane capable of traveling in the handling cell along wall tracks. The bridge crane has its carriage provided with a carousel type turntable having mounted thereon both fixed and telescopic masts. The fixed mast has a gripper movable on linear guides for the transfer of fuel assemblies. The telescopic mast has a manipulator arm capable of maneuvering equipment present in the fuel handling cell, as well as conducting necessary maintenance and cleaning operations or rectifying possible fault conditions. The auxiliary fuel handling cell systems consist of several subsystems. The subsystems include a service manipulator, a tool carrier for manipulators, a material hatch, assisting winches, a vacuum cleaner, as well as a hose reel. With the exception of the vacuum cleaner, the devices included in the fuel handling cell's auxiliary system are only used when the actual encapsulation process is not ongoing. The malfunctions of mechanisms or actuators responsible for the motion actions of a fuel handling machine preclude in a worst case scenario the bringing of the fuel handling cell and related systems to a condition appropriate for

Fuel handling machine and auxiliary systems for a fuel handling cell

Energy Technology Data Exchange (ETDEWEB)

Suikki, M. [Optimik Oy, Turku (Finland)

2013-10-15

This working report is an update for as well as a supplement to an earlier fuel handling machine design (Kukkola and Roennqvist 2006). A focus in the earlier design proposal was primarily on the selection of a mechanical structure and operating principle for the fuel handling machine. This report introduces not only a fuel handling machine design but also auxiliary fuel handling cell equipment and its operation. An objective of the design work was to verify the operating principles of and space allocations for fuel handling cell equipment. The fuel handling machine is a remote controlled apparatus capable of handling intensely radiating fuel assemblies in the fuel handling cell of an encapsulation plant. The fuel handling cell is air tight space radiation-shielded with massive concrete walls. The fuel handling machine is based on a bridge crane capable of traveling in the handling cell along wall tracks. The bridge crane has its carriage provided with a carousel type turntable having mounted thereon both fixed and telescopic masts. The fixed mast has a gripper movable on linear guides for the transfer of fuel assemblies. The telescopic mast has a manipulator arm capable of maneuvering equipment present in the fuel handling cell, as well as conducting necessary maintenance and cleaning operations or rectifying possible fault conditions. The auxiliary fuel handling cell systems consist of several subsystems. The subsystems include a service manipulator, a tool carrier for manipulators, a material hatch, assisting winches, a vacuum cleaner, as well as a hose reel. With the exception of the vacuum cleaner, the devices included in the fuel handling cell's auxiliary system are only used when the actual encapsulation process is not ongoing. The malfunctions of mechanisms or actuators responsible for the motion actions of a fuel handling machine preclude in a worst case scenario the bringing of the fuel handling cell and related systems to a condition appropriate for

Radiology fundamentals

CERN Document Server

Singh, Harjit

2011-01-01

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

Quality index of radiological devices: results of one year of use.

Science.gov (United States)

Tofani, Alessandro; Imbordino, Patrizia; Lecci, Antonio; Bonannini, Claudia; Del Corona, Alberto; Pizzi, Stefano

2003-01-01

The physical quality index (QI) of radiological devices summarises in a single numerical value between 0 and 1 the results of constancy tests. The aim of this paper is to illustrate the results of the use of such an index on all public radiological devices in the Livorno province over one year. The quality index was calculated for 82 radiological devices of a wide range of types by implementing its algorithm in a spreadsheet-based software for the automatic handling of quality control data. The distribution of quality index values was computed together with the associated statistical quantities. This distribution is strongly asymmetrical, with a sharp peak near the highest QI values. The mean quality index values for the different types of device show some inhomogeneity: in particular, mammography and panoramic dental radiography devices show far lower quality than other devices. In addition, our analysis has identified the parameters that most frequently do not pass the quality tests for each type of device. Finally, we sought some correlation between quality and age of the device, but this was poorly significant. The quality index proved to be a useful tool providing an overview of the physical conditions of radiological devices. By selecting adequate QI threshold values for, it also helps to decide whether a given device should be upgraded or replaced. The identification of critical parameters for each type of device may be used to improve the definition of the QI by attributing greater weights to critical parameters, so as to better address the maintenance of radiological devices.

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

DEFF Research Database (Denmark)

Andersen, Poul Erik

2011-01-01

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

Sampling on radiological protection training in diagnostic radiology

International Nuclear Information System (INIS)

Gaona, E.

2001-01-01

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

Nonuniformities in organic liquid ionization calorimeters

International Nuclear Information System (INIS)

Wenzel, W.A.

1989-06-01

Hermeticity and uniformity in SSC calorimeter designs are compromised by structure and modularity. Some of the consequences of the cryogenic needs of liquid argon calorimetry are relatively well known. If the active medium is an organic liquid (TMP, TMS, etc.), a large number of independent liquid volumes is needed for safety and for rapid liquid exchange to eliminate local contamination. Modular construction ordinarily simplifies fabrication, assembly, handling and preliminary testing at the price of additional walls, other dead regions and many nonuniformities. Here we examine ways of minimizing the impact of some generic nonuniformities on the quality of calorimeter performance. 6 refs., 7 figs

Manual on safe production, transport, handling and storage of uranium hexafluoride

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-11-01

This document includes a description of the physical, chemical and radiological properties of UF{sub 6} and related products, including information concerning their production, handling, storage and transportation and the management of the wastes which result. All the operations of UF{sub 6} management are considered form a safety point of view. The IAEA organized a series of meetings to consider the hazards of UF{sub 6} transport since considerable quantities of depleted, natural and enriched UF{sub 6} are transported between nuclear fuel sites. Storage of depleted UF{sub 6} is another important issue. Factors affecting long term storage are presented, especially site choice and cylinder corrosion. Other topics such as waste management, quality assurance and emergency preparedness which contribute to the overall safety of UF{sub 6} handling, are included. The intention of this document is to provide analysis of the safety implications of all stages of UF{sub 6} operations and to draw attention to specific features and properties of importance. 38 refs, figs, tabs.

Liquid decontaminants for nuclear applications

International Nuclear Information System (INIS)

Henning, Klaus; Gojowczyk, Peter

2011-01-01

Decontaminants used in the nuclear field must meet a variety of requirements. On the one hand, the washing process must remove radioactive contamination and conventional dirt from the items washed. On the other hand, subsequent disposal of the washing water arisings must be feasible by the usual waste disposal pathway. One aspect of particular importance is unproblematic treatment of the radioactively contaminated waste water, as a rule low to medium active, whose final storage must be ensured. Decontaminants must not impair waste treatment processes, such as evaporation, filtration, and centrifuging, as well as further treatment of the concentrates and residues arising which are worked into matrix materials (cementation, bituminization), in drum drying or roller mill drying. For reasons of safety at work and environmental quality, also aspects of human toxicology and ecotoxicology must be taken into account. In this way, handling decontaminants will not jeopardize the health of personnel or cause potential long-term environmental damage. Liquid decontaminants, compared to powders, offer the advantage of automatic dosage. The liquid product is dosed accurately as a function of the washing program used. Liquid decontaminants can be handled safely in hot laundries without causing skin and eye contacts. (orig.)

Validation of a DNA IQ-based extraction method for TECAN robotic liquid handling workstations for processing casework.

Science.gov (United States)

Frégeau, Chantal J; Lett, C Marc; Fourney, Ron M

2010-10-01

A semi-automated DNA extraction process for casework samples based on the Promega DNA IQ™ system was optimized and validated on TECAN Genesis 150/8 and Freedom EVO robotic liquid handling stations configured with fixed tips and a TECAN TE-Shake™ unit. The use of an orbital shaker during the extraction process promoted efficiency with respect to DNA capture, magnetic bead/DNA complex washes and DNA elution. Validation studies determined the reliability and limitations of this shaker-based process. Reproducibility with regards to DNA yields for the tested robotic workstations proved to be excellent and not significantly different than that offered by the manual phenol/chloroform extraction. DNA extraction of animal:human blood mixtures contaminated with soil demonstrated that a human profile was detectable even in the presence of abundant animal blood. For exhibits containing small amounts of biological material, concordance studies confirmed that DNA yields for this shaker-based extraction process are equivalent or greater to those observed with phenol/chloroform extraction as well as our original validated automated magnetic bead percolation-based extraction process. Our data further supports the increasing use of robotics for the processing of casework samples. Crown Copyright © 2009. Published by Elsevier Ireland Ltd. All rights reserved.

Acoustophoretic contactless transport and handling of matter in air.

Science.gov (United States)

Foresti, Daniele; Nabavi, Majid; Klingauf, Mirko; Ferrari, Aldo; Poulikakos, Dimos

2013-07-30

Levitation and controlled motion of matter in air have a wealth of potential applications ranging from materials processing to biochemistry and pharmaceuticals. We present a unique acoustophoretic concept for the contactless transport and handling of matter in air. Spatiotemporal modulation of the levitation acoustic field allows continuous planar transport and processing of multiple objects, from near-spherical (volume of 0.1-10 μL) to wire-like, without being limited by the acoustic wavelength. The independence of the handling principle from special material properties (magnetic, optical, or electrical) is illustrated with a wide palette of application experiments, such as contactless droplet coalescence and mixing, solid-liquid encapsulation, absorption, dissolution, and DNA transfection. More than a century after the pioneering work of Lord Rayleigh on acoustic radiation pressure, a path-breaking concept is proposed to harvest the significant benefits of acoustic levitation in air.

Chronicle of pediatric radiology

International Nuclear Information System (INIS)

Benz-Bohm, Gabriele; Richter, Ernst

2012-01-01

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

Determination and evaluation of the radiological situation using mobile measurements during the ground phase

Energy Technology Data Exchange (ETDEWEB)

Obrecht, R.; Pohl, H.; Schneider, S.; Grimm, C. [Umweltministerium Baden-Wuerttemberg, Stuttgart (Germany); Neff, Ulrich; Coutinho, Paula; Mueller, Ulrich; Mandel, Carmen [Landesanstalt fuer Umweltschutz, Messungen und Naturschutz Baden-Wuerttemberg, Karlsruhe (Germany); Wilbois, Thomas; Ren, Yongxiang [T-Systems GEI GmbH, Ulm (Germany); Chaves, Fernando [Fraunhofer Inst. IITB, Karlsruhe (Germany)

2009-08-15

The nuclear reactor remote monitoring system of the state of Baden-Wuerttemberg (Kernreaktor-Fernueberwachung Baden-Wuerttemberg - KFUeBW) is implemented according to the recently renewed ''recommendations for remote monitoring of nuclear power plants''. In Baden-Wuerttemberg, the application area of the system covers both, the surveillance of internal procedures on one hand, and the handling of incidents or accidents on the other. The following paper shows the role of the KFUeregarding the determination and evaluation of the radiological situation in the range of off-site emergency response. Progress is reported on the measurement conception and the technical possibilities for the investigation of the radiological situation after the end of the deposition of radio nuclides (ground phase). (orig.)

ESR paper on the proper use of mobile devices in radiology.

Science.gov (United States)

2018-04-01

Mobile devices (smartphones, tablets, etc.) have become key methods of communication, data access and data sharing for the population in the past decade. The technological capabilities of these devices have expanded very rapidly; for example, their in-built cameras have largely replaced conventional cameras. Their processing power is often sufficient to handle the large data sets of radiology studies and to manipulate images and studies directly on hand-held devices. Thus, they can be used to transmit and view radiology studies, often in locations remote from the source of the imaging data. They are not recommended for primary interpretation of radiology studies, but they facilitate sharing of studies for second opinions, viewing of studies and reports by clinicians at the bedside, etc. Other potential applications include remote participation in educational activity (e.g. webinars) and consultation of online educational content, e-books, journals and reference sources. Social-networking applications can be used for exchanging professional information and teaching. Users of mobile device must be aware of the vulnerabilities and dangers of their use, in particular regarding the potential for inappropriate sharing of confidential patient information, and must take appropriate steps to protect confidential data. • Mobile devices have revolutionized communication in the past decade, and are now ubiquitous. • Mobile devices have sufficient processing power to manipulate and display large data sets of radiological images. • Mobile devices allow transmission & sharing of radiologic studies for purposes of second opinions, bedside review of images, teaching, etc. • Mobile devices are currently not recommended as tools for primary interpretation of radiologic studies. • The use of mobile devices for image and data transmission carries risks, especially regarding confidentiality, which must be considered.

Improvement of the Radiological system of emergency classification in Cuba

International Nuclear Information System (INIS)

Jerez Vegueria, Pablo F.; Yamil Lopez Forteza; Diaz Guerra, Pedro I.

2003-01-01

In 1998 the National Center of Nuclear Security (CNSN), on the base of the experience in the one handling of emergencies and the preparation aspects, planning and answer, it perfects and it modernizes, with the approval of the national bigger State of the Civil Defense, the approaches of the Scale of Radiological Events approved from 1992. Given the operational experience of the System of Answer to Emergency of the Ministry Of Science Technology And Environment in the year 2001 the CNSN develops, it perfects and it puts in vigor a more complete System of Classification of Emergency of unique use for all the entities that use sources of radiations ionizations and that it also includes those answer forces that are imbricate in the Plan of Measures Against Catastrophe for cases of Radiological Accidents. The setting in vigor of this Unique System of Classification of Emergencies at national level has allowed to secure the coordination, planning and answer in an effective, quick and effective way. Presently work is exposed the philosophy on which this System of Classification was elaborated, the approaches used to classify the events as much in radioactive facilities as in the practice of the transport of radioactive materials and the activation of the forces of answers in cases of radiological emergencies

Imaging and radiology

Science.gov (United States)

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

Liquid hydrogen: back to basics

Energy Technology Data Exchange (ETDEWEB)

Sherif, S.A. [Dept. of Mechanical and Aerospace Engineering, Univ. of Florida, Florida (United States)

2009-07-01

'Full text': Liquid hydrogen is primarily used as a rocket fuel and is predestined for supersonic and hypersonic space vehicles to a large extent because it has the lowest boiling point density and the highest specific thrust of any known fuel. Its favorable characteristics include its high heating value per unit mass, its wide ignition range in hydrogen/oxygen or air mixtures, as well as its large flame speed and cooling capacity due to its high specific heat which permits very effective engine cooling and cooling the critical parts of the outer skin. Liquid hydrogen has some other important uses such as in high-energy nuclear physics and bubble chambers. The transport of hydrogen is vastly more economical when it is in liquid form even though cryogenic refrigeration and special Dewar vessels are required. Although liquid hydrogen can provide a lot of advantages, its uses are restricted in part because liquefying hydrogen by existing conventional methods consumes a large amount of energy (around 30% of its heating value). Liquefying 1 kg of hydrogen in a medium-size plant requires 10 to 13 kWh of electric energy. In addition, boil-off losses associated with the storage, transportation, and handling of liquid hydrogen can consume up to 40% of its available combustion energy. It is therefore important to search for ways that can improve the efficiency of the liquefiers and diminish the boil-off losses. This lecture gives an overview of the main issues associated with the production, storage, and handling of liquid hydrogen. Some discussion of promising ways of hydrogen liquefaction will also be presented. (author)

Evaluation of the radiological risk resulting from road transportation of tritiated water

International Nuclear Information System (INIS)

Menossi, C.A.; Segado, R.; Reyes, R.

1983-01-01

A probability model for the evaluation of the individual radiological risk resulting from road transportation of tritiated water in 200-liter drums is presented. In order to evaluate such risk, an evaluation must be made of the probability for an individual to be involved in the consequences of a radiological transport accident, to incur a given dose and to suffer deleterious effects resulting from the dose incurred. With the purpose of quantifying the importance of accidents, a severity level classification was adopted as a function of the fraction of liquid volume spilled as a result of the accident. Considering the above-mentioned severity classification and the transported volume, the volume and the spill area are implied, while the soil characteristics are taken into account. By evaluating the spill characteristics, the average meteorological conditions in the area under analysis and the activity concentration of the transported liquid, the activity concentration values for tritium in air may be estimated, thus allowing calculation of the effective dose equivalent to be incurred by the individual who is most exposed to the consequences of an associated event. As a result of the summarized analysis above, a value of the individual risk per unit of activity concentration is obtained for tritium and for a given volume of transported liquid. 8 references

New system for the container conditioning of liquid waste in the German future finale repository 'Schacht Konrad'

International Nuclear Information System (INIS)

Starke, H.

2012-01-01

control panel next to the plant. Thus, the individual radiation exposure is minimized to the greatest possible extent. Accompanying radiological measuring ensures compliance with the transport limit value. With this system, Babcock Noell possesses a procedure that has the possibility to extract completely different kinds of liquid waste from storage containers. The different kind of waste can be radiologically characterized and can be adjusted to their solids content. Since the cementation can be directly filled into a Konrad container, the demands on homogeneity and quality of the conditioned waste product have been absolutely achieved. The modular concept of the plant allows independent use of parts such as transport and cementation unit. The plan also can easily extended or modified to process different kinds of waste or handling of different waste packages. (author)

Damping of liquid sloshing by foams: from everyday observations to liquid transport

Science.gov (United States)

Sauret, Alban; Boulogne, Francois; Cappello, Jean; Stone, Howard

2014-11-01

When a liquid-filled container is set in motion, the free surface of the liquid starts to slosh, i.e. oscillate. Such effects can be observed when a glass of water is handled carelessly and the fluid sloshes or even spills over the rim of the container. However, beer does not slosh as readily, which suggests that the presence of foam could be used to damp sloshing. In this work, we study experimentally the effect on sloshing of liquid foam placed on top of a liquid bath in a Hele-Shaw cell. We generate a monodisperse 2D liquid foam and track its motion. The influence of the foam on the sloshing dynamics is characterized: 2 to 3 layers of bubbles are sufficient to significantly damp the oscillations. For more than 5 layers of bubbles, the original vertical motion of the foam becomes mainly horizontal. We rationalize our experimental findings with a model that describes the foam contribution to the damping coefficient. This study motivated by everyday observations has promising applications in numerous industrial applications such as the transport of liquid in cargoes.

Radiological Control Manual

Energy Technology Data Exchange (ETDEWEB)

1993-04-01

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

Radiological Control Manual

International Nuclear Information System (INIS)

1993-04-01

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

Radiological English

Energy Technology Data Exchange (ETDEWEB)

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

2007-07-01

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

Radiological English

International Nuclear Information System (INIS)

Ribes, R.; Ros, P.R.

2007-01-01

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

Handbook of radiologic procedures

International Nuclear Information System (INIS)

Hedgcock, M.

1986-01-01

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

Management of liquid radioactive wastes at PNRI

International Nuclear Information System (INIS)

Garcia, C.M.

1994-10-01

Liquid wastes accepted at PNRI waste management facility are generated by hospitals and research institutions from all over the country including those generated from the research laboratories within the PNRI. The operation of the Philippine TRIGA Research Reactor is also a potential source of liquid waste to be handled and managed by the facility in the future. This technical report is a result of the study of the present status and development of the management of liquid wastes at PNRI. (auth.). 8 refs.; 3 figs.; 4 tabs

Individual radiological monitoring for exposed personnel of Nuclear Fuel Plant at Pitesti

International Nuclear Information System (INIS)

Ivana, T.; Epure, Gh.

2010-01-01

In the activity of nuclear fuel fabrication of CANDU type, based on natural and depleted uranium, individual radiological monitoring of the personnel exposed to ionizing radiation is very carefully approached. For Nuclear Fuel Plant (NFP) facility, where uranium appears in bulk and itemized form, measures for individual radiological monitoring are established by Radiological Safety Manual (MSR) in accordance with national and international legislation. All NFP employees are classified in either category A or category B of exposure to ionizing radiation. The classification is a function of type of activity and magnitude of exposure. All the exposed personnel are monitored for external doses (from gamma radiation) by measuring the equivalent dose H p (10) with monthly frequency. The system used for external individual dosimetric monitoring is based on the thermoluminescent dosimeter (TLD) of PANASONIC type UD813AS14. The NFP incorporates an in-house dosimetric laboratory notified by Romanian regulatory body CNCAN (National Commission for Control of Nuclear Activities). The workers handling nuclear materials are exposed to internal intake of uranium, mainly by inhalation. For internal doses monitoring is included part of exposed employees working directly with radioactive open sources (pulverulent or liquid nuclear materials), UO 2 sinterable powder, green pellets, sintered pellets, scrap and radioactive effluents. The estimation of internal exposure is made quarterly using the results from radioactive airborne monitors operating in the working places. The internal dose of each person exposed to open sources is calculated taking into account the rate of breathing, the time spent at the work place and the dose-activity coefficient (variable function of uranium absorption rate). The total effective individual dose is obtained by summing the external dose and internal dose (E=E ext +E int ). For conformity, the total effective individual dose (E) is compared with dose

Training for the medical response in radiological emergency experiences and results

International Nuclear Information System (INIS)

Cardenas Herrera, J.; Lopez Forteza, Y.

2003-01-01

The use of the nuclear techniques int he social practice confers a special imporatnce to the relative aspects to the safety of the practices and radiationsources, for what the implementation of efficient programs of radiation protection constitutes a priority. However in spite of the will before expressed, regrettably radiological situations happen accidental assocaited to multiple causes taht suggest the creation of response capacities to intervention before these fortuitous facts. The experiences accumulated in the last decades related with accidental exposures have evidenced the convenience of having properly qualified human resources for the Medical Response in Radiological Emergencies. The training in the medical aspects of the radiological emergencies acquires a singular character. In such a sense when valuing the national situation put onof manifest deficiences as for the training in medical aspects of the radiological emergencies that advised the development of training programs in such aspects for the different response groups linked to the topic. After identified the training necessities and the scope of the same ones, the contents of the training program were elaborated. The program has as general purpose the invigoration of the capacity of the medical response in front of accidental radiological situations, by means of actions that they bear to prepare groups of medical response in the handling of people accident victims and to the identification of potentials,accidental scenarios, as well as of the necessary resources to confront them. The program content approaches theoretical and paractical aspects to the medical aspect to radiological emergencies. The program include the different topics about fundamental of physical biological to radiation protection, radiation protection during exposure of radiological accidents, medical care for overexposed or contaminated persons, drill, exercises and concludes with designation of a strategy as preparation and

RSVP radiology

International Nuclear Information System (INIS)

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

1990-01-01

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

Liquid biopsy for brain tumors

Science.gov (United States)

Shankar, Ganesh M.; Balaj, Leonora; Stott, Shannon L.; Nahed, Brian; Carter, Bob S.

2018-01-01

Introduction Minimally invasive methods will augment the clinical approach for establishing the diagnosis or monitoring treatment response of central nervous system tumors. Liquid biopsy by blood or cerebrospinal fluid sampling holds promise in this regard. Areas covered In this literature review, the authors highlight recent studies describing the analysis of circulating tumor cells, cell free nucleic acids, and extracellular vesicles as strategies to accomplish liquid biopsy in glioblastoma and metastatic tumors. The authors then discuss the continued efforts to improve signal detection, standardize the liquid biopsy handling and preparation, develop platforms for clinical application, and establish a role for liquid biopsies in personalized medicine. Expert commentary As the technologies used to analyze these biomarkers continue to evolve, we propose that there is a future potential to precisely diagnose and monitor treatment response with liquid biopsies. PMID:28875730

Formerly utilized MED/AEC sites remedial action program. Radiological survey of the former Horizons, Inc., metal handling facility, Cleveland, Ohio. Final report

International Nuclear Information System (INIS)

Leggett, R.W.; Cottrell, W.D.; Shinpaugh, W.H.; Doane, R.W.; Haywood, F.F.; Johnson, W.M.

1979-02-01

The results of a radiological survey of the former Horizons, Inc., metal handling facility in Cleveland, Ohio, are presented in this report. During the 1940's and early 1950's, two of the three buildings on this site (Buildings B and C) were used for the production of granular thorium metal. The survey included measurements related to the following: fixed and transferable alpha and beta-gamma contamination levels on the surfaces in Buildings B and C and on the roofs of these buildings; external gamma radiation levels at 1 m above the floors and grounds on and near the property; radionuclide concentrations in soil, water, and other materials collected from surfaces and drains inside Buildings B and C, from beneath the floor in Building C, and from outdoor locations on and near the site; and thoron ( 220 Rn) daughter concentrations in the air in Buildings B and C. Elevated concentrations of 232 Th, 228 Ra, 228 Th, and 230 Th were found in some samples. Alpha and beta-gamma contamination levels exceeded applicable guideline limits in some areas of Buildings B and C. External gamma radiation levels, approximately 10 times the average background level, were measured at isolated points in and near Building B. Thorium B ( 212 Pb) concentrations in air in Building B were near the Radioactivity Concentration Guide (RCG) level. Most of the elevated radiation levels were found indoors in areas presently used for storage. Outdoors on and near the site, significant radiation levels were found only near the east wall of Building B

Updated Decision Support Tool for the Management of Waste and Debris from Radiological Incidents

International Nuclear Information System (INIS)

Lemieux, P.; Thorneloe, S.; Hayes, C.; Rodgers, M.; Christman, R.

2009-01-01

Unique challenges exist for the handling, transport, and disposal of debris resulting from homeland security incidents, disasters or other national emergencies. Access to guidance for facilitating decision making in the safe and timely disposal of debris is critical to helping restore a community or region and prevent further contamination or spread of disease. For a radiological dispersal device (RDD) or other radiological incident, proper characterization of the quantity, properties, and level of contamination of debris and decontamination residue can have a significant impact on cleanup costs and timelines. A suite of decision support tools (DSTs) is being developed by the U.S. EPA's Office of Research and Development to assist individuals responsible for making decisions associated with handling, transport, treatment, and disposal of such debris. The DSTs are location-specific to help identify specific facilities and contacts for making final disposal decisions. The DSTs provide quick reference to technical information, regulations, and other information to provide decision makers with assistance in guiding disposal decisions that are important for the protection of public health, first responders, and the environment. This tool is being developed in partnership with other U.S. government agencies, EPA program offices, industry, and state and local emergency response programs. (authors)

Radiological anatomy - evaluation of integrative education in radiology.

Science.gov (United States)

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

2013-09-01

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

Analysis of the Radiology Reports from Radiology Clinics

International Nuclear Information System (INIS)

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

2009-01-01

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

Radiation protection and quality assurance in dental radiology: I. Intraoral radiography

International Nuclear Information System (INIS)

Martinez-Beneyto, Y.; Alcaraz, M.; Jodar-Porlan, S.; Saura-Iniesta, A.M.; Velasco-Hidalgo, E.

2001-01-01

This paper studies 2524 official reports on quality assurance in dental radiography, made in the context of the three first revisions of these dental clinics as a result of the entry into force of the regulations establishing the duties for these types of facilities. In the results section we present a quantitative analysis of the facilities equipped with an intraoral device, making a special reference to the brands they have available, as well as their physical features (KV, mAs, filtration, length of cone) and the deviations detected in their operation. Some of the features in the process of obtaining radiological images at those facilities (film control, development time, liquid renewal) are determined, and the average dose of ionizing radiation used in order to obtain the radiological image of the same tooth is presented. This paper shows, in a quantitative way, the characteristic features of intraoral dental radiology in our medium. The study is intended to be continued during the next years, which would allow the assessment of the prospective improvement in dental radiological performances as a result of the newly established regulations. (author)

Shielded enclosure for handling radioactive material

International Nuclear Information System (INIS)

Laurent, H.; Courouble, J.M.

1959-01-01

Two enclosures linked by an air-lock are described: they are designed for the safe handling of 5 curies 0.3 to 0.5 MeV γ emitters, and each is composed of a semi-tight case, ventilated, clad in 80 mm steel plate, and suited for a wide variety of physics and chemistry operations. The equipment required for any given operation can be installed in the shortest possible time, access to the enclosure being via a removable front. Visual control is assured through a lead-glass screen. Each enclosure is fitted with a master-slave manipulator, Argon model 7, and plugs and air-locks are provided for the introduction of liquids and solids. (author) [fr

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

Science.gov (United States)

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

2017-10-01

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

Hypothermic manipulation of bone cement can extend the handling time during vertebroplasty

Directory of Open Access Journals (Sweden)

Lai Po-Liang

2012-10-01

Full Text Available Abstract Background Polymethylmethacrylate (PMMA is commonly used for clinical applications. However, the short handling time increases the probability of a surgeon missing the crucial period in which the cement maintains its ideal viscosity for a successful injection. The aim of this article was to illustrate the effects a reduction in temperature would have on the cement handling time during percutaneous vertebroplasty. Methods The injectability of bone cement was assessed using a cement compressor. By twisting the compressor, the piston transmits its axial load to the plunger, which then pumps the bone cement out. The experiments were categorized based on the different types of hypothermic manipulation that were used. In group I (room temperature, sham group, the syringes were kept at 22°C after mixing the bone cement. In group 2 (precooling the bone cement and the container, the PMMA powder and liquid, as well as the beaker, spatula, and syringe, were stored in the refrigerator (4°C overnight before mixing. In group 3 (ice bath cooling, the syringes were immediately submerged in ice water after mixing the bone cement at room temperature. Results The average liquid time, paste time, and handling time were 5.1 ± 0.7, 3.4 ± 0.3, and 8.5 ± 0.8 min, respectively, for group 1; 9.4 ± 1.1, 5.8 ± 0.5, and 15.2 ± 1.2 min, respectively, for group 2; and 83.8 ± 5.2, 28.8 ± 6.9, and 112.5 ± 11.3 min, respectively, for group 3. The liquid and paste times could be increased through different cooling methods. In addition, the liquid time (i.e. waiting time for ice bath cooling was longer than for that of the precooling method (p Conclusions Both precooling (i.e. lowering the initial temperature and ice bath cooling (i.e. lowering the surrounding temperature can effectively slow polymerization. Precooling is easy for clinical applications, while ice bath cooling might be more suitable for multiple-level vertebroplasty. Clinicians can take

Hypothermic manipulation of bone cement can extend the handling time during vertebroplasty.

Science.gov (United States)

Lai, Po-Liang; Tai, Ching-Lung; Chu, I-Ming; Fu, Tsai-Sheng; Chen, Lih-Huei; Chen, Wen-Jer

2012-10-16

Polymethylmethacrylate (PMMA) is commonly used for clinical applications. However, the short handling time increases the probability of a surgeon missing the crucial period in which the cement maintains its ideal viscosity for a successful injection. The aim of this article was to illustrate the effects a reduction in temperature would have on the cement handling time during percutaneous vertebroplasty. The injectability of bone cement was assessed using a cement compressor. By twisting the compressor, the piston transmits its axial load to the plunger, which then pumps the bone cement out. The experiments were categorized based on the different types of hypothermic manipulation that were used. In group I (room temperature, sham group), the syringes were kept at 22°C after mixing the bone cement. In group 2 (precooling the bone cement and the container), the PMMA powder and liquid, as well as the beaker, spatula, and syringe, were stored in the refrigerator (4°C) overnight before mixing. In group 3 (ice bath cooling), the syringes were immediately submerged in ice water after mixing the bone cement at room temperature. The average liquid time, paste time, and handling time were 5.1 ± 0.7, 3.4 ± 0.3, and 8.5 ± 0.8 min, respectively, for group 1; 9.4 ± 1.1, 5.8 ± 0.5, and 15.2 ± 1.2 min, respectively, for group 2; and 83.8 ± 5.2, 28.8 ± 6.9, and 112.5 ± 11.3 min, respectively, for group 3. The liquid and paste times could be increased through different cooling methods. In addition, the liquid time (i.e. waiting time) for ice bath cooling was longer than for that of the precooling method (p < 0.05). Both precooling (i.e. lowering the initial temperature) and ice bath cooling (i.e. lowering the surrounding temperature) can effectively slow polymerization. Precooling is easy for clinical applications, while ice bath cooling might be more suitable for multiple-level vertebroplasty. Clinicians can take advantage of the improved injectability without any

Introduction of radiological protection; Pengenalan kepada perlindungan radiologi

Energy Technology Data Exchange (ETDEWEB)

NONE

1988-12-31

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

Solidification of liquid concentrate and solid waste generated as by-products of the liquid radwaste treatment systems in light-water reactors

International Nuclear Information System (INIS)

Neilson, R.M. Jr.; Colombo, P.

1977-01-01

The treatment of liquid concentrate and solid waste produced in light-water reactors as by-products of liquid radwaste treatment systems consists of five basic operations: waste collection, waste pretreatment, solidification agent handling, mixing/packaging (solidification) and waste package handling. This paper will concern itself primarily with the solidification operation, however, the other operations enumerated as well as the types of wastes treated and their origins will be briefly described, especially with regards to their effects on solidification. During solidification, liquid concentrate and solid wastes are incorporated with a solidification agent to form a monolithic, free-standing solid. The basic solidification agent types either currently used in the United States or proposed for use include absorbants, hydraulic cement, urea-formaldehyde, other polymer systems, and bitumen. The operation, formulations and limitations of these agents as used for radwaste solidification will be discussed. Properties relevant to the evaluation of solidified waste forms will be identified and relative comparisons made for wastes solidified by various processes

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

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.)

Remotely controlled inspection and handling systems for decommissioning tasks in nuclear facilities

International Nuclear Information System (INIS)

Schreck, G.; Bach, W.; Haferkamp, H.

1993-01-01

The Institut fur Werkstoffkunde at the University of Hanover has recently developed three remotely controlled systems for different underwater inspection and dismantling tasks. ODIN I is a tool guiding device, particularly being designed for the dismantling of the steam dryer housing of the KRB A power plant at Gundremmingen, Germany. After being approved by the licencing organization TUEV Bayern, hot operation started in November 1992. The seven axes remotely controlled handling system ZEUS, consisting of a three translatory axes guiding machine and a tool handling device with four rotatory axes, has been developed for the demonstration of underwater plasma arc cutting of spherical metallic components with great wall thicknesses. A specially designed twin sensor system and a modular torch, exchanged by means of a remote controlled tool changing device, will be used for different complex cutting tasks. FAUST, an autonomous, freediving underwater vehicle, was designed for complex inspection, maintenance and dismantling tasks. It is equipped with two video cameras, an ultrasonic and a radiologic sensor and a small plasma torch. A gripper and a subsidiary vehicle for inspection may be attached. (author)

Assessment of radiological environment around coal mining area of Dhanbad, Jharkhand

International Nuclear Information System (INIS)

Patnaik, R.L.; Thakur, V.K.; Jha, V.N.; Sethy, N.K.; Srivastava, V.S.; Kumar, Rajesh; Tripathi, R.M.; Puranik, V.D.

2012-01-01

Naturally occurring radionuclides present in the earth crust is a significant source of human exposure. Variation in natural background radiation is expected in different geological formations. Anthropogenic activities in geological formation of elevated radionuclide level may enhance the area background. In areas of coal mining industries investigation of radiological environment is required as the residues contains significant amount of uranium and thorium series radionuclides (Van Hook, 1 979, Balogun, 2003). Radon and its short-lived progeny present in the environment contributes maximum natural background radiation dose due to inhalation. Apart from this radionuclide content in key environmental matrices may also contribute to inhalation and ingestion exposure for members of public. Present investigation was carried out in coal mining areas of Dhanbad, Jharkhand to assess the existing radiological status. A detailed investigation is required to evaluate the environmental impact of coal handling activities in the area. The contribution of 222 Rn progeny towards outdoor inhalation dose compares with global average reported by UNSCEAR (2006)

Radiological effect of caesium-137 and strontium-90 on aquatic system of the pathway of the discharged liquid radioactive waste

International Nuclear Information System (INIS)

Sinakhom, F.; Pothipin, K.; Supaokit, P.

1984-12-01

The objective of this paper is to study the radiological effect from the release of treated liquid radioactive waste to the fresh water environment in order to the protection of human health. The emphasis in this program was concentrated on Sr-90 and Cs-137 analyses on Sr-90 and Cs-137 analyses in surface water, water-plants and fish collected during August 1980 to July 1981. Sr-90 concentration was separated by solvent extraction (TBP-tributyl phosphate) procedure. Beta radioactivity of the two nuclides were measured in the form of yttrium oxalate (Y-90, the daughter nuclide of Sr-90) and caesium phospho-molybdate using a low-background anticoincidence proportional counter. To interpret the result obtained, the analytical data were converted to percent derived working limits (%DWL) using Derived Working Limit acquired from the value of (MPC) and water consumption rate stipulated by ICRP as 100% DWL. The value of %DWL is a useful and convenient index to judge the hazardous from radiation exposed by a certain group of people. The interpretation of the result revealed the equivalence of %DWL of Sr-90 and Cs-137 in canal-fish and swamp cabbage for people resided nearby the canal who obtained their whole protein from consumption of that fish from canal and vegetation grown in that water. The value above was equal 2.5 percent which means that this critical group of people exposed to the radiation only 2.5 percent of that intake limit recommended by ICRP. Thus, the amounts of waste disposed of from waste treatment plant into the canal were too small to have a radiological effect on the environment

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

Computer in radiology: Physicians memorandum and administration of medical practice aided by COMRAD

International Nuclear Information System (INIS)

Kuesters, H.

1983-01-01

One year after introduction of the COMRAD EDP system of text processing to the radiological practice of the author, the advantages resulting for the physician and medical staff as well as for the transferring physician and their patients are presented and the econimic efficiency is determined. The high capacity of COMRAD including the automatic text processing for a complete computer aided administration of medical practice and the accounting department, is based on the advanced technological development of microelectronics and combined with a user specific software. The hardware equipment enables multiprogram processing, data processing in on-line operation as well as short access-time of stored data, due to the rapid tracertechnology of the computer. The software equipment, with text processing and a medical practice administration system, permits the regular workload to be handled efficiently and reliable. The main issue is text processing using a text rail. An integrated part of the result output is the performance capacity enabling automatic settlement of accounts with health insurance agencies and privatly insured patients. Statistical evaluation, for instance the daily performance efficiency of the practice can be recalled any time. An accounting system accounts receivable, accounts payable, payroll and general accounting supplements the software package enabling a computer aided handling of all administrative tasks required in a radiological practice. (orig.)

Aerial radiological survey of the US Department of Energy's Mound Facility, Miamisburg, Ohio

International Nuclear Information System (INIS)

1978-03-01

An aerial radiological survey to measure terrestrial gamma radiation was carried out by helicopter over an area centered on Mound Facility, a 180 acre area adjacent to the southern edge of the city of Miamisburg, Ohio. This survey was part of an effort to document background radiation levels around nuclear processing and handling facilities owned or contracted by the United States Department of Energy (DOE). Survey activities were conducted and performed by EG and G for the DOE. Wright-Patterson Air Force Base served as the survey base of operations. During the survey, gamma ray data were collected over a 12.3 km 2 area by flying an east-west grid of lines spaced 61 m apart, flying slowly over several selected areas, and hovering over several spots of interest. The processed data indicated that the on-site radioactivity was primarily due to radionuclides currently being handled or processed at the Facility, and that lesser activity could be attributed to previously handled or processed nuclear materials. Off-site data showed the radioactivity to be that only due to naturally occurring radionuclides

Radiological impact due to natural radionuclides (U and Th-isotopes) in soils from Salamanca, Mexico

Energy Technology Data Exchange (ETDEWEB)

Mandujano G, C. D.; Sosa, M. [Universidad de Guanajuato, Division de Ciencias e Ingenierias, Loma del Bosque 103, Col. Lomas del Campestre, 37150 Leon, Guanajuato (Mexico); Mantero, J.; Manjon, G.; Garcia T, R. [Universidad de Sevilla, Grupo en Fisica Nuclear Aplicada, Av. Reina Mercedes No. 2, 41012 Sevilla (Spain); Costilla, R., E-mail: cmandujano@fisica.ugto.mx [Universidad de Guanajuato, Division de Ciencias de la Vida, Departamento de Ciencias Ambientales, Ex-Hacienda El Copal Km 9 Irapuato-Silao, 36500 Irapuato, Guanajuato (Mexico)

2015-10-15

Full text: Activity concentrations of U ({sup 238}U, {sup 234}U) and Th ({sup 232}Th, {sup 230}Th) radionuclides in samples of superficial urban soils surrounding an industrial complex in Salamanca, Mexico have been determined. Levels of naturally occurring radionuclides (Norm) in the environment may be affected due to the presence of different industrial activities in this zone, representing a potential radiological risk for the population which should be evaluated. Alpha-particle Spectrometry with Pips detectors has been used for the radiometric characterization. A well established radiochemical procedure was used for the isolation of the radionuclides of interest. Alkali fusion for sample digestion, liquid-liquid extraction with Tbp (tri-butyl-phosphate) for U and Th isolation and electrodeposition in stainless steel dishes for measurement conditioning has been used. The results cover the ranges of 10-42, 12-60, 12-52 and 11-51 Bq·kg{sup -1} for {sup 238}U, {sup 234}U, {sup 230}Th, and {sup 232}Th respectively, being not observed any clear anthropogenic increments in relation with the values normally found in unaffected soils. Although there is disequilibrium between U isotopes and {sup 230}Th in some soil samples, it can be attributed to natural processes. The radiological impact of the industrial activities in the surrounding soils can be then evaluated as very low. Hence, from the Radiological Protection point of view, the soils studied do not represent a radiological risk for the health of the population. (Author)

Nevada National Security Site Radiological Control Manual

International Nuclear Information System (INIS)

2012-01-01

low-level radioactive waste and the handling of radioactive sources. Remediation of contaminated land areas may also result in radiological exposures.

Nevada National Security Site Radiological Control Manual

Energy Technology Data Exchange (ETDEWEB)

Radiological Control Managers’ Council

2012-03-26

low-level radioactive waste and the handling of radioactive sources. Remediation of contaminated land areas may also result in radiological exposures.

Guidelines for training and qualification of radiological protection technicians

International Nuclear Information System (INIS)

1987-08-01

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

Radiological terrorism and Australia's response

International Nuclear Information System (INIS)

Patterson, D.

2003-01-01

A terrorist attack in Australia involving dispersal of radioactive material is different from conventional terrorist attacks involving explosives. The trauma experienced by victims during an explosive incident includes cuts, broken limbs, burns and shock. When an explosive device involving radioactive materials is involved, there are a number of additional characteristics including the contamination of victims and the surrounding area and the potential requirement for ongoing monitoring and decontamination. Response actions may require additional complex emergency response measures including immediate protective actions to protect those potentially exposed to contamination, mass casualty care, and public and mental health. There are concerns that terrorist organizations are showing increasing interest in acquiring radiological material that could be used with explosive. A dirty bomb or technically known as a radiological dispersal device (RDD) is a device designed to spread radioactive contamination over a wide area and pose a health and safety threat to those within the contaminated area. The radioactive material could be in the form of a large chunk of material, fine powder, a liquid mist, or a gas. The material may also be spread in other ways, such as by simply emptying a container over the desired area. As RDD's do not require large amounts of explosives, there is unlikely to be a large numbers of casualties, however the areas contaminated by the radiological material may cause immediate and long term health risks to those exposed. An RDD is a weapon of Mass Disruption rather than destruction. While the likelihood of RDD's being employed by terrorist in Australia is still considered remote, Australia's emergency response organizations are developing plans to ensure a rapid and comprehensive response occurs should such an event occur in this country, The presentation will outline Australia's response arrangements at the local/state level and the type of federal

Solid bolus swallowing in the radiologic evaluation of dysphagia

International Nuclear Information System (INIS)

Westen, D. van; Ekberg, O.

1993-01-01

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

Solid bolus swallowing in the radiologic evaluation of dysphagia

Energy Technology Data Exchange (ETDEWEB)

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

1993-07-01

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

Handling of multiassembly sealed baskets between reactor storage and a remote handling facility

International Nuclear Information System (INIS)

Massey, J.V.; Kessler, J.H.; McSherry, A.J.

1989-06-01

The storage of multiple fuel assemblies in sealed (welded) dry storage baskets is gaining increasing use to augment at-reactor fuel storage capacity. Since this increasing use will place a significant number of such baskets on reactor sites, some initial downstream planning for their future handling scenarios for retrieving multi-assembly sealed baskets (MSBs) from onsite storage and transferring and shipping the fuel (and/or the baskets) to a federally operated remote handling facility (RHF). Numerous options or at-reactor and away-from-reactor handling were investigated. Materials handling flowsheets were developed along with conceptual designs for the equipment and tools required to handle and open the MSBs. The handling options were evaluated and compared to a reference case, fuel handling sequence (i.e., fuel assemblies are taken from the fuel pool, shipped to a receiving and handling facility and placed into interim storage). The main parameters analyzed are throughout, radiation dose burden and cost. In addition to evaluating the handling of MSBs, this work also evaluated handling consolidated fuel canisters (CFCs). In summary, the handling of MSBs and CFCs in the store, ship and bury fuel cycle was found to be feasible and, under some conditions, to offer significant benefits in terms of throughput, cost and safety. 14 refs., 20 figs., 24 tabs

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

International Nuclear Information System (INIS)

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

2017-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2017-10-15

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

Radiological protection in interventional radiology

International Nuclear Information System (INIS)

Padovani, R.

2001-01-01

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

Role of first responder's training in the management of nuclear and radiological emergencies

International Nuclear Information System (INIS)

Nagarajan, V.; Sankhla, Rajesh; Verma, R.K.

2008-01-01

Consequent to the terrorist attacks on WTC in USA and other similar terrorist attacks worldwide, there has been increasing public concern regarding the use of radioactive materials in a malevolent act. As the radioactive sources are widely used in the industries, terrorists may have access to these facilities and obtain the radioactive material suitable for making Radioactive Dispersal Device (RDD) often called as dirty bomb. Response to nuclear or radiological emergency may involve highly specialized agencies or technical experts. Hence well-coordinated arrangements must be integrated with those required for any other conventional emergencies. During radiological emergencies, emergency service personnel are expected to play a major role in the early response. Though these personnel are well equipped and trained in tackling the normal emergencies it is essential to train them to deal with the radiological emergencies due to inherent characteristics of radioactivity. For the effective management of radiological emergencies, these first responders are required to be trained in such a way that they understand the concept of radiation protection. This objective can be achieved by using a typical training module consisting of interactive class room lectures, practical sessions to use the instruments and handling of radioactive sources, demonstration of radiation protection practices, exhibition of all radiation survey instruments and protective equipment etc., display of various posters and RDD Emergency Exercise. (author)

Handling and storage of conditioned high-level wastes

International Nuclear Information System (INIS)

Heafield, W.

1984-01-01

This paper deals with certain aspects of the management of one of the most important radioactive wastes arising from the nuclear fuel cycle, i.e. the handling and storage of conditioned high-level wastes. The paper is based on an IAEA report of the same title published during 1983 in the Technical Reports Series. The paper provides illustrative background material on the characteristics of high-level wastes and, qualitatively, their requirements for conditioning. The principles important in the storage of high-level wastes are reviewed in conjunction with the radiological and socio-political considerations involved. Four fundamentally different storage concepts are described with reference to published information and the safety aspects of particular storage concepts are discussed. Finally, overall conclusions are presented which confirm the availability of technology for constructing and operating conditioned high-level waste storage facilities for periods of at least several decades. (author)

Ionic liquids as electrolytes

International Nuclear Information System (INIS)

Galinski, Maciej; Lewandowski, Andrzej; Stepniak, Izabela

2006-01-01

Salts having a low melting point are liquid at room temperature, or even below, and form a new class of liquids usually called room temperature ionic liquids (RTIL). Information about RTILs can be found in the literature with such key words as: room temperature molten salt, low-temperature molten salt, ambient-temperature molten salt, liquid organic salt or simply ionic liquid. Their physicochemical properties are the same as high temperature ionic liquids, but the practical aspects of their maintenance or handling are different enough to merit a distinction. The class of ionic liquids, based on tetraalkylammonium cation and chloroaluminate anion, has been extensively studied since late 1970s of the XX century, following the works of Osteryoung. Systematic research on the application of chloroaluminate ionic liquids as solvents was performed in 1980s. However, ionic liquids based on aluminium halides are moisture sensitive. During the last decade an increasing number of new ionic liquids have been prepared and used as solvents. The general aim of this paper was to review the physical and chemical properties of RTILs from the point of view of their possible application as electrolytes in electrochemical processes and devices. The following points are discussed: melting and freezing, conductivity, viscosity, temperature dependence of conductivity, transport and transference numbers, electrochemical stability, possible application in aluminium electroplating, lithium batteries and in electrochemical capacitors

Radiological consequences of the Chernobyl reactor accident

International Nuclear Information System (INIS)

Hill, P.; Hille, R.

2003-01-01

The reactor accident at unit 4 of the Chernobyl nuclear power plant in Ukraine has deeply affected the living conditions of millions of people. Especially the health consequences have been of public concern up to the present and also been the subject of sometimes absurd claims. The current knowledge on the radiological consequences of the accident is reviewed. Though an increased hazard for some risk groups with high radiation exposure, e.g., liquidators, still cannot be totally excluded for the future, the majority of the population shows no statistically significant indication of radiation-induced illnesses. The contribution of the Research Center Juelich to the assessment of the post-accidental situation and psychological relief of the population is reported. The population groups still requiring special attention include, in particular, children growing up in highly contaminated regions and the liquidators of the years 1986 and 1987 deployed immediately after the accident. (author)

TSD-DOSE: A radiological dose assessment model for treatment, storage, and disposal facilities

International Nuclear Information System (INIS)

Pfingston, M.; Arnish, J.; LePoire, D.; Chen, S.-Y.

1998-01-01

Past practices at US Department of Energy (DOE) field facilities resulted in the presence of trace amounts of radioactive materials in some hazardous chemical wastes shipped from these facilities. In May 1991, the DOE Office of Waste Operations issued a nationwide moratorium on shipping all hazardous waste until procedures could be established to ensure that only nonradioactive hazardous waste would be shipped from DOE facilities to commercial treatment, storage, and disposal (TSD) facilities. To aid in assessing the potential impacts of shipments of mixed radioactive and chemically hazardous wastes, a radiological assessment computer model (or code) was developed on the basis of detailed assessments of potential radiological exposures and doses for eight commercial hazardous waste TSD facilities. The model, called TSD-DOSE, is designed to incorporate waste-specific and site-specific data to estimate potential radiological doses to on-site workers and the off-site public from waste-handling operations at a TSD facility. The code is intended to provide both DOE and commercial TSD facilities with a rapid and cost-effective method for assessing potential human radiation exposures from the processing of chemical wastes contaminated with trace amounts of radionuclides

Handling and treatment of radioactive aqueous wastes

International Nuclear Information System (INIS)

1992-07-01

This report aims to provide essential guidance to developing Member States without a nuclear power programme regarding selection, design and operation of cost effective treatment processes for radioactive aqueous liquids arising as effluents from small research institutions, hospitals and industries. The restricted quantities and low activity associated with the relevant wastes will generally permit contact-handling and avoid the need for shielding requirements. The selection of liquid waste treatment involves: Characterization of arising with the possibility of segregation; Discharge requirements for decontaminated liquors, both radioactive and non-radioactive; Available technologies and costs; Conditioning of the concentrates resulting from the treatment; Storage and disposal of the conditioned concentrates. The report will serve as a technical manual providing reference material and direct step-by-step know-how to staff in radioisotope user establishments and research centres in the developing Member States without nuclear power generation. Therefore, emphasis is limited to the simpler treatment facilities, which will be included with only the robust, well-established waste management processes carefully chosen as appropriate to developing countries. 20 refs, 12 figs, 7 tabs

Spent nuclear fuel retrieval system fuel handling development testing. Final report

International Nuclear Information System (INIS)

Jackson, D.R.; Meeuwsen, P.V.

1997-09-01

Fuel handling development testing was performed in support of the Fuel Retrieval System (FRS) Sub-Project, a subtask of the Spent Nuclear Fuel Project at the Hanford Site in Richland, Washington. The FRS will be used to retrieve and repackage K-Basin Spent Nuclear Fuel (SNF) currently stored in old K-Plant storage basins. The FRS is required to retrieve full fuel canisters from the basin, clean the fuel elements inside the canister to remove excessive uranium corrosion products (or sludge), remove the contents from the canisters and sort the resulting debris, scrap, and fuel for repackaging. The fuel elements and scrap will be collected in fuel storage and scrap baskets in preparation for loading into a multi canister overpack (MCO), while the debris is loaded into a debris bin and disposed of as solid waste. This report describes fuel handling development testing performed from May 1, 1997 through the end of August 1997. Testing during this period was mainly focused on performance of a Schilling Robotic Systems' Conan manipulator used to simulate a custom designed version, labeled Konan, being fabricated for K-Basin deployment. In addition to the manipulator, the camera viewing system, process table layout, and fuel handling processes were evaluated. The Conan test manipulator was installed and fully functional for testing in early 1997. Formal testing began May 1. The purposes of fuel handling development testing were to provide proof of concept and criteria, optimize equipment layout, initialize the process definition, and identify special needs/tools and required design changes to support development of the performance specification. The test program was set up to accomplish these objectives through cold (non-radiological) development testing using simulated and prototype equipment

Medical Preparedness and Response for a Nuclear or Radiological Emergency. Training Materials

International Nuclear Information System (INIS)

2014-01-01

In almost all nuclear and radiological emergencies, local emergency services (e.g. local medical, law enforcement, and fire brigades) will have the most important role in the early response. Within hours, hospitals may also have an important role to play in the response at the local level. Since nuclear and radiological emergencies are rare, medical responders often have little or no experience in dealing with this type of emergency and inexperience may lead to an inadequate response. For this reason, training in medical preparedness and response for a nuclear or radiological emergency is an important aspect of preparedness and response activities. These materials are designed for use at a training course on medical preparedness and response for a nuclear or radiological emergency. They contain a wide range of lectures and supporting materials, which cover the basic topics and more specific areas of medical preparedness and response. Therefore, in planning their specific courses, organizers are encouraged to choose those lectures and supportive materials from the CD-ROM that best match their training priorities. Materials on the CD-ROM address the following areas: • Terrorism in Perspective; • Malicious Act Scenarios; • Providing Information to the Medical Community and the Public; • Medical Response to a Radiation Mass Casualty Event; • Handling of Contaminated Persons in Malicious Events; • Planning and Preparedness for Medical Response to Malicious Events with Radioactive Material; • Handling the Bodies of Decedents Contaminated with Radioactive Material; • Radiation Emergencies: Scope of the Problem; • Common Sources of Radiation; • Basic Concepts of Ionizing Radiation; • Basic Concepts of Radiation Protection; • Biological Effects of Ionizing Radiation – Basic Notions; • Basics of Radiopathology; • External Radioactive Contamination; • Internal Radioactive Contamination; • Acute Radiation Syndrome; • Cutaneous Radiation

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

Energy Technology Data Exchange (ETDEWEB)

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

1997-12-31

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

Leveraging liquid dielectrophoresis for microfluidic applications

International Nuclear Information System (INIS)

Chugh, Dipankar; Kaler, Karan V I S

2008-01-01

Miniaturized fluidic systems have been developed in recent years and offer new and novel means of leveraging the domain of microfluidics for the development of micro-total analysis systems (μTAS). Initially, such systems employed closed microchannels in order to facilitate chip-based biochemical assays, requiring very small quantities of sample and/or reagents and furthermore providing rapid and low-cost analysis on a compact footprint. More recently, advancements in the domain of surface microfluidics have suggested that similar low volume sample handling and manipulation capabilities for bioassays can be attained by leveraging the phenomena of liquid dielectrophoresis and droplet dielectrophoresis (DEP), without the need for separate pumps or valves. Some of the key aspects of this surface microfluidic technology and its capabilities are discussed and highlighted in this paper. We, furthermore, examine the integration and utility of liquid DEP and droplet DEP in providing rapid and automated sample handling and manipulation capabilities on a compact chip-based platform

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

International Nuclear Information System (INIS)

1992-10-01

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

Protecting worker health and safety using remote handling systems

International Nuclear Information System (INIS)

Dennison, D.K.; Merrill, R.D.; Reed, R.K.

1995-03-01

Lawrence Livermore National Laboratory (LLNL) is currently developing and installing two large-scale, remotely controlled systems for use in improving worker health and safety by minimizing exposure to hazardous and radioactive materials. The first system is a full-scale liquid feed system for use in delivering chemical reagents to LLNL's existing aqueous low-level radioactive and mixed waste treatment facility (Tank Farm). The Tank Farm facility is used to remove radioactive and toxic materials in aqueous wastes prior to discharge to the City of Livermore Water Reclamation Plant (LWRP), in accordance with established discharge limits. Installation of this new reagent feed system improves operational safety and process efficiency by eliminating the need to manually handle reagents used in the treatment processes. This was done by installing a system that can inject precisely metered amounts of various reagents into the treatment tanks and can be controlled either remotely or locally via a programmable logic controller (PLC). The second system uses a robotic manipulator to remotely handle, characterize, process, sort, and repackage hazardous wastes containing tritium. This system uses an IBM-developed gantry robot mounted within a special glove box enclosure designed to isolate tritiated wastes from system operators and minimize the potential for release of tritium to the atmosphere. Tritiated waste handling is performed remotely, using the robot in a teleoperational mode for one-of-a-kind functions and in an autonomous mode for repetitive operations. The system is compatible with an existing portable gas cleanup unit designed to capture any gas-phase tritium inadvertently released into the glove box during waste handling

Radioactive Waste Management Produced from the Generator Tc-99m Products

International Nuclear Information System (INIS)

Suhaedi Muhammad; Rimin Sumantri; Affan Ahmad; Tuyono

2012-01-01

Generator Tc-99m product is used in hospitals will result in radioactive waste both solid waste in the form of a column compacted Tc-99m Generator, bottles vials and bottles of saline fluid path series: burning of solid waste in the form of paper straw, hand gloves, and cardboard (vial packing boxes and wrapping Generator) and liquid waste form leaching results lead pot and enclosure. So that these wastes pose no radiological consequences for both humans and the environment, it must be properly managed in accordance with the provisions. In order to realize these expectations should be made so that the radioactive waste management system can be handled effectively, optimal, economical, safe and secure and in accordance with applicable regulations. Management system is in it include: procedures for handling radioactive waste, solid waste compacted, burning of solid waste management, liquid waste handling, shipment of radioactive waste and determination of the amount of radiation doses received by workers who handle radioactive waste. (author)

Liquid air cycle engines

Science.gov (United States)

Rosevear, Jerry

1992-01-01

Given here is a definition of Liquid Air Cycle Engines (LACE) and existing relevant technologies. Heat exchanger design and fabrication techniques, the handling of liquid hydrogen to achieve the greatest heat sink capabilities, and air decontamination to prevent heat exchanger fouling are discussed. It was concluded that technology needs to be extended in the areas of design and fabrication of heat exchangers to improve reliability along with weight and volume reductions. Catalysts need to be improved so that conversion can be achieved with lower quantities and lower volumes. Packaging studies need to be investigated both analytically and experimentally. Recycling with slush hydrogen needs further evaluation with experimental testing.

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)

Radiological risk curves for the liquid radioactive waste transfer from Angra 1 to Angra 2 nuclear power plants by a container tank

International Nuclear Information System (INIS)

Alves, A.S.M.; Passos, E.M. dos; Duarte, J.P.

2013-01-01

Eletrobras Termonuclear has a radiowaste management program focused on reducing the produced volumes, for which it has considered to transfer Angra 1 liquid radioactive waste by a container tank to be processed and packed in Angra 2. This paper presents a radiological risk study for providing the necessary technical foundations to obtain the license from the regulatory agency for implementing this transfer operation. Out of the 92 accident scenarios identified with the help of a preliminary hazard analysis, the greatest risk of fatal cancer for members of the public was equal to 6.9 x 10 -13 fatalities/yr, which refers to the accident scenario involving intrinsic failures of valves, hoses, flanges, seals, gaskets and instrumentation lines, while filling the container tank at Angra 1 filling station. This risk figure is about ten million times less than the one adopted by Eletronuclear for such a waste transfer. The highest frequency was also associated with this type of scenario, and its value was equal to 1.4 x 10 -6 yr -1 . This paper also presents and discusses the radiological risk curves for the three possible in-plant transfer routes, the Angra 1 filling station and Angra 2 discharging station and the overall risk curve in order to allow for a broader perspective of the results obtained. These risk curves display the accident scenarios frequencies against radiation doses by considering relevant in-plant and surroundings release paths. In these curves, the extreme scenarios mentioned earlier can be clearly identified in terms of occurrence frequencies and radiation doses. (author)

Rancho Seco liquid effluent pathway aquatic and terrestrial dietary survey report

International Nuclear Information System (INIS)

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

1984-01-01

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

Radiological design guide

International Nuclear Information System (INIS)

Evans, R.A.

1994-01-01

The purpose of this design guide is to provide radiological safety requirements, standards, and information necessary for designing facilities that will operate without unacceptable risk to personnel, the public, or the environment as required by the US Department of Energy (DOE). This design guide, together with WHC-CM-4-29, Nuclear Criticality Safety, WHC-CM-4-46, Nonreactor Facility Safety Analysis, and WHC-CM-7-5, Environmental Compliance, covers the radiation safety design requirements at Westinghouse Hanford Company (WHC). This design guide applies to the design of all new facilities. The WHC organization with line responsibility for design shall determine to what extent this design guide shall apply to the modifications to existing facilities. In making this determination, consideration shall include a cost versus benefit study. Specifically, facilities that store, handle, or process radioactive materials will be covered. This design guide replaces WHC-CM-4-9 and is designated a living document. This design guide is intended for design purposes only. Design criteria are different from operational criteria and often more stringent. Criteria that might be acceptable for operations might not be adequate for design

Handling and storage of high-level liquid wastes from reprocessing of spent fuel

International Nuclear Information System (INIS)

Finsterwalder, L.

1982-01-01

The high level liquid wastes arise from the reprocessing of irradiated nuclear fuels, which are dissolved in aqueous acid solution, and the plutonium and unburned uranium removed in the chemical separation plant. The remaining solution, containing more than 99% of the dissolved fission products, together with impurities from cladding materials, corrosion products, traces of unseparated plutonium and uranium and most of the transuranic elements, constitutes the high-level waste. At present, these liquid wastes are usually concentrated by evaporation and stored as an aqueous nitric acid solution in high-integrity stainless-steel tanks. There is now world-wide agreement that, for the long term, these liquid wastes should be converted to solid form and much work is in progress to develop techniques for the solidification of these wastes. This paper considers the design requirements for such facilities and the experience gained during nearly 30 years of operation. (orig./RW)

Radiological considerations in the design of Reprocessing Uranium Plant (RUP) of Fast Reactor Fuel Cycle Facility (FRFCF), Kalpakkam

International Nuclear Information System (INIS)

Chandrasekaran, S.; Rajagopal, V.; Jose, M.T.; Venkatraman, B.

2012-01-01

A Fast Reactor Fuel Cycle Facility (FRFCF) being planned at Indira Gandhi Centre for Atomic Research, Kalpakkam is an integrated facility with head end and back end of fuel cycle plants co-located in a single place, to meet the refuelling needs of the prototype fast breeder reactor (PFBR). Reprocessed uranium oxide plant (RUP) is one such plant in FRFCF to built to meet annual requirements of UO 2 for fabrication of fuel sub-assemblies (FSAs) and radial blanket sub-assemblies (RSAs) for PFBR. RUP receives reprocessed uranium oxide powder (U 3 O 8 ) from fast reactor fuel reprocessing plant (FRP) of FRFCF. Unlike natural uranium oxide plant, RUP has to handle reprocessed uranium oxide which is likely to have residual fission products activity in addition to traces of plutonium. As the fuel used for PFBR is recycled within these plants, formation of higher actinides in the case of plutonium and formation of higher levels of 232 U in the uranium product would be a radiological problem to be reckoned with. The paper discussed the impact of handling of multi-recycled reprocessed uranium in RUP and the radiological considerations

Current aspects in the development of the quality control in the conventional X-ray diagnostic radiology

International Nuclear Information System (INIS)

Stoeva, M.; Velkova, K.

2004-01-01

The role of the X-ray diagnostic radiology as one of the main factors forming the general public dose is indisputable. Following the requirement for justification of the application of X-rays for medical purposes, certain criteria for assessment of the parameters of the X-ray diagnostic equipment are formed and maximum permissible values defined. The latter are developed by the international and national radiation protection organizations and introduced both in the international and national legislation. The importance of the quality assurance concept for the radiation protection of the patient and staff in diagnostic radiology turned the quality control into main toll for obtaining high quality images with minimum dose to the patient and staff. X-ray diagnostics is one of the most common methods used in the medical practice. This is the main reason for the increase of the quality control protocols, winch makes their handling difficult. The latest developments in this area bring forward the idea for the development of specialized quality control software, which is capable of: 1) full or semi-automated calculation and assessment of the parameters of the X-ray diagnostic units; 2) tools for data handling and access; 3) tools for data analysis based on predefined procedures

Advanced radiology information system.

Science.gov (United States)

Kolovou, L; Vatousi, M; Lymperopoulos, D; Koukias, M

2005-01-01

The innovative features of an advanced Radiology Information System (RIS) are presented in this paper. The interoperability of RIS with the other Intra-hospital Information Systems that interacts with, dealing with the compatibility and open architecture issues, are accomplished by two novel mechanisms [1]. The first one is the particular message handling system that is applied for the exchange of information, according to the Health Level Seven (HL7) protocol's specifications and serves the transfer of medical and administrative data among the RIS applications and data store unit. The same mechanism allows the secure and HL7-compatible interactions with the Hospital Information System (HIS) too. The second one implements the translation of information between the formats that HL7 and Digital Imaging and Communication in Medicine (DICOM) protocols specify, providing the communication between RIS and Picture and Archive Communication System (PACS). The whole structure ensures the automation of the every-day procedures that the ;medical protocol' specifies and provides its services through a friendly and easy to manage graphical user interface.

The radiological testing of consumer products 1976-1978

International Nuclear Information System (INIS)

Wilkins, B.T.; Dixon, D.W.

1979-02-01

The National Radiological Protection Board's source testing laboratory has been operational since 1976. In the intervening period the types of consumer product which have received most attention have been ionisation chamber smoke detectors and liquid crystal digital watches containing gaseous tritium light sources; the results obtained on these two types of device are the main subject of this report. The report also traces the development of the practical appraisal of these devices by the Board and describes the part played by the test results in the evolution of national and international standards. (author)

MEMO radiology

International Nuclear Information System (INIS)

Wagner-Manslau, C.

1989-01-01

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

Steam coal processing technology: handling, high-order processing, COM, meth-coal

Energy Technology Data Exchange (ETDEWEB)

Kamata, H.; Onodera, J.

1982-01-01

Topics covered include: various handling techologies (overland and marine transport, storage, water removal, drying, comminution and sizing); various coal processing technologies (gravity concentration, magnetic separation, multi-stage flotation, liquid-phase pelletizing, chemical processing); production methods for coal-oil mixtures (COM), their physical properties, stability, storage, transport, advantages, plus recent trends in research and development; production of coal-methanol slurry (meth-coal), its stability, storage, transport, utilization and environmental problems, plus latest trends in research and development. (In Japanese)

Contribution of the Medical Radiology Research Center, Russian Academy of Medical Sciences, to liquidation of radionuclide contamination aftereffects in the Kaluga Region that resulted from the Chernobyl power plant accident

International Nuclear Information System (INIS)

Matveenko, E.G.; Berdov, B.A.; Gorobets, V.F.; Tsyplyakovskaya, L.M.; Ivanov, V.K.; Stepanenko, V.F.; Pitkevich, V.A.; Omel'chenko, V.N.; Borovikova, M.P.

1992-01-01

Specialists from the Medical Radiology Research Center, have been participating in liquidation of the Chernobyl power plant accident aftereffects since May-June, 1986. The basic trends of their work are mass dosimetric studies of the population of the contaminated areas, annual prophylactic check-ups of children and adolescents, pregnant and nursing women and other adults of high-risk groups (agricultural workers, patients with chronic diseases), development of recommendations for health and prophylactic measures in the districts under observation, treatment of patients from these regions, who are in need of a specialized care, at the clinic of the Center

Instrument platforms for nano liquid chromatography

Czech Academy of Sciences Publication Activity Database

Šesták, Jozef; Moravcová, Dana; Kahle, Vladislav

2015-01-01

Roč. 1421, NOV (2015), s. 2-17 ISSN 0021-9673 R&D Projects: GA MV VG20112015021 Institutional support: RVO:68081715 Keywords : nano liquid chromatography * splitless gradient generation * nano LC platforms Subject RIV: CB - Analytical Chemistry, Separation Impact factor: 3.926, year: 2015 http://hdl.handle.net/11104/0250900

Management and Handling of Rejected Fuel of MTR Type and Process Effluents Contained Uranium at FEPI

International Nuclear Information System (INIS)

Ghaib Widodo; Bambang Herutomo

2007-01-01

Research Reactor Fuel Element Production Installation (FEPI) - Serpong has performed management and handling of all kinds of rejected fuel material during production (solids, liquids, and gases) and process effluents contained uranium. The methods that has been implemented are precipitation, absorption, evaporation, electrolysis, and electrodialysis. By these methods will finally be obtained forms of product which can be used directly as fuel material feed and solid/liquid radioactive waste that fulfil the requirements (uranium contents < 50 ppm) to be send to Radioactive Waste Management Installation. (author)

Advanced image display systems in radiology

International Nuclear Information System (INIS)

Wendler, T.

1987-01-01

Advanced image display systems for the fully digital diagnostic imaging departments of the future will be far more than simple replacements of the traditional film-viewing equipment. The new capabilities of very high resolution and highly dynamic displays offer a userfriendly and problem-oriented way of image interpretation. Advanced harware-, software- and human-machine interaction-concepts have been outlined. A scenario for a future way of handling and displaying images, reflecting a new image viewing paradigm in radiology is sketched which has been realized in an experimental image workstation model in the laboratory which, despite its technical complexity, offers a consistent strategy for fast and convenient interaction with image objects. The perspective of knowledge based techniques for workstation control software with object-oriented programming environments and user- and task-adaptive behavior leads to more advanced display properties and a new quality of userfriendliness. 2 refs.; 5 figs

Radiology and fine art.

Science.gov (United States)

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

2012-07-01

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

Proposed radioactive liquid effluent monitoring requirements at the Savannah River Site

International Nuclear Information System (INIS)

Jannik, G.T.; Carlton, W.H.; Blunt, B.C.

1994-01-01

Clear regulatory guidance exists for structuring a radiological air monitoring program, however, there is no parallel guidance for radiological liquid monitoring. For Department of Energy (DOE) facilities, there are no existing applicable federal regulations, DOE orders, or DOE guidance documents that specify at what levels continuous monitoring, continuous sampling, or periodic confirmatory measurements of radioactive liquid effluents must be made. In order to bridge this gap and to technically justify and document liquid effluent monitoring decisions at DOE's Savannah River Site, Westinghouse Savannah River Company has proposed that a graded, dose-based approach be established, in conjunction with limits on facility radionuclide inventories, to determine the monitoring and sampling criteria to be applied at each potential liquid radioactive effluent point. The graded approach would be similar to--and a conservative extension of--the existing, agreed-upon SRS/EPA-IV airborne effluent monitoring approach documented in WSRC's NESHAP Quality Assurance Project Plan. The limits on facility radionuclide inventories are based on--and are a conservative extension of--the 10 CFR 834, 10 CFR 20, and SCR 61-63 annual limits on discharges to sanitary sewers. Used in conjunction with each other, the recommended source category criteria levels and facility radionuclide inventories would allow for the best utilization of resources and provide consistent, technically justifiable determinations of radioactive liquid effluent monitoring requirements

A classical density functional theory of ionic liquids.

Science.gov (United States)

Forsman, Jan; Woodward, Clifford E; Trulsson, Martin

2011-04-28

We present a simple, classical density functional approach to the study of simple models of room temperature ionic liquids. Dispersion attractions as well as ion correlation effects and excluded volume packing are taken into account. The oligomeric structure, common to many ionic liquid molecules, is handled by a polymer density functional treatment. The theory is evaluated by comparisons with simulations, with an emphasis on the differential capacitance, an experimentally measurable quantity of significant practical interest.

The handling of radiation accidents

International Nuclear Information System (INIS)

1977-01-01

The symposium was attended by 204 participants from 39 countries and 5 international organizations. Forty-two papers were presented in 8 sessions. The purpose of the meeting was to foster an exchange of experiences gained in establishing and exercising plans for mitigating the effects of radiation accidents and in the handling of actual accident situations. Only a small number of accidents were reported at the symposium, and this reflects the very high standards of safety that has been achieved by the nuclear industry. No accidents of radiological significance were reported to have occurred at commercial nuclear power plants. Of the accidents reported, industrial radiography continues to be the area in which most of the radiation accidents occur. The experience gained in the reported accident situations served to confirm the crucial importance of the prompt availability of medical and radiological services, particularly in the case of uptake of radioactive material, and emphasized the importance of detailed investigation into the causes of the accident in order to improve preventative measures. One of the principal themes of the symposium involved emergency procedures related to nuclear power plant accidents, and several papers defining the scope, progression and consequences of design base accidents for both thermal and fast reactor systems were presented. These were complemented by papers defining the resultant protection requirements that should be satisfied in the establishment of plans designed to mitigate the effects of the postulated accident situations. Several papers were presented describing existing emergency organizational arrangements relating both to specific nuclear power plants and to comprehensive national schemes, and a particularly informative session was devoted to the topic of training of personnel in the practical conduct of emergency arrangements. The general feeling of the participants was one of studied confidence in the competence and

NV/YMP radiological control manual, Revision 2

International Nuclear Information System (INIS)

Gile, A.L.

1996-11-01

The Nevada Test Site (NTS) and the adjacent Yucca Mountain Project (YMP) are located in Nye County, Nevada. The NTS has been the primary location for testing nuclear explosives in the continental US since 1951. Current activities include operating low-level radioactive and mixed waste disposal facilities for US defense-generated waste, assembly/disassembly of special experiments, surface cleanup and site characterization of contaminated land areas, and non-nuclear test operations such as controlled spills of hazardous materials at the hazardous Materials (HAZMAT) Spill Center (HSC). Currently, the major potential for occupational radiation exposure is associated with the burial of low-level nuclear waste and the handling of radioactive sources. Planned future remediation of contaminated land areas may also result in radiological exposures. The NV/YMP Radiological Control Manual, Revision 2, represents DOE-accepted guidelines and best practices for implementing Nevada Test Site and Yucca Mountain Project Radiation Protection Programs in accordance with the requirements of Title 10 Code of Federal Regulations Part 835, Occupational Radiation Protection. These programs provide protection for approximately 3,000 employees and visitors annually and include coverage for the on-site activities for both personnel and the environment. The personnel protection effort includes a DOE Laboratory Accreditation Program accredited dosimetry and personnel bioassay programs including in-vivo counting, routine workplace air sampling, personnel monitoring, and programmatic and job-specific As Low as Reasonably Achievable considerations

NV/YMP radiological control manual, Revision 2

Energy Technology Data Exchange (ETDEWEB)

Gile, A.L. [comp.

1996-11-01

The Nevada Test Site (NTS) and the adjacent Yucca Mountain Project (YMP) are located in Nye County, Nevada. The NTS has been the primary location for testing nuclear explosives in the continental US since 1951. Current activities include operating low-level radioactive and mixed waste disposal facilities for US defense-generated waste, assembly/disassembly of special experiments, surface cleanup and site characterization of contaminated land areas, and non-nuclear test operations such as controlled spills of hazardous materials at the hazardous Materials (HAZMAT) Spill Center (HSC). Currently, the major potential for occupational radiation exposure is associated with the burial of low-level nuclear waste and the handling of radioactive sources. Planned future remediation of contaminated land areas may also result in radiological exposures. The NV/YMP Radiological Control Manual, Revision 2, represents DOE-accepted guidelines and best practices for implementing Nevada Test Site and Yucca Mountain Project Radiation Protection Programs in accordance with the requirements of Title 10 Code of Federal Regulations Part 835, Occupational Radiation Protection. These programs provide protection for approximately 3,000 employees and visitors annually and include coverage for the on-site activities for both personnel and the environment. The personnel protection effort includes a DOE Laboratory Accreditation Program accredited dosimetry and personnel bioassay programs including in-vivo counting, routine workplace air sampling, personnel monitoring, and programmatic and job-specific As Low as Reasonably Achievable considerations.

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

International Nuclear Information System (INIS)

2001-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-03-01

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

TSD-DOSE : a radiological dose assessment model for treatment, storage, and disposal facilities

International Nuclear Information System (INIS)

Pfingston, M.

1998-01-01

In May 1991, the U.S. Department of Energy (DOE), Office of Waste Operations, issued a nationwide moratorium on shipping slightly radioactive mixed waste from DOE facilities to commercial treatment, storage, and disposal (TSD) facilities. Studies were subsequently conducted to evaluate the radiological impacts associated with DOE's prior shipments through DOE's authorized release process under DOE Order 5400.5. To support this endeavor, a radiological assessment computer code--TSD-DOSE (Version 1.1)--was developed and issued by DOE in 1997. The code was developed on the basis of detailed radiological assessments performed for eight commercial hazardous waste TSD facilities. It was designed to utilize waste-specific and site-specific data to estimate potential radiological doses to on-site workers and the off-site public from waste handling operations at a TSD facility. The code has since been released for use by DOE field offices and was recently used by DOE to evaluate the release of septic waste containing residual radioactive material to a TSD facility licensed under the Resource Conservation and Recovery Act. Revisions to the code were initiated in 1997 to incorporate comments received from users and to increase TSD-DOSE's capability, accuracy, and flexibility. These updates included incorporation of the method used to estimate external radiation doses from DOE's RESRAD model and expansion of the source term to include 85 radionuclides. In addition, a detailed verification and benchmarking analysis was performed

Radiology and the mobile device: Radiology in motion

Directory of Open Access Journals (Sweden)

Sridhar G Panughpath

2012-01-01

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

Radiology and the mobile device: Radiology in motion

International Nuclear Information System (INIS)

Panughpath, Sridhar G; Kalyanpur, Arjun

2012-01-01

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

The influence of a solid and liquid bolus on food-stimulated gastroesophageal reflux

International Nuclear Information System (INIS)

Naeser, A.; Behrens, J.K.; Vejen-Christiansen, L.; Funch-Jensen, P.; Thommesen, P.; Aarhus Kommunehospital

1992-01-01

Using a radiological method to demonstrate food-stimulated gastroesophageal reflux (GER), a comparative study was carried out employing a solid, already validated bolus versus a liquid one. One hundred and four consecutive patients received both a solid and a liquid bolus in randomized order. GER was observed in 37 (35.6%) patients receiving the solid bolus versus 28 (26.9%) with the liquid one. This means that the solid bolus provokes significantly more reflux (P [de

A study regarding measurements of bacterial contamination levels in radiology room equipment

Energy Technology Data Exchange (ETDEWEB)

Choi, Eun Jin [Dept. of Public Health and Medicine, Dongshin University Graduate School, Naju (Korea, Republic of); Song, Hyeon Je [Dept. of Clinical Pathology, Gwangju Health University, Gwangju (Korea, Republic of); Dong, Kyung Rae; Kim, Chang Bok [Dept. of Radiological Technology, Gwangju Health University, Gwangju (Korea, Republic of); Ryu, Jae Kwang [Dept. of Nuclear Medicine, Asan Medical Center, Seoul (Korea, Republic of)

2017-03-15

Reported some level of bacteria in areas that are well made contact in Radiology imaging room evaluate the importance of cleanliness in the hospital management of equipment to check for the presence of pathogenic bacteria. Gwang-ju and Jeol-la city and medium-sized hospitals in the material with a cotton swab and rub evenly Radiology selection cassette, a handle, Apron of the imaging apparatus having the most contact with patients from July 2016 to August 2016 as a target in place and special studios 6, and saline solution will placed in a test tube containing. The swab sample was diluted 1,000 times, you can see the bacteria and the intestinal bacterial selective medium Trypticase Soy Agar (TSA), Muller-Hinton Agar (MHA), EosinMethylene Blue (EMB), ENDO (BD, NJ, USA) then incubated smear to. In the incubator (incubator, SANYO, Japan) was observed after incubation of bacteria and counting the total number of bacteria also Colonies (colony) suspected intestinal bacteria were isolated and cultured on KIA medium (BD, NJ, USA). As a result, it was found that this came Gram positive Coccus A hospital handle the F hospital, from the C Gram positive Coccus cassette and handle the F hospital. The striking yellow coloring Staphylococcus aureus 110 agar (STA 110) in the medium sample, but it is suspected staphylococcal Coccus to the final identifcation in the laboratory is not a single specimen of the two samples from Gram positive Coccus biochemical identifcation. Identifcation Kit is an API could not, it was thought to be non-Staphylococcus aureus was cultured on blood agar suggesting that (BAP) blood of dance. Dynamic tests were conducted biochemical API kit of the two samples were identifed from Gram positive Coccus bacteria Escherichia coli (E. coli) is F hospital cassette was confrmed Eenterobacter cloaca in A hospital possession. Did not aggregate O-26, O-111, O-157 and the serum test was conducted in the laboratory from the E. coli F cassette hospital.

A study regarding measurements of bacterial contamination levels in radiology room equipment

International Nuclear Information System (INIS)

Choi, Eun Jin; Song, Hyeon Je; Dong, Kyung Rae; Kim, Chang Bok; Ryu, Jae Kwang

2017-01-01

Reported some level of bacteria in areas that are well made contact in Radiology imaging room evaluate the importance of cleanliness in the hospital management of equipment to check for the presence of pathogenic bacteria. Gwang-ju and Jeol-la city and medium-sized hospitals in the material with a cotton swab and rub evenly Radiology selection cassette, a handle, Apron of the imaging apparatus having the most contact with patients from July 2016 to August 2016 as a target in place and special studios 6, and saline solution will placed in a test tube containing. The swab sample was diluted 1,000 times, you can see the bacteria and the intestinal bacterial selective medium Trypticase Soy Agar (TSA), Muller-Hinton Agar (MHA), EosinMethylene Blue (EMB), ENDO (BD, NJ, USA) then incubated smear to. In the incubator (incubator, SANYO, Japan) was observed after incubation of bacteria and counting the total number of bacteria also Colonies (colony) suspected intestinal bacteria were isolated and cultured on KIA medium (BD, NJ, USA). As a result, it was found that this came Gram positive Coccus A hospital handle the F hospital, from the C Gram positive Coccus cassette and handle the F hospital. The striking yellow coloring Staphylococcus aureus 110 agar (STA 110) in the medium sample, but it is suspected staphylococcal Coccus to the final identifcation in the laboratory is not a single specimen of the two samples from Gram positive Coccus biochemical identifcation. Identifcation Kit is an API could not, it was thought to be non-Staphylococcus aureus was cultured on blood agar suggesting that (BAP) blood of dance. Dynamic tests were conducted biochemical API kit of the two samples were identifed from Gram positive Coccus bacteria Escherichia coli (E. coli) is F hospital cassette was confrmed Eenterobacter cloaca in A hospital possession. Did not aggregate O-26, O-111, O-157 and the serum test was conducted in the laboratory from the E. coli F cassette hospital

Immunogenicity of biopharmaceuticals and biosimilars in relation to storage, handling and stability

International Nuclear Information System (INIS)

Hincal, F.

2009-01-01

Therapeutic proteins or biopharmaceuticals provide effective treatment for many diseases and medical conditions, and vaccines, immunoglobulins and monoclonal antibodies are critical biodefense biopharmaceuticals which constitute an indispensable part of biodefense stockpiles. The manufacturing process for biopharmaceuticals and their generic forms which are called biosimilars is far more complex than for low molecular weight drugs and generics. Any minor change made at any stage may have a critical effect on the clinical efficacy and safety. Potential immunogenicity is the key issue for biopharmaceuticals and biosimilars and may have serious clinical consequences ranging from allergy and anaphylaxis, as well as loss of efficacy of the product. Immunogenicity may be influenced by factors related to manufacturing process, formulation, aggregate formation, contaminants and impurities, and also by the factors related to the storage and handling. Stability is particularly important with larger protein molecules, because their in vivo effects often depend on their three-dimensional structure. Proteins usually aggregate from partially unfolded molecules and aggregates can enhance immunogenicity. Although product formulations are developed to maximize and maintain the fraction of the protein molecules present in the native state, significant amounts of aggregates can form, especially over pharmaceutically relevant time scales and under stress conditions. Exposure to air-liquid and solid-liquid interfaces, light, temperature fluctuations or minor impurities can induce aggregation. Such exposure can occur during processing steps, as well as in the final product container during storage, shipment and handling. Biopharmaceuticals are particularly sensitive to temperature changes and/or shaking. Strict storage and handling conditions and timely and effective stability/shelf-life testing are therefore essential for maintaining product integrity and stability, and hence efficacy

FFTF [Fast Flux Test Facility] fuel handling experience (1979--1986)

International Nuclear Information System (INIS)

Romrell, D.M.; Art, D.M.; Redekopp, R.D.; Waldo, J.B.

1987-05-01

The Fast Flux Test Facility (FFTF)is a 400 MW (th) sodium-cooled fast flux test reactor located on the Hanford Site in southeastern Washington State. The FFTF is operated by the Westinghouse Hanford Company for the United States Department of Energy. The FFTF is a three loop plant designed primarily for the purpose of testing full-scale core components in an environment prototypic of future liquid metal reactors. The plant design emphasizes features to enhance this test capability, especially in the area of the core, reactor vessel, and refueling system. Eight special test positions are provided in the vessel head to permit contact instrumented experiments to be installed and irradiated. These test positions effectively divide the core into three sectors. Each sector requires its own In-Vessel Handling Machine (IVHM) to access all the core positions. Since the core and the in-vessel refueling components are submerged under sodium, all handling operations must be performed blind. This puts severe requirements on the positioning ability are reliability of the refueling components. This report addresses the operating experience with the fuel handling system from initial core loading in November, 1979 through 1986. This includes 9 refueling cycles. 2 refs., 8 figs

Radiological protection in medical facilities and applications and around accelerator facilities

International Nuclear Information System (INIS)

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

1992-01-01

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

Handling and storage of high-level radioactive liquid wastes requiring cooling

International Nuclear Information System (INIS)

1979-01-01

The technology of high-level liquid wastes storage and experience in this field gained over the past 25 years are reviewed in this report. It considers the design requirements for storage facilities, describes the systems currently in use, together with essential accessories such as the transfer and off-gas cleaning systems, and examines the safety and environmental factors

Chemical toxicity and radiological health detriment associated with the inhalation of various enrichments of uranium

International Nuclear Information System (INIS)

3C Limited, Queen Square House, 18-21 Queen Square, Bristol BS1 4NH (United Kingdom))" data-affiliation=" (SR3C Limited, Queen Square House, 18-21 Queen Square, Bristol BS1 4NH (United Kingdom))" >Bryant, P A

2014-01-01

The occupational risks associated with the chemical toxicity of uranium can be overlooked during the processing, handling and storage of the material, as the radioactivity of the material is often used alone to assess the health consequences of exposure to uranium compounds. This note provides a summary of the current United Kingdom occupational standards for uranium based on radiation dose and/or chemical toxicity with a particular focus on intake via inhalation. A simple model is subsequently presented to allow a comparison to be drawn between the occupational exposure standard for chemical toxicity and radiological dose limit. Using these data a set of suggested limits on occupational exposure to airborne uranium is proposed that indicate where the legal annual radiological dose limit for workers or the Health and Safety Executive occupational exposure standard for chemical toxicity are at risk of being breached. (note)

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

International Nuclear Information System (INIS)

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

2016-01-01

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

Pump Propels Liquid And Gas Separately

Science.gov (United States)

Harvey, Andrew; Demler, Roger

1993-01-01

Design for pump that handles mixtures of liquid and gas efficiently. Containing only one rotor, pump is combination of centrifuge, pitot pump, and blower. Applications include turbomachinery in powerplants and superchargers in automobile engines. Efficiencies lower than those achieved in separate components. Nevertheless, design is practical and results in low consumption of power.

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.

Liquid fuel cells

Directory of Open Access Journals (Sweden)

Grigorii L. Soloveichik

2014-08-01

Full Text Available The advantages of liquid fuel cells (LFCs over conventional hydrogen–oxygen fuel cells include a higher theoretical energy density and efficiency, a more convenient handling of the streams, and enhanced safety. This review focuses on the use of different types of organic fuels as an anode material for LFCs. An overview of the current state of the art and recent trends in the development of LFC and the challenges of their practical implementation are presented.

Current radiology. Volume 5

International Nuclear Information System (INIS)

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

1984-01-01

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

Medical Ethics in Radiology

International Nuclear Information System (INIS)

Kim, Kyung Won; Park, Jae Hyung; Yoon, Soon Ho

2010-01-01

According to the recent developments in radiological techniques, the role of radiology in the clinical management of patients is ever increasing and in turn, so is the importance of radiology in patient management. Thus far, there have been few open discussions about medical ethics related to radiology in Korea. Hence, concern about medical ethics as an essential field of radiology should be part of an improved resident training program and patient management. The categories of medical ethics related with radiology are ethics in the radiological management of patient, the relationship of radiologists with other medical professionals or companies, the hazard level of radiation for patients and radiologists, quality assurance of image products and modalities, research ethics, and other ethics issues related to teleradiology and fusion imaging. In order to achieve the goal of respectful progress in radiology as well as minimizing any adverse reaction from other medical professions or society, we should establish a strong basis of medical ethics through the continuous concern and self education

Valve Concepts for Microfluidic Cell Handling

Directory of Open Access Journals (Sweden)

M. Grabowski

2010-01-01

Full Text Available In this paper we present various pneumatically actuated microfluidic valves to enable user-defined fluid management within a microfluidic chip. To identify a feasible valve design, certain valve concepts are simulated in ANSYS to investigate the pressure dependent opening and closing characteristics of each design. The results are verified in a series of tests. Both the microfluidic layer and the pneumatic layer are realized by means of soft-lithographic techniques. In this way, a network of channels is fabricated in photoresist as a molding master. By casting these masters with PDMS (polydimethylsiloxane we get polymeric replicas containing the channel network. After a plasma-enhanced bonding process, the two layers are irreversibly bonded to each other. The bonding is tight for pressures up to 2 bar. The valves are integrated into a microfluidic cell handling system that is designed to manipulate cells in the presence of a liquid reagent (e.g. PEG – polyethylene glycol, for cell fusion. For this purpose a user-defined fluid management system is developed. The first test series with human cell lines show that the microfluidic chip is suitable for accumulating cells within a reaction chamber, where they can be flushed by a liquid medium.

Analysis of papers in radiological journals in recent years: a comparison of journal of Korean radiologic society and radiology

International Nuclear Information System (INIS)

Kim, Jin Suh; Kim, Jae Kyun; Han, Dong Bok; Lim, Tae Hwan

1997-01-01

The purpose of this study was to determine current trends and the mode of future development in the field of medical radiology and to promote research among the nation's radiologists by analyzing the contents of the Journal of the Korean Radiologic Society(JKRS) and Radiology. The number of articles published in JKRS each year between 1990 and 1994 was counted. The research articles in JKRS(n=740) and in Radiology(n=1748) between 1992 and 1994 were categorized according to the objective, type, topic, materials, and radiologic techniques of their contents on the basis of predetermined criteria. Domestic Masters theses(n=126) and doctoral dissertations(n=75) accepted between 1990 and 1994, and domestic materials published in international journals (n=416) between 1986 and 1994 were also categorized using the same criteria. The greatest increase in the number of articles published in JKRS was seen during 1994. The majority of these aimed to retrospectively analyse the findings of diseases while the majority of articles published in Radiology dealt prospectively with the development and/or evaluation of diagnostic methods. More variety of topics and issues was seen in Radiology than in JKRS. The number of articles of domestic materials published in international journals increased from 1986 to 1994, while the number of articles of foreign materials published in Korea was relatively stationary : A significant number of theses and dissertations dealt, mostly prospectively, with studies of pathophysiologic and/or pharmacologic mechanisms using animal models. In order to understand both current trends and the direction and mode of future developments in the field of radiology, and to be able to actively deal with challenges at the forefront of radiologic development, it is essential to review research articles published in radiology-related journals

Recommendations for cask features for robotic handling from the Advanced Handling Technology Project

International Nuclear Information System (INIS)

Drotning, W.

1991-02-01

This report describes the current status and recent progress in the Advanced Handling Technology Project (AHTP) initiated to explore the use of advanced robotic systems and handling technologies to perform automated cask handling operations at radioactive waste handling facilities, and to provide guidance to cask designers on the impact of robotic handling on cask design. Current AHTP tasks have developed system mock-ups to investigate robotic manipulation of impact limiters and cask tiedowns. In addition, cask uprighting and transport, using computer control of a bridge crane and robot, were performed to demonstrate the high speed cask transport operation possible under computer control. All of the current AHTP tasks involving manipulation of impact limiters and tiedowns require robotic operations using a torque wrench. To perform these operations, a pneumatic torque wrench and control system were integrated into the tool suite and control architecture of the gantry robot. The use of captured fasteners is briefly discussed as an area where alternative cask design preferences have resulted from the influence of guidance for robotic handling vs traditional operations experience. Specific robotic handling experiences with these system mock-ups highlight a number of continually recurring design principles: (1) robotic handling feasibility is improved by mechanical designs which emphasize operation with limited dexterity in constrained workspaces; (2) clearances, tolerances, and chamfers must allow for operations under actual conditions with consideration for misalignment and imprecise fixturing; (3) successful robotic handling is enhanced by including design detail in representations for model-based control; (4) robotic handling and overall quality assurance are improved by designs which eliminate the use of loose, disassembled parts. 8 refs., 15 figs

Assessment of dose using TLD during activity handling at RPhL, BRIT

International Nuclear Information System (INIS)

Choughule, Nitin V.; Bairwa, S.M.; Murali, S.; Rakesh, R.B.; Madhumita, B.; Adtani, M.M.; Mehra, Kiran; Padmanabhan, D.; Borkute, S.D.; Pal, N.; Sachdev, S.S.

2012-01-01

Radiopharmaceutical Lab (RPhL), BRIT undertakes production, supply of radiopharmaceuticals. At RPhL short lived isotopes 131 I, 99 Mo, 99m Tc, 125 I, 153 Sm, 32 P and 51 Cr, are handled with total activity handled per week ranging from MBq to TBq (mCiCi). Radiological survey provides idea on radiation level helps to ensure safe working condition. In order to improve the working condition and to estimate the integrated dose over a period of week with uniform pattern of activity handling in the period, a study was carried out using TLD badges. Specifically prepared TLD badges containing CaSO 4 :Dy phosphor were placed at various locations at RPhL It is used for personnel monitoring. One set of TLD was exposed for a week long period while the other set was exposed only during activity handling, kept in the lead pot during the rest of the period. Dose measured by TLDs were compared with the dose estimated using the survey data for the respective locations as well as with the dose estimated using the activity handled by taking into account the time, distance and shielding. The maximum radiation level recorded during lab survey was used to estimate the TLD exposure during the period. It was observed that results on TLD dose measurement and estimated doses using survey results were of same order. The cumulative TLD dose recorded for week duration (168 h) was significantly higher than doses recorded by exposed TLD only during activity handling (8 h). It was expected that the TLD dose would not be more than dose estimated using radiation survey data, while in 3 among 8 experimental TLDs, the dose was ∼ 25% higher. This could be due to the movement of active material or open handling of activity do not get reflected during normal radiation survey and contribution from background radiation at the lab where those TLDs were placed. The individual dose of all the personnel working in different labs were well within the relevant dose limits indicating the safe working condition

Machine Learning and Radiology

Science.gov (United States)

Wang, Shijun; Summers, Ronald M.

2012-01-01

In this paper, we give a short introduction to machine learning and survey its applications in radiology. We focused on six categories of applications in radiology: medical image segmentation, registration, computer aided detection and diagnosis, brain function or activity analysis and neurological disease diagnosis from fMR images, content-based image retrieval systems for CT or MRI images, and text analysis of radiology reports using natural language processing (NLP) and natural language understanding (NLU). This survey shows that machine learning plays a key role in many radiology applications. Machine learning identifies complex patterns automatically and helps radiologists make intelligent decisions on radiology data such as conventional radiographs, CT, MRI, and PET images and radiology reports. In many applications, the performance of machine learning-based automatic detection and diagnosis systems has shown to be comparable to that of a well-trained and experienced radiologist. Technology development in machine learning and radiology will benefit from each other in the long run. Key contributions and common characteristics of machine learning techniques in radiology are discussed. We also discuss the problem of translating machine learning applications to the radiology clinical setting, including advantages and potential barriers. PMID:22465077

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

International Nuclear Information System (INIS)

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

2006-01-01

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

Interactive, Computer-Based Training Program for Radiological Workers

International Nuclear Information System (INIS)

Trinoskey, P.A.; Camacho, P.I.; Wells, L.

2000-01-01

Lawrence Livermore National Laboratory (LLNL) is redesigning its Computer-Based Training (CBT) program for radiological workers. The redesign represents a major effort to produce a single, highly interactive and flexible CBT program that will meet the training needs of a wide range of radiological workers--from researchers and x-ray operators to individuals working in tritium, uranium, plutonium, and accelerator facilities. The new CBT program addresses the broad diversity of backgrounds found at a national laboratory. When a training audience is homogeneous in terms of education level and type of work performed, it is difficult to duplicate the effectiveness of a flexible, technically competent instructor who can tailor a course to the express needs and concerns of a course's participants. Unfortunately, such homogeneity is rare. At LLNL, they have a diverse workforce engaged in a wide range of radiological activities, from the fairly common to the quite exotic. As a result, the Laboratory must offer a wide variety of radiological worker courses. These include a general contamination-control course in addition to radioactive-material-handling courses for both low-level laboratory (i.e., bench-top) activities as well as high-level work in tritium, uranium, and plutonium facilities. They also offer training courses for employees who work with radiation-generating devices--x-ray, accelerator, and E-beam operators, for instance. However, even with the number and variety of courses the Laboratory offers, they are constrained by the diversity of backgrounds (i.e., knowledge and experience) of those to be trained. Moreover, time constraints often preclude in-depth coverage of site- and/or task-specific details. In response to this situation, several years ago LLNL began moving toward computer-based training for radiological workers. Today, that CBT effort includes a general radiological safety course developed by the Department of Energy's Hanford facility and a

Scalable 96-well Plate Based iPSC Culture and Production Using a Robotic Liquid Handling System.

Science.gov (United States)

Conway, Michael K; Gerger, Michael J; Balay, Erin E; O'Connell, Rachel; Hanson, Seth; Daily, Neil J; Wakatsuki, Tetsuro

2015-05-14

Continued advancement in pluripotent stem cell culture is closing the gap between bench and bedside for using these cells in regenerative medicine, drug discovery and safety testing. In order to produce stem cell derived biopharmaceutics and cells for tissue engineering and transplantation, a cost-effective cell-manufacturing technology is essential. Maintenance of pluripotency and stable performance of cells in downstream applications (e.g., cell differentiation) over time is paramount to large scale cell production. Yet that can be difficult to achieve especially if cells are cultured manually where the operator can introduce significant variability as well as be prohibitively expensive to scale-up. To enable high-throughput, large-scale stem cell production and remove operator influence novel stem cell culture protocols using a bench-top multi-channel liquid handling robot were developed that require minimal technician involvement or experience. With these protocols human induced pluripotent stem cells (iPSCs) were cultured in feeder-free conditions directly from a frozen stock and maintained in 96-well plates. Depending on cell line and desired scale-up rate, the operator can easily determine when to passage based on a series of images showing the optimal colony densities for splitting. Then the necessary reagents are prepared to perform a colony split to new plates without a centrifugation step. After 20 passages (~3 months), two iPSC lines maintained stable karyotypes, expressed stem cell markers, and differentiated into cardiomyocytes with high efficiency. The system can perform subsequent high-throughput screening of new differentiation protocols or genetic manipulation designed for 96-well plates. This technology will reduce the labor and technical burden to produce large numbers of identical stem cells for a myriad of applications.

Tuned liquid dampers for multi-storey structure: numerical simulation ...

Indian Academy of Sciences (India)

M Eswaran

Abstract. Wind-induced and earthquake-induced vibrations of structures such as super-tall towers and bridges ... A TLD is liquid confined in a container that uses the sloshing energy ... lation and handling, easy maintenance and lower cost,.

Pediatric radiology malpractice claims - characteristics and comparison to adult radiology claims

Energy Technology Data Exchange (ETDEWEB)

Breen, Micheal A.; Taylor, George A. [Boston Children' s Hospital, Department of Radiology, Boston, MA (United States); Dwyer, Kathy; Yu-Moe, Winnie [CRICO Risk Management Foundation, Boston, MA (United States)

2017-06-15

Medical malpractice is the primary method by which people who believe they have suffered an injury in the course of medical care seek compensation in the United States and Canada. An increasing body of research demonstrates that failure to correctly diagnose is the most common allegation made in malpractice claims against radiologists. Since the 1994 survey by the Society of Chairmen of Radiology in Children's Hospitals (SCORCH), no other published studies have specifically examined the frequency or clinical context of malpractice claims against pediatric radiologists or arising from pediatric imaging interpretation. We hypothesize that the frequency, character and outcome of malpractice claims made against pediatric radiologists differ from those seen in general radiology practice. We searched the Controlled Risk Insurance Co. (CRICO) Strategies' Comparative Benchmarking System (CBS), a private repository of approximately 350,000 open and closed medical malpractice claims in the United States, for claims related to pediatric radiology. We further queried these cases for the major allegation, the clinical environment in which the claim arose, the clinical severity of the alleged injury, indemnity paid (if payment was made), primary imaging modality involved (if applicable) and primary International Classification of Diseases, 9th revision (ICD-9) diagnosis underlying the claim. There were a total of 27,056 fully coded claims of medical malpractice in the CBS database in the 5-year period between Jan. 1, 2010, and Dec. 31, 2014. Of these, 1,472 cases (5.4%) involved patients younger than 18 years. Radiology was the primary service responsible for 71/1,472 (4.8%) pediatric cases. There were statistically significant differences in average payout for pediatric radiology claims ($314,671) compared to adult radiology claims ($174,033). The allegations were primarily diagnosis-related in 70% of pediatric radiology claims. The most common imaging modality

Pediatric radiology malpractice claims - characteristics and comparison to adult radiology claims

International Nuclear Information System (INIS)

Breen, Micheal A.; Taylor, George A.; Dwyer, Kathy; Yu-Moe, Winnie

2017-01-01

Medical malpractice is the primary method by which people who believe they have suffered an injury in the course of medical care seek compensation in the United States and Canada. An increasing body of research demonstrates that failure to correctly diagnose is the most common allegation made in malpractice claims against radiologists. Since the 1994 survey by the Society of Chairmen of Radiology in Children's Hospitals (SCORCH), no other published studies have specifically examined the frequency or clinical context of malpractice claims against pediatric radiologists or arising from pediatric imaging interpretation. We hypothesize that the frequency, character and outcome of malpractice claims made against pediatric radiologists differ from those seen in general radiology practice. We searched the Controlled Risk Insurance Co. (CRICO) Strategies' Comparative Benchmarking System (CBS), a private repository of approximately 350,000 open and closed medical malpractice claims in the United States, for claims related to pediatric radiology. We further queried these cases for the major allegation, the clinical environment in which the claim arose, the clinical severity of the alleged injury, indemnity paid (if payment was made), primary imaging modality involved (if applicable) and primary International Classification of Diseases, 9th revision (ICD-9) diagnosis underlying the claim. There were a total of 27,056 fully coded claims of medical malpractice in the CBS database in the 5-year period between Jan. 1, 2010, and Dec. 31, 2014. Of these, 1,472 cases (5.4%) involved patients younger than 18 years. Radiology was the primary service responsible for 71/1,472 (4.8%) pediatric cases. There were statistically significant differences in average payout for pediatric radiology claims ($314,671) compared to adult radiology claims ($174,033). The allegations were primarily diagnosis-related in 70% of pediatric radiology claims. The most common imaging modality implicated in

Pediatric radiology malpractice claims - characteristics and comparison to adult radiology claims.

Science.gov (United States)

Breen, Micheál A; Dwyer, Kathy; Yu-Moe, Winnie; Taylor, George A

2017-06-01

Medical malpractice is the primary method by which people who believe they have suffered an injury in the course of medical care seek compensation in the United States and Canada. An increasing body of research demonstrates that failure to correctly diagnose is the most common allegation made in malpractice claims against radiologists. Since the 1994 survey by the Society of Chairmen of Radiology in Children's Hospitals (SCORCH), no other published studies have specifically examined the frequency or clinical context of malpractice claims against pediatric radiologists or arising from pediatric imaging interpretation. We hypothesize that the frequency, character and outcome of malpractice claims made against pediatric radiologists differ from those seen in general radiology practice. We searched the Controlled Risk Insurance Co. (CRICO) Strategies' Comparative Benchmarking System (CBS), a private repository of approximately 350,000 open and closed medical malpractice claims in the United States, for claims related to pediatric radiology. We further queried these cases for the major allegation, the clinical environment in which the claim arose, the clinical severity of the alleged injury, indemnity paid (if payment was made), primary imaging modality involved (if applicable) and primary International Classification of Diseases, 9th revision (ICD-9) diagnosis underlying the claim. There were a total of 27,056 fully coded claims of medical malpractice in the CBS database in the 5-year period between Jan. 1, 2010, and Dec. 31, 2014. Of these, 1,472 cases (5.4%) involved patients younger than 18 years. Radiology was the primary service responsible for 71/1,472 (4.8%) pediatric cases. There were statistically significant differences in average payout for pediatric radiology claims ($314,671) compared to adult radiology claims ($174,033). The allegations were primarily diagnosis-related in 70% of pediatric radiology claims. The most common imaging modality implicated in

Radiological protection and quality control for diagnostic radiology in China

International Nuclear Information System (INIS)

Baorong, Yue

2008-01-01

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

FLIT: Flowing LIquid metal Torus

Science.gov (United States)

Kolemen, Egemen; Majeski, Richard; Maingi, Rajesh; Hvasta, Michael

2017-10-01

The design and construction of FLIT, Flowing LIquid Torus, at PPPL is presented. FLIT focuses on a liquid metal divertor system suitable for implementation and testing in present-day fusion systems, such as NSTX-U. It is designed as a proof-of-concept fast-flowing liquid metal divertor that can handle heat flux of 10 MW/m2 without an additional cooling system. The 72 cm wide by 107 cm tall torus system consisting of 12 rectangular coils that give 1 Tesla magnetic field in the center and it can operate for greater than 10 seconds at this field. Initially, 30 gallons Galinstan (Ga-In-Sn) will be recirculated using 6 jxB pumps and flow velocities of up to 10 m/s will be achieved on the fully annular divertor plate. FLIT is designed as a flexible machine that will allow experimental testing of various liquid metal injection techniques, study of flow instabilities, and their control in order to prove the feasibility of liquid metal divertor concept for fusion reactors. FLIT: Flowing LIquid metal Torus. This work is supported by the US DOE Contract No. DE-AC02-09CH11466.

Preliminary Characterization of the Liquid Discharge of the Mexico Hospital

International Nuclear Information System (INIS)

Hernandez Rojas, A

2001-01-01

The generation and wrong handling of hospital waste constitutes a serious problem at national level. In this work, a preliminary characterization of the discharge it liquidates of the Mexico Hospital is carried out. For it, different pouring points were analyzed inside the institution; they are: Laundry, Central Kitchen, Clinical Laboratory, X-Rays, Laboratory of Biomass, Morgue, and the final discharge of the hospital. This with the purpose of knowing the handling of the liquid waste in the health center, the sanitary quality of these liquids and their influence in the raw waters of the Mexico Hospital in the receiving body. For this study, we first coordinated with the personnel of each department to know about the handling and type of liquid residuals that are discharged to the system of pipes. Later on the physical-chemical and biological tests were carried out with base in two compound samplings done the days October 26 and November 4 1998. Among the carried out tests we have: pH, DBO, DQO, SAAM, Fatty and Oils, Temperature, Nitrogen and Faecal Coniforms, depending on the characteristics of their origin point. At the end of the study, the obtained results were evaluated for each studied pouring point, and then the influence of these focuses on the quality of the raw waters of the hospital that discharge in a gulch located to the northwest side of the facilities was analyzed. The obtained results allow to preliminarily know the characterization of the liquid discharge of the Mexico Hospital and it was classified as a source of contamination. The Hospital requires of a biological treatment plant for those biodegradable poured liquids, and of a system of chemical treatment for that type of products used in the processes characteristic of each department. It is also required to take into account measures of reduction of contamination that diminish the quantity of waste from the source. (Author) [es

Machine learning and radiology.

Science.gov (United States)

Wang, Shijun; Summers, Ronald M

2012-07-01

In this paper, we give a short introduction to machine learning and survey its applications in radiology. We focused on six categories of applications in radiology: medical image segmentation, registration, computer aided detection and diagnosis, brain function or activity analysis and neurological disease diagnosis from fMR images, content-based image retrieval systems for CT or MRI images, and text analysis of radiology reports using natural language processing (NLP) and natural language understanding (NLU). This survey shows that machine learning plays a key role in many radiology applications. Machine learning identifies complex patterns automatically and helps radiologists make intelligent decisions on radiology data such as conventional radiographs, CT, MRI, and PET images and radiology reports. In many applications, the performance of machine learning-based automatic detection and diagnosis systems has shown to be comparable to that of a well-trained and experienced radiologist. Technology development in machine learning and radiology will benefit from each other in the long run. Key contributions and common characteristics of machine learning techniques in radiology are discussed. We also discuss the problem of translating machine learning applications to the radiology clinical setting, including advantages and potential barriers. Copyright © 2012. Published by Elsevier B.V.

Radiology in Medical Education: A Pediatric Radiology Elective as a Template for Other Radiology Courses.

Science.gov (United States)

Hilmes, Melissa A; Hyatt, Eddie; Penrod, Cody H; Fleming, Amy E; Singh, Sudha P

2016-03-01

Traditionally, the pediatric radiology elective for medical students and pediatric residents constituted a morning teaching session focused mainly on radiography and fluoroscopy. A more structured elective was desired to broaden the exposure to more imaging modalities, create a more uniform educational experience, and include assessment tools. In 2012, an introductory e-mail and formal syllabus, including required reading assignments, were sent to participants before the start date. A rotating weekly schedule was expanded to include cross-sectional imaging (ultrasound, CT, MR) and nuclear medicine. The schedule could accommodate specific goals of the pediatric resident or medical student, as requested. Starting in 2013, an online pre-test and post-test were developed, as well as an online end-of-rotation survey specific to the pediatric radiology elective. Taking the Image Gently pledge was required. A scavenger hunt tool, cue cards, and electronic modules were added. Pre-test and post-test scores, averaged over 2 years, showed improvement in radiology knowledge, with scores increasing by 27% for medical students and 21% for pediatric residents. Surveys at the end of the elective were overwhelmingly positive, with constructive criticism and complimentary comments. We have successfully created an elective experience in radiology that dedicates time to education while preserving the workflow of radiologists. We have developed tools to provide a customized experience with many self-directed learning opportunities. Our tools and techniques are easily translatable to a general or adult radiology elective. Copyright © 2016 American College of Radiology. Published by Elsevier Inc. All rights reserved.

Assessment of radiological risks at the ATLAS experiment

International Nuclear Information System (INIS)

Zajacova, Z.

2009-07-01

activity is low (less than 1 %) the overall predictions are unaffected. The two studies together served as the basis for the radioactive waste zoning of ATLAS. Activation and radiological aspects of liquid argon from the ATLAS Liquid Argon Calorimeter were studied. First, we investigated the effective dose to selected population groups in case of an uncontrolled accidental release. We based this estimate on the assumption that all liquid argon from one end-cap calorimeter would leak out and all radioactivity in the liquid argon would be carried with it into the atmosphere. We based the calculations on pre-existing argon activation data. The calculations were performed with the EDAR code for the realistic topological data and adverse weather conditions. We estimated the effective dose that could be received by the people in the offices on the ATLAS site and by the people living on two nearby farms. Among these we identified the infants living on the closest farm as the critical population group, that would be potentially most affected. The critical exposure pathway that contributes most to the effective dose would be the ingestion of contaminated milk. The highest dose would come from 32 P in the milk. For this population group, the committed effective dose of 165 μSv was estimated. This is not negligible in comparison with the usual CERN goals for the radiological protection of the members of the general public but it is still compliant with the respective CERN guideline value of 300 μSv. Excluding ingestion, the maximum dose from external exposure and inhalation of 1:48 μSv was predicted for the people in the offices on site. We also investigated the conditions for a controlled planned release of the total amount of argon at the time of its disposal. We concluded that the release could occur after as little as 15 days of cooling time, provided that it occurs in winter, i.e., outside of the plant-growing season. Under these conditions, the estimated effective dose to

Handling of tritium-bearing wastes

International Nuclear Information System (INIS)

1981-01-01

The generation of nuclear power and reprocessing of nuclear fuel results in the production of tritium and the possible need to control the release of tritium-contaminated effluents. In assessing the need for controls, it is necessary to know the production rates of tritium at different nuclear facilities, the technologies available for separating tritium from different gaseous and liquid streams, and the methods that are satisfactory for storage and disposal of tritiated wastes. The intention in applying such control technologies and methods is to avoid undesirable effects on the environment, and to reduce the radiation burden on operational personnel and the general population. This technical report is a result of the IAEA Technical Committee Meeting on Handling of Tritium-bearing Effluents and Wastes, which was held in Vienna, 4 - 8 December 1978. It summarizes the main topics discussed at the meeting and appends the more detailed reports on particular aspects that were prepared for the meeting by individual participants

Radiology education: a radiology curriculum for all medical students?

Science.gov (United States)

Zwaan, Laura; Kok, Ellen M; van der Gijp, Anouk

2017-09-26

Diagnostic errors in radiology are frequent and can cause severe patient harm. Despite large performance differences between radiologists and non-radiology physicians, the latter often interpret medical images because electronic health records make images available throughout the hospital. Some people argue that non-radiologists should not diagnose medical images at all, and that medical school should focus on teaching ordering skills instead of image interpretation skills. We agree that teaching ordering skills is crucial as most physicians will need to order medical images in their professional life. However, we argue that the availability of medical images is so ubiquitous that it is important that non-radiologists are also trained in the basics of medical image interpretation and, additionally in recognizing when radiological consultancy should be sought. In acute situations, basic image interpretations skills can be life-saving. We plead for a radiology curriculum for all medical students. This should include the interpretation of common abnormalities on chest and skeletal radiographs and a basic distinction of normal from abnormal images. Furthermore, substantial attention should be given to the correct ordering of radiological images. Finally, it is critical that students are trained in deciding when to consult a radiologist.

Radiology education: a radiology curriculum for all medical students?

NARCIS (Netherlands)

Zwaan, Laura; Kok, E.M.; van der Gijp, Anouk

2017-01-01

Diagnostic errors in radiology are frequent and can cause severe patient harm. Despite large performance differences between radiologists and non-radiology physicians, the latter often interpret medical images because electronic health records make images available throughout the hospital. Some

Radiological optimization

International Nuclear Information System (INIS)

Zeevaert, T.

1998-01-01

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

Quality control in diagnostic radiology: software (Visual Basic 6) and database applications

International Nuclear Information System (INIS)

Md Saion Salikin; Muhammad Farid Abdul Khalid

2002-01-01

Quality Assurance programme in diagnostic Radiology is being implemented by the Ministry of Health (MoH) in Malaysia. Under this program the performance of an x-ray machine used for diagnostic purpose is tested by using the approved procedure which is commonly known as Quality Control in diagnostic radiology. The quality control or performance tests are carried out b a class H licence holder issued the Atomic Energy Licensing Act 1984. There are a few computer applications (software) that are available in the market which can be used for this purpose. A computer application (software) using Visual Basics 6 and Microsoft Access, is being developed to expedite data handling, analysis and storage as well as report writing of the quality control tests. In this paper important features of the software for quality control tests are explained in brief. A simple database is being established for this purpose which is linked to the software. Problems encountered in the preparation of database are discussed in this paper. A few examples of practical usage of the software and database applications are presented in brief. (Author)

Development of national level preparedness for response to nuclear and radiological emergencies

International Nuclear Information System (INIS)

Pradeepkumar, K.S.

2014-01-01

In India, DAE being the nodal agency for technical support for response to any radiation emergency nuclear disaster and various nuclear and radiological emergency scenarios and their impacts are identified. To reduce their consequences development of methodologies for detection and quick impact assessment, trained First Responders and Quick Response Teams (QRTs), twenty two DAE Emergency Response Centers, mobile and aerial radiation monitoring systems, aerial and ground based validation trials etc. are carried out. Study related to radiological threats and simulated RDD experiments conducted using stable isotopes indicates that radiation levels for distances more than 50 m will not be very high as hotspots may be restricted to nearby area. The biggest challenge from an RDD explosion will be handling of the radioactive contamination and 'fear factor' compared to radiation exposure to public or First Responders. Level and pattern of radioactive contamination on ground following releases during nuclear accidents and minimum strength of orphan radioactive sources to be detected are taken into account for optimizing systems and monitoring methodology required for emergency preparedness

Radiology systems architecture.

Science.gov (United States)

Deibel, S R; Greenes, R A

1996-05-01

This article focuses on the software requirements for enterprise integration in radiology. The needs of a future radiology systems architecture are examined, both at a concrete functional level and at an abstract system-properties level. A component-based approach to software development is described and is validated in the context of each of the abstract system requirements for future radiology computing environments.

Radiological controls integrated into design

Energy Technology Data Exchange (ETDEWEB)

Kindred, G.W. [Cleveland Electric Illuminating Co., Perry, OH (United States)

1995-03-01

Radiological controls are required by law in the design of commercial nuclear power reactor facilities. These controls can be relatively minor or significant, relative to cost. To ensure that radiological controls are designed into a project, the health physicist (radiological engineer) must be involved from the beginning. This is especially true regarding keeping costs down. For every radiological engineer at a nuclear power plant there must be fifty engineers of other disciplines. The radiological engineer cannot be an expert on every discipline of engineering. However, he must be knowledgeable to the degree of how a design will impact the facility from a radiological perspective. This paper will address how to effectively perform radiological analyses with the goal of radiological controls integrated into the design package.

New era of the relationship between Chinese interventional radiology sub-society and journal of interventional radiology

International Nuclear Information System (INIS)

Li Linsun

2009-01-01

The past decades have witnessed interventional radiology in China to go from a very initial clinical practice to an important medical player in modern medicine. Recently, a friendly collaboration has been successfully established between the Chinese Interventional Radiology Sub-society and the Journal of Interventional Radiology. The Chinese Interventional Radiology Sub-society will take the full responsibility for the academic governance of the Journal of Interventional Radiology and the Journal of Interventional Radiology will formally become the sole interventional academic periodical of the Chinese Interventional Radiology Sub-society in China. This collaboration will surely make Chinese interventional radiology to initiate a new era,promote the further development of interventional radiology at home and enable the Journal of Interventional Radiology to step into the international medical circle. (authors)

Procedures in diagnostic radiology

International Nuclear Information System (INIS)

Doyle, T.; Hare, W.S.C.; Thomson, K.; Tess, B.

1989-01-01

This book outlines the various procedures necessary for the successful practice of diagnostic radiology. Topics covered are: general principles, imaging of the urinary and gastrointestinal tracts, vascular radiology, arthrography, and miscellaneous diagnostic radiologic procedures

Proposal of inspection methodology for environment radiological control

International Nuclear Information System (INIS)

Martins, Nadia Soido Falcao

2005-01-01

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

A radiological case collection with interactive character as a new element in the education of medical students

International Nuclear Information System (INIS)

Heye, T.; Kurz, P.; Eiers, M.; Kauffmann, G.W.; Schipp, A.

2008-01-01

Purpose: evaluation of an interactive, multimedia case-based learning platform for the radiological education of medical students. Materials and methods: an interactive electronic learning platform for the education of medical students was built in html format independent of the operating system in the context of the Heidelberg Curriculum Medicinale (HeiCuMed). A case collection of 30 common and authentic clinical cases is used as the central theme and clinical background. The user has to work on each case by making decisions regarding a selection of diagnostic modalities and by analyzing the chosen studies. After a reasonable selection and sequence of diagnostic radiological modalities and their interpretation, a diagnosis has to be made. An extensive collection of normal findings for any modality is available for the user as a reference in correlation with the pathology at anytime within each case. The case collection consists of 2053 files with 1109 Internet pages (html) and 869 image files (jpeg) with approximately 10 000 crosslinks (links). The case collection was evaluated by a questionnaire (scale 1 - 5) at the end of the radiological student course. The development of the results of the radiological course exam was analyzed to investigate any effect on the learning performance after the case collection was introduced. Results: 97.6% of the course participants would use the case collection beyond the radiological student course to learn radiology in their medical studies. The handling of the case collection was rated excellent in 36.9%, good in 54.6%, satisfactory in 8% and unsatisfactory in 0.4%. 41% felt that the case collection was overall excellent, 49.2% good, 7.8% satisfactory, 1.6% unsatisfactory and 0.4% poor. A positive trend in the development of the results in the radiological course exam with less variance after the introduction of the case collection was found but failed statistical significance. (orig.)

Socioeconomic trends in radiology

International Nuclear Information System (INIS)

Barneveld Binkhuysen, F.H.

1998-01-01

For radiology the socioeconomic environment is a topic of increasing importance. In addition to the well-known important scientific developments in radiology such as interventional MRI, several other major trends can be recognized: (1) changes in the delivery of health care, in which all kinds of managed care are developing and will influence the practice of radiology, and (2) the process of computerization and digitization. The socioeconomic environment of radiology will be transformed by the developments in managed care, teleradiology and the integration of information systems. If radiologists want to manage future radiology departments they must have an understanding of the changes in the fields of economics and politics that are taking place and that will increasingly influence radiology. Some important and recognizable aspects of these changes will be described here. (orig.)

Radiologic findings of double contrast knee arthrography

International Nuclear Information System (INIS)

Choi, Hye Ran; Ahn, Byeong Yeob; Kim, Mi Young; Lee, So Hyun; Suh, Chang Hae; Chung, Won Kyun

1990-01-01

The double contrast arthrography of the knee is a highly accurate diagnostic modality in wide rage of the clinical disorders of the knee. It allows radiological assessment of the menisci, the articular cartilages, the synovium and the ligaments. The double contrast knee arthrography was performed in 356 cases at Inha hospital for about 3 years from June 1986 to June 1989. Among them, 115 cases were abnormal, and were analyzed clinically and radiologically with the back ground of the operative finding. The results were as follows ; 1. Of the 115 cases, male were 77 and female 38. Male exceeds female in the ratio of 2 : 1. 2. The age group of 20 - 39 years was commonly involved (60%). 3. The right knee was more commonly involved than the left and the medial meniscus tear was more common (61%). The posterior horn of the meniscus was more frequently torn than the other parts of the meniscus (42%). 4. The incidence of the bucket-handle tear was the most frequent (33%). 5. The cases of the popliteal cyst were 16 (13.9%), and the combined meniscus tears were in 4 cases (25%). 6. The numbers of the discoid meniscus were 9 (7.8%), and all were present in the lateral meniscus, and combined tears were in 4 cases (44.4%). 7. The diagnostic accuracy of the double contrast knee arthrogram was 82.7% compared with operative finding. The false positive examination were 17.3%

Development of a computer program for supporting to the radiological adviser in the management of an emergency situation

International Nuclear Information System (INIS)

Loureiro, E.C.M.; Ferreira F, A.L.; Andrade L, F.R. de

2006-01-01

One of the more important aspects of the handling of a radiological emergency it is the capacity for, in an immediate and appropriate way, to take the actions to protect the public members and the personnel that intervenes in the emergency. The evaluation of the radiological accident should keep in mind the whole available pertinent information in any moment and it should be an iterative and dynamic process directed to examine the answer in the measure that more complete and detailed information is available. This work presents a program in Delphi, with the tools, generic procedures and the necessary data to support to the radiological advisory in the initial answer to a radiological accident. It is based on the IAEA document, Generic Procedures for the Evaluation and Answer during a radiological emergency, the IAEA-TECDOC-1162. These procedures offer clear, concise and predetermined action criteria, based on the current knowledge and in the accumulated experiences, allowing the immediate decision making. The philosophy is to maintain the simple and quick, but effective process. The objective is to toast, through a laptop, practical and quick orientation for the answer to emergencies that of being implemented, it will provide an estimation or basic evaluation of the situation and it will guarantee the capacity of necessary answer to protect the public and the workers in the event of different types of radiological emergencies. Besides the recommendations of actions of appropriate protection, also it will toast, when it is necessary, orientations on the recovery of sources and initial operations of cleaning. (Author)

NOCHAR Polymers: An Aqueous and Organic Liquid Solidification Process for Cadarache LOR (Liquides Organiques Radioactifs) - 13195

International Nuclear Information System (INIS)

Vaudey, Claire-Emilie; Renou, Sebastien; Porco, Julien; Kelley, Dennis; Cochaud, Chantal; Serrano, Roger

2013-01-01

To handle the Very Low Level Waste (VLLW) and the Low Level Waste (LLW) in France, two options can be considered: the incineration at CENTRACO facility and the disposal facility on ANDRA sites. The waste acceptance in these radwaste routes is dependent upon the adequacy between the waste characteristics (physical chemistry and radiological) and the radwaste route specifications. If the waste characteristics are incompatible with the radwaste route specifications (presence of significant quantities of chlorine, fluorine, organic component etc or/and high activity limits), it is necessary to find an alternative solution that consists of a waste pre-treatment process. In the context of the problematic Cadarache LOR (Liquides Organiques Radioactifs) waste streams, two radioactive scintillation cocktails have to be treated. The first one is composed of organic liquids at 13.1 % (diphenyloxazol, mesitylene, TBP, xylene) and water at 86.9 %. The second one is composed of TBP at 8.6 % and water at 91.4 %. They contain chlorine, fluorine and sulphate and have got alpha/beta/gamma spectra with mass activities equal to some kBq.g -1 . Therefore, tritium is present and creates the second problematic waste stream. As a consequence, in order for disposal acceptance at the ANDRA site, it is necessary to pre-treat the waste. The NOCHAR polymers as an aqueous and organic liquid solidification process seem to be an adequate solution. Indeed, these polymers constitute an important variety of products applied to the treatment of radioactive aqueous and organic liquids (solvent, oil, solvent/oil mixing etc) and sludge through a mechanical and chemical solidification process. For Cadarache LOR, N910 and N960 respectively dedicated to the organic and aqueous liquids solidification are considered. With the N910, the organic waste solidification occurs in two steps. As the organic liquid travels moves through the polymer strands, the strands swell and immobilise the liquid. Then as the

Performance Assessment for the Idaho National Laboratory Remote-Handled Low-Level Waste Disposal Facility

Energy Technology Data Exchange (ETDEWEB)

Annette L. Schafer; A. Jeffrey Sondrup; Arthur S. Rood

2012-05-01

This performance assessment for the Remote-Handled Low-Level Radioactive Waste Disposal Facility at the Idaho National Laboratory documents the projected radiological dose impacts associated with the disposal of low-level radioactive waste at the facility. This assessment evaluates compliance with the applicable radiological criteria of the U.S. Department of Energy and the U.S. Environmental Protection Agency for protection of the public and the environment. The calculations involve modeling transport of radionuclides from buried waste to surface soil and subsurface media, and eventually to members of the public via air, groundwater, and food chain pathways. Projections of doses are calculated for both offsite receptors and individuals who inadvertently intrude into the waste after site closure. The results of the calculations are used to evaluate the future performance of the low-level radioactive waste disposal facility and to provide input for establishment of waste acceptance criteria. In addition, one-factor-at-a-time, Monte Carlo, and rank correlation analyses are included for sensitivity and uncertainty analysis. The comparison of the performance assessment results to the applicable performance objectives provides reasonable expectation that the performance objectives will be met

Full scale tests on remote handled FFTF fuel assembly waste handling and packaging

International Nuclear Information System (INIS)

Allen, C.R.; Cash, R.J.; Dawson, S.A.; Strode, J.N.

1986-01-01

Handling and packaging of remote handled, high activity solid waste fuel assembly hardware components from spent FFTF reactor fuel assemblies have been evaluated using full scale components. The demonstration was performed using FFTF fuel assembly components and simulated components which were handled remotely using electromechanical manipulators, shielding walls, master slave manipulators, specially designed grapples, and remote TV viewing. The testing and evaluation included handling, packaging for current and conceptual shipping containers, and the effects of volume reduction on packing efficiency and shielding requirements. Effects of waste segregation into transuranic (TRU) and non-transuranic fractions also are discussed

Dental radiology

International Nuclear Information System (INIS)

Bhaskar, S.N.

1982-01-01

The book presents the radiological manifestations of the maxillodental region in a suitable manner for fast detection and correct diagnosing of diseases of the teeth, soft tissue, and jaws. Classification therefore is made according to the radiological manifestations of the diseases and not according to etiology. (orig./MG) [de

Surface studies of liquid metals and alloys

International Nuclear Information System (INIS)

Bastasz, Robert

2003-01-01

Liquid metals and alloys have been proposed for use in nuclear fusion reactors to serve as replaceable plasma-facing surfaces that remove particles and heat from reacting plasmas. Several materials are being considered for this purpose including lithium, gallium, and tin as well as some of the alloys made from these elements. In order to better understand the properties of liquid surfaces, the technique of low-energy ion scattering was used to examine the surface composition of several of these materials in vacuum as a function of temperature. Oxygen is found to rapidly segregate to the surface of several metallic liquids. The segregation process can be interpreted using a simple thermodynamic model based on Gibbs theory. In the case of an alloy of Sn and Li, Li also segregates to the liquid surface. This provides a means to produce a surface enriched in Li, which is more plasma compatible than Sn, without the need to handle large quantities of liquid Li. (author)

White Paper: Curriculum in Interventional Radiology.

Science.gov (United States)

Mahnken, Andreas H; Bücker, Arno; Hohl, Christian; Berlis, Ansgar

2017-04-01

Purpose  Scope and clinical importance of interventional radiology markedly evolved over the last decades. Consequently it was acknowledged as independent subspecialty by the "European Union of Medical Specialists" (UEMS). Based on radiological imaging techniques Interventional Radiology is an integral part of Radiology. Materials und Methods  In 2009 the German Society for Interventional Radiology and minimally-invasive therapy (DeGIR) developed a structured training in Interventional Radiology. In cooperation with the German Society of Neuroradiology (DGNR) this training was extended to also cover Interventional Neuroradiology in 2012. Tailored for this training in Interventional Radiology a structured curriculum was developed, covering the scope of this modular training. Results  The curriculum is based on the DeGIR/DGNR modular training concept in Interventional Radiology. There is also an European Curriculum and Syllabus for Interventional Radiology developed by the "Cardiovascular and Interventional Radiological Society of Europe" (CIRSE). The presented curriculum in Interventional Radiology is designed to provide a uniform base for the training in Interventional Radiology in Germany, based on the competencies obtained during residency. Conclusion  This curriculum can be used as a basis for training in Interventional Radiology by all training sites. Key Points: · Interventional Radiology is an integral part of clinical radiology. · The German Society for Interventional Radiology and minimally-invasive therapy (DeGIR) developed a curriculum in Interventional Radiology. · This curriculum is an integrative basis for the training in interventional. Citation Format · Mahnken AH, Bücker A, Hohl C et al. White Paper: Curriculum in Interventional Radiology. Fortschr Röntgenstr 2017; 189: 309 - 311. © Georg Thieme Verlag KG Stuttgart · New York.

Radiological protection

International Nuclear Information System (INIS)

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

2010-01-01

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

Introduction to CRRIS: a computerized radiological risk investigation system for assessing atmospheric releases of radionuclides

International Nuclear Information System (INIS)

Baes, C.F. III; Miller, C.W.; Kocher, D.C.; Sjoreen, A.L.; Murphy, B.D.

1985-08-01

The CRRIS is a Computerized Radiological Risk Investigation System consisting of eight fully integrated computer codes which calculate environmental transport of atmospheric releases of radionuclides and resulting doses and health risks to individuals or populations. Each code may also be used alone for various assessment applications. Radionuclides are handled by the CRRIS either in terms of the released radionuclides or the exposure radionuclides which consist of both the released nuclides and decay products that grow in during environmental transport. The CRRIS is not designed to simulate short-term effects. 51 refs

Radiology trainer. Musculoskeletal system

International Nuclear Information System (INIS)

Staebler, A.; Erlt-Wagner, B.

2006-01-01

This book enables students to simulate examinations. The Radiology Trainer series comprises the whole knowledge of radiology in the form of case studies for self-testing. It is based on the best-sorted German-language collection of radiological examinations of all organ regions. Step by step, radiological knowledge is trained in order to make diagnoses more efficient. The book series ensures optimal preparation for the final medical examinations and is also a valuable tool for practical training. (orig.)

Handling and Treatment of Poultry Hatchery Waste: A Review

Directory of Open Access Journals (Sweden)

Belinda Rodda

2011-01-01

Full Text Available A literature review was undertaken to identify methods being used to handle and treat hatchery waste. Hatchery waste can be separated into solid waste and liquid waste by centrifuging or by using screens. Potential methods for treating hatchery waste on site include use of a furnace to heat the waste to produce steam to run a turbine generator or to use an in line composter to stabilise the waste. There is also potential to use anaerobic digestion at hatcheries to produce methane and fertilisers. Hatcheries disposing wastewater into lagoons could establish a series of ponds where algae, zooplankton and fish utilise the nutrients using integrated aquaculture which cleans the water making it more suitable for irrigation. The ideal system to establish in a hatchery would be to incorporate separation and handling equipment to separate waste into its various components for further treatment. This would save disposal costs, produce biogas to reduce power costs at plants and produce a range of value added products. However the scale of operations at many hatcheries is too small and development of treatment systems may not be viable.

Use of film digitizers to assist radiology image management

Science.gov (United States)

Honeyman-Buck, Janice C.; Frost, Meryll M.; Staab, Edward V.

1996-05-01

The purpose of this development effort was to evaluate the possibility of using digital technologies to solve image management problems in the Department of Radiology at the University of Florida. The three problem areas investigated were local interpretation of images produced in remote locations, distribution of images to areas outside of radiology, and film handling. In all cases the use of a laser film digitizer interfaced to an existing Picture Archiving and Communication System (PACS) was investigated as a solution to the problem. In each case the volume of studies involved were evaluated to estimate the impact of the solution on the network, archive, and workstations. Communications were stressed in the analysis of the needs for all image transmission. The operational aspects of the solution were examined to determine the needs for training, service, and maintenance. The remote sites requiring local interpretation included were a rural hospital needing coverage for after hours studies, the University of Florida student infirmary, and the emergency room. Distribution of images to the intensive care units was studied to improve image access and patient care. Handling of films originating from remote sites and those requiring urgent reporting were evaluated to improve management functions. The results of our analysis and the decisions that were made based on the analysis are described below. In the cases where systems were installed, a description of the system and its integration into the PACS system is included. For all three problem areas, although we could move images via a digitizer to the archive and a workstation, there was no way to inform the radiologist that a study needed attention. In the case of outside films, the patient did not always have a medical record number that matched one in our Radiology Information Systems (RIS). In order to incorporate all studies for a patient, we needed common locations for orders, reports, and images. RIS orders

Proceedings of the 5th international conference on stability and handling of liquid fuels. Volume 1

Energy Technology Data Exchange (ETDEWEB)

Giles, H.N. [ed.

1995-03-01

This proceedings summarizes recent work concerning stability and handling of fuels. Jet fuels, gasolines, heavy oils, and distillate fuels were considered. Fuel issues relevant to environmental mandates were discussed. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database.

Oxygen Handling and Cooling Options in High Temperature Electrolysis Plants

Energy Technology Data Exchange (ETDEWEB)

Manohar S. Sohal; J. Stephen Herring

2008-07-01

Idaho National Laboratory is working on a project to generate hydrogen by high temperature electrolysis (HTE). In such an HTE system, safety precautions need to be taken to handle high temperature oxygen at ~830°C. This report is aimed at addressing oxygen handling in a HTE plant.. Though oxygen itself is not flammable, most engineering material, including many gases and liquids, will burn in the presence of oxygen under some favorable physicochemical conditions. At present, an absolute set of rules does not exist that can cover all aspects of oxygen system design, material selection, and operating practices to avoid subtle hazards related to oxygen. Because most materials, including metals, will burn in an oxygen-enriched environment, hazards are always present when using oxygen. Most materials will ignite in an oxygen-enriched environment at a temperature lower than that in air, and once ignited, combustion rates are greater in the oxygen-enriched environment. Even many metals, if ignited, burn violently in an oxygen-enriched environment. However, these hazards do not preclude the operations and systems involving oxygen. Oxygen can be safely handled and used if all the materials in a system are not flammable in the end-use environment or if ignition sources are identified and controlled. In fact, the incidence of oxygen system fires is reported to be low with a probability of about one in a million. This report is a practical guideline and tutorial for the safe operation and handling of gaseous oxygen in high temperature electrolysis system. The intent is to provide safe, practical guidance that permits the accomplishment of experimental operations at INL, while being restrictive enough to prevent personnel endangerment and to provide reasonable facility protection. Adequate guidelines are provided to govern various aspects of oxygen handling associated with high temperature electrolysis system to generate hydrogen. The intent here is to present acceptable

Ergonomic material-handling device

Science.gov (United States)

Barsnick, Lance E.; Zalk, David M.; Perry, Catherine M.; Biggs, Terry; Tageson, Robert E.

2004-08-24

A hand-held ergonomic material-handling device capable of moving heavy objects, such as large waste containers and other large objects requiring mechanical assistance. The ergonomic material-handling device can be used with neutral postures of the back, shoulders, wrists and knees, thereby reducing potential injury to the user. The device involves two key features: 1) gives the user the ability to adjust the height of the handles of the device to ergonomically fit the needs of the user's back, wrists and shoulders; and 2) has a rounded handlebar shape, as well as the size and configuration of the handles which keep the user's wrists in a neutral posture during manipulation of the device.

Radiology and social media: are private practice radiology groups more social than academic radiology departments?

Science.gov (United States)

Glover, McKinley; Choy, Garry; Boland, Giles W; Saini, Sanjay; Prabhakar, Anand M

2015-05-01

This study assesses the prevalence of use of the most commonly used social media sites among private radiology groups (PRGs) and academic radiology departments (ARDs). The 50 largest PRGs and the 50 ARDs with the highest level of funding from the National Institutes of Health were assessed for presence of a radiology-specific social media account on Facebook, Twitter, Instagram, Pinterest, YouTube, and LinkedIn. Measures of organizational activity and end-user activity were collected, including the number of posts and followers, as appropriate; between-group comparisons were performed. PRGs adopted Facebook 12 months earlier (P = .02) and Twitter 18 months earlier (P = .02) than did ARDs. A total of 76% of PRGs maintained ≥1 account on the social media sites included in the study, compared with 28% of ARDs (P Instagram, 2%. The prevalence of radiology-specific social media accounts for ARDs was: Facebook, 18%; LinkedIn, 0%; Twitter, 24%; YouTube, 6%; Pinterest, 0%; and Instagram, 0%. There was no significant difference between ARDs and PRGs in measures of end-user or organizational activity on Facebook or Twitter. Use of social media in health care is emerging as mainstream, with PRGs being early adopters of Facebook and Twitter in comparison with ARDs. Competitive environments and institutional policies may be strong factors that influence how social media is used by radiologists at the group and department levels. Copyright © 2015 American College of Radiology. Published by Elsevier Inc. All rights reserved.

Status of microwave process development for RH-TRU [remote-handled transuranic] wastes at Oak Ridge National Laboratory

International Nuclear Information System (INIS)

White, T.L.; Youngblood, E.L.; Berry, J.B.; Mattus, A.J.

1990-01-01

The Oak Ridge National Laboratory (ORNL) Waste Handling and Packaging Plant is developing a microwave process to reduce and solidify remote-handled transuranic (RH-TRU) liquids and sludges presently stored in large tanks at ORNL. Testing has recently begun on an in-drum microwave process using nonradioactive RH-TRU surrogates. The microwave process development effort has focused on an in-drum process to dry the RH-TRU liquids and sludges in the final storage container and then melt the salt residues to form a solid monolith. A 1/3-scale proprietary microwave applicator was designed, fabricated, and tested to demonstrate the essential features of the microwave design and to provide input into the design of the full-scale applicator. The microwave fields are uniform in one dimension to reduce the formation of hot spots on the microwaved wasteform. The final wasteform meets the waste acceptance criteria for the Waste Isolation Pilot Plant, a federal repository for defense transuranic wastes near Carlsbad, New Mexico. 7 refs., 1 fig., 1 tab

Radiological diagnostics in hyperparathyroidism

International Nuclear Information System (INIS)

Moedder, U.; Kuhn, F.P.; Gruetzner, G.

1991-01-01

The most important radiologically detectable effects of the primary and secondary hyperparathyroidism of the skeletal system and the periarticular soft tissue structures are presented. In the following sensitivity and specificity of radiological imaging - sonography, scintigraphy, computed tomography, magnetic resonance imaging, arteriography and selective venous sampling - in the preoperative diagnostic of the parathyroid adenomas are discussed. Therefore, radiological imaging can be omitted before primary surgery. It was only in secondary surgery that radiological process proved useful and a guide during surgical intervention. (orig.) [de

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

Science.gov (United States)

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

2017-03-01

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

The differential radiological impact of plutonium recycle in the light-water reactor fuel cycle: effluent discharges during normal operation

International Nuclear Information System (INIS)

Bouville, A.; Guetat, P.; Jones, J.A.; Kelly, G.N.; Legrand, J.; White, I.F.

1980-01-01

The radiological impact of a light-water reactor fuel cycle utilizing enriched uranium fuel may be altered by the recycle of plutonium. Differences in impact may arise during various operations in the fuel cycle: those which arise from effluents discharged during normal operation of the various installations comprising the fuel cycle are evaluated in this study. The differential radiological impact on the population of the European Communities (EC) of effluents discharged during the recycling of 10 tonnes of fissile plutonium metal is evaluated. The contributions from each stage of the fuel cycle, i.e. fuel fabrication, reactor operation and fuel reprocessing and conversion, are identified. Separate consideration is given to airborne and liquid effluents and account is taken of a wide range of environmental conditions, representative of the EC, in estimating the radiological impact. The recycle of plutonium is estimated to result in a reduction in the radiological impact from effluents of about 30% of that when using enriched uranium fuel

Liquid Natural Gas

International Nuclear Information System (INIS)

Anon.

1992-01-01

After a brief introduction on the origins of the Liquid Natural Gas (LNG) industry the production and transportation of LNG are discussed. Special attention is paid to the importance of the safety aspect during every activity or handling of LNG. Next the most important trade flows for LNG are dealt with. Two zones can be distinguished: the western part of the Pacific and the Atlantic basin. Subsequently the main aspects of a LNG-project are mentioned, as well as the success factors. Finally the prospects for the LNG-industry are reviewed. 11 figs

Engineering studies: high-level radioactive waste repositories task 3 - review of underground handling and emplacement. 1. Executive summary

Energy Technology Data Exchange (ETDEWEB)

1981-02-01

The report reviews proposals for transport, handling and emplacement of high-level radioactive waste in an underground repository with particular reference to: waste block size and configuration; self-shielded or partially-shielded block; stages of disposal; transport by road/rail to repository site; handling techniques within repository; emplacement in vertical holes or horizontal tunnels; repository access by adit, incline or shaft; conventional and radiological safety; costs; and major areas of uncertainty requiring research or development. In carrying out this programme due attention was given to work already carried out both in the U.K. and overseas and where appropriate comparisons with this work have been made to substantiate and explain the observations made in this report. The examination and use of this previous work however has been confined to those proposals which were considered capable of meeting the basic design criterion for a U.K. based repository, that the maximum temperature achieved by the host rock should not exceed 100/sup 0/C.

Pediatric radiology

International Nuclear Information System (INIS)

Benz-Bohm, G.

1997-01-01

Pediatric radiology is an important subsection of diagnostic radiology involving specific difficulties, but unfortunately is quite too often neglected as a subject of further education and training. The book therefore is not intended for specialists in the field, but for radiologists wishing to plunge deeper into the matter of pediatric radiology and to acquire a sound, basic knowledge and information about well-proven modalities, the resulting diagnostic images, and interpretation of results. The book is a compact guide and a helpful source of reference and information required for every-day work, or in special cases. With patients who are babies or children, the challenges are different. The book offers all the information needed, including important experience from pediatric hospital units that may be helpful in diagnostic evaluation, information about specific dissimilarities in anatomy and physiology which affect the imaging results, hints for radiology planning and performance, as well as information about the various techniques and their indication and achievements. The book presents a wide spectrum of informative and annotated images. (orig./CB) [de

Attention for pediatric interventional radiology

International Nuclear Information System (INIS)

Zhu Ming; Cheng Yongde

2005-01-01

Radiological interventions possess wide utilization in the diagnosis and treatment for pediatric patients. Pediatric interventional radiology is an important branch of interventional radiology and also an important branch of pediatric radiology. Pediatric interventional radiology has grown substantially over the last 30 years, radiologists closely cooperation with surgeons and other physicians providing a new horizon in the management of pediatric diseases in western countries. It includes pediatric cardiac interventional radiology, pediatric neuro-interventional radiology, pediatric vascular interventional radiology, pediatric nonvascular interventional radiology, pediatric tumor interventional radiology and others. In the United States, every children hospital which owns two hundred beds has to have special trained interventional radiologists in radiologic department installing with advanced digital subtraction angiographic equipment. Interventional therapeutic procedures and diagnostic angiography have been proceeding more and more for the congenital and acquired diseases of children. The promising results give use uprising and interventional therapy as an alternative or a replacement or supplement to surgical operation. Pediatric interventional radiology is rather underdeveloped in China with a few special pediatric interventional radiologist, lack of digital subtraction angiography equipment. Pediatric radiologists have no enough field for interventional procedures such as pediatric neuro-interventional radiology and pediatric vascular interventional radiology. In the contrary adult interventional radiologists do have better interventional jobs in China and Pediatric cardiologists also share the same trend. They perform angiocardiography for congenital heart diseases and treat congenital heart disease with interventional procedures including balloon dilation of valves and vessels, coil embolization of collaterals, patent ducts and other arterial fistulae

Cadarache LOR (liquides organiques radioactifs) treatment by a solidification process using NOCHAR polymers

International Nuclear Information System (INIS)

Vaudey, Claire-Emilie; Renou, Sebastien; Kelley, Dennis; Cochaud, Chantal; Serrano, Roger

2013-01-01

In France, two options can be considered to handle the Very Low Level Waste (VLLW) and the Low Level Waste (LLW). The first one is the incineration at CENTRACO facility and the second one is the disposal at ANDRA sites. The waste acceptance in these two channels is dependent upon the adequacy between the waste characteristics (physical chemistry and radiological) and the channel specifications. If the waste characteristics and the channel specifications (presence of significant quantities of halogens, complexing agents, organic components... or/and high activity limits) are incompatible, an alternative solution have to be identify. It consists of a waste pre-treatment process. For Cadarache LOR (Liquides Organiques Radioactifs) waste streams, two radioactive scintillation cocktails have to be treated. They are composed of a mix of organic liquids and water: for the first one, 19 % of organic compounds (xylene, mesitylene, diphenyloxazole, TBP...) and 86.9 % of water, and for the second one, 23 % of organic compounds (TBP...) and 77 % of water. They contain halogens (chlorine and fluorine), complexants agents (nitrate, sulphate, oxalate and formate) and have got αβγ spectra with mass activities equal to some 100 Bq/g. Therefore, tritium is also present. As a consequence, in order for storage acceptance at the ANDRA site, it is necessary to pre-treat the waste. An adequate solution seems to be a solidification process using NOCHAR polymers. Indeed, NOCHAR polymers correspond to an important variety of products applied to the treatment of radioactive aqueous and organic liquids (solvent, oil, solvent/oil mixing ...) and sludge through a mechanical and chemical solidification process. For Cadarache LOR, N910 and N960 respectively dedicated to the organic and aqueous liquids solidification are considered. With the N910, the organic waste solidification occurs in two steps. As the organic liquid travels moves through the polymer strands, the strands swell and

Aerial radiological survey of the area surrounding the Portsmouth Gaseous Diffusion Plant, Portsmouth, Ohio

International Nuclear Information System (INIS)

1979-09-01

An airborne radiological survey was conducted in July 1976. It was centered on the Portsmouth Gaseous Diffusion Plant. Two areas were surveyed: one 35 km 2 and the other 16 km 2 . Using Nal(Tl) scintillation detectors, measurements were made of the terrestrial gamma radiation over the areas with a series of north-south flight lines. The processed data indicated that on-site radioactivity was due to nuclear matterials currently or previously handled, processed, or stored. Off-site activities were found to be due wholly to the naturally occurring 40 K, the 238 U chain, and thorium chain gamma emitters

Radiological evaluation of dysphagia

Energy Technology Data Exchange (ETDEWEB)

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

1986-11-21

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

Radiological evaluation of dysphagia

International Nuclear Information System (INIS)

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

1986-01-01

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

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

International Nuclear Information System (INIS)

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

2001-01-01

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

The influence of molecule size and structure on the lubricity of liquids: An experimental study

DEFF Research Database (Denmark)

Sivebæk, Ion Marius; Sorenson, Spencer C

2002-01-01

to stay liquid. Recently a lubricity test capable of handling DME was developed [1], as well as a volatile fuel viscometer [2]. As a result of this development it has become possible to test the lubricity of small hydrocarbons such as propane and butane as well as liquids with larger molecules...

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...

Radiological characterisation of V1 NPP technological systems and buildings - Activation

International Nuclear Information System (INIS)

Kristofova, Kristina; Rapant, Tibor; Svitek, Jaroslav

2012-01-01

V1 NPP at Jaslovske Bohunice site has been finally shutdown after 28 years of successful operation in 2006 (Unit 1) and 2008 (Unit 2). At present, both units are finally shutdown and since July 2011 under decommissioning license. The preparation of V1 NPP decommissioning has been supported and partly financed by the Bohunice International Decommissioning Support Fund (BIDSF), under the administration of the European Bank for Reconstruction and Development. From 06/2008 to 12/2011 AMEC Nuclear Slovakia, together with partners STM Power and EWN GmbH, carried out BIDSF B6.4 project - Decommissioning database development (DDB). The main purpose of the B6.4 project was to develop a physical and radiological inventory database to support V1 NPP decommissioning process planning and performance. One of the specific deliverable tasks within the B6.4 project was deliverable D12 - Characterization of activated equipment and civil structures based on measurement, sampling and analyses performed on the samples. The scope of deliverable services within D12 task consisted of: 1. Categorization of activated components ; 2. Development of single working programs for their radiological monitoring and sampling ; 3. Preparation of sampling device and revision of all handling equipment; 4. Dose rate monitoring and sampling of: - Civil structures from reactors shaft on both units ; - Components placed in HLW storage, (so called 'Mogilnik') - connection rods, absorbers ; of control rod assemblies and neutron flux measurement channels ; - Reactor pressure vessel and shielding assemblies at both units of V1 NPP, reactor; internals from Unit 2 of V1 NPP; 5. Analysis of samples ; 6. Determination of radiological inventory ; 7. Import of radiological data for activated components into DDB. During sampling, mainly remotely controlled sampling device and radiation resistant camera with LED lightening for visual checking of all performed activities was used. In total, 125 samples have been taken

30o inclination in handles of plastic boxes can reduce postural and muscular workload during handling

Directory of Open Access Journals (Sweden)

Luciana C. C. B. Silva

2013-06-01

Full Text Available BACKGROUND: The handling of materials, which occurs in the industrial sector, is associated with lesions on the lumbar spine and in the upper limbs. Inserting handles in industrial boxes is a way to reduce work-related risks. Although the position and angle of the handles are significant factors in comfort and safety during handling, these factors have rarely been studied objectively. OBJECTIVE: To compare the handling of a commercial box and prototypes with handles and to evaluate the effects on upper limb posture, muscle electrical activity, and perceived acceptability using different grips while handling materials from different heights. METHOD: Thirty-seven healthy volunteers evaluated the handles of prototypes that allowed for changes in position (top and bottom and angle (0°, 15°, and 30°. Wrist, elbow, and shoulder movements were evaluated using electrogoniometry and inclinometry. The muscle electrical activity in the wrist extensors, biceps brachii, and the upper portion of the trapezius was measured using a portable electromyographer. The recorded data on muscle movements and electrical activity were synchronized. Subjective evaluations of acceptability were evaluated using a visual analog scale. RESULTS AND CONCLUSIONS: The prototypes with handles at a 30° angle produced the highest acceptability ratings, more neutral wrist positions, lower levels of electromyographic activity for the upper trapezius, and lower elevation angles for the arms. The different measurement methods were complementary in evaluating the upper limbs during handling.

New transport and handling contract

CERN Multimedia

SC Department

2008-01-01

A new transport and handling contract entered into force on 1.10.2008. As with the previous contract, the user interface is the internal transport/handling request form on EDH: https://edh.cern.ch/Document/TransportRequest/ To ensure that you receive the best possible service, we invite you to complete the various fields as accurately as possible and to include a mobile telephone number on which we can reach you. You can follow the progress of your request (schedule, completion) in the EDH request routing information. We remind you that the following deadlines apply: 48 hours for the transport of heavy goods (up to 8 tonnes) or simple handling operations 5 working days for crane operations, transport of extra-heavy goods, complex handling operations and combined transport and handling operations in the tunnel. For all enquiries, the number to contact remains unchanged: 72202. Heavy Handling Section TS-HE-HH 72672 - 160319

The handling of nuclear emergencies in Argentina

International Nuclear Information System (INIS)

Hernandez, Daniel; Jordan, Osvaldo; Kunst, Juan; Bruno, Hector

2008-01-01

Full text: In 1998, the Executive signed the decree 1390, which defined the scope and the procedures corresponding to the Nuclear Activity Law. In this decree, the new functions of the Nuclear Regulatory Authority (ARN) are described, being the most important related to preparation and response for a nuclear emergency the following ones: 1) ARN must provide protection from harmful effects of ionizing radiations under normal conditions and emergency situations; 2) ARN must advise the Executive in case of radiological and nuclear emergencies; 3) ARN shall establish the criteria for the emergency plans of the facilities and train the members of neighbor public to the facilities in case of nuclear emergencies; 4) The emergency plans developed by local, provincial and national authorities must be approved by the ARN; 5) ARN shall lead the actions within the area covered by the emergency plans of the facilities. Security Forces and the Representatives of Civil Institutions shall report the designated ARN officer. The ARN recognized immediately the responsibility imposed by this law and, at the same time, the opportunity of improving the handling of emergencies through a centralized direction of the operations. Under this frame, ARN created the Radiological Emergencies Intervention System (SIER) with the goal of taking charge of the preparation and the handling of emergency situations. From the beginning, the purpose of the SIER was to improve the preparation and response to nuclear emergencies in a regular form, bearing in mind the cultural and socioeconomic situation of the country, as well as the local peculiarities. The first steep to achieve such a target was to gain the confidence of other organizations included in the response on the ARN technical and operational aptitude to lead the actions inside the emergency area and, later, to establish the pertinent arrangements. The strategy chosen by ARN to respond to nuclear emergencies consists in establishing an expert

Highly cited works in radiology: the top 100 cited articles in radiologic journals.

Science.gov (United States)

Pagni, Matthew; Khan, Nickalus R; Cohen, Harris L; Choudhri, Asim F

2014-08-01

The number of citations a publication receives can be used to show its impact on a field of study. It may indicate the educational interest in a given population or underline a perceived or real educational gap. This article identifies and characterizes the 100 top cited publications in radiologic journals as of May 2013. All clinical radiologic journals listed by Thomson Reuters Journal Citation Reports in 2011 were identified. A total of 46 journals were identified, and all articles published within these journals were analyzed for citation counts. The top 100 highly cited articles were recorded. The most frequently cited radiologic articles appeared in 9 of the 46 journals. These included 59 articles in Radiology, 17 in Journal of Nuclear Medicine, 9 in the American Journal of Roentgenology, 5 in the British Journal of Radiology, 4 in Investigative Radiology, 2 in American Journal of Neuroradiology, 2 in European Radiology, 2 in Radiologic Clinics of North America, 1 in the Seminars in Nuclear Medicine, and 1 in Pediatric Radiology. The citation values ranged from 422 to 7506 with a mean of 751. Publication dates ranged from 1967 to 2006 with the 5-year period between 1986 and 1990 accounting for the largest percentage of articles. The most frequently studied radiologic modality was magnetic resonance imaging (MRI; 28 articles), followed by vascular/interventional (19 articles) and nuclear medicine (13 articles). The central nervous system was the most frequently studied organ system (22 articles), followed by mixed organ systems (14 articles) and liver (12 articles). The top cited articles in radiologic journals span a wide range of imaging modalities, subspecialties, and organ systems. Topics that occurred frequently in the top 100 cited articles included contrast and radiopharmaceutical characterization, MRI of motion, percutaneous radiofrequency ablation in the liver and percutaneous vertebroplasty. We present a methodology that uses citation analysis to

Liquid Scintillation Counting - Packard Triple-Label Calibration

Energy Technology Data Exchange (ETDEWEB)

Torretto, P. A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

2017-03-23

The Radiological Measurements Laboratory (RML) maintains and operates nine Packard Liquid Scintillation Counters (LSCs). These counters were obtained through various sources and were generally purchased as 2500, 2700 or 3100 series counters. In 2004/2005 the software and firmware on the counters were upgraded. The counters are now designated as 3100 series counters running the Quantasmart software package. Thus, a single procedure can be used to calibrate and operate the Packard LSCs.

Radiological Worker Training: Radiological Worker 2 lesson plans

International Nuclear Information System (INIS)

1992-10-01

Upon completion of this g course, the participant will have the knowledge to work safely in areas controlled for a radiological purposes using proper radiological practices. The participant will be able toidentify the fundamentals of radiation, radioactive material and radioactive contamination includes identify the three basic particles of an atom, define ionization, define ionizing radiation, radioactive material and radioactive contamination, distinguish between ionizing radiation and non-ionizing radiation, define radioactivity and radioactive half-life

Concentration device for leak liquids

International Nuclear Information System (INIS)

Matsumoto, Kaname; Matsuda, Ken; Takabori, Ken-ichi.

1987-01-01

Purpose: To improve radioactivity recovery and volume-reducing rates, as well as enable safety and easy handling for leak liquids resulted from reptures in coolant circuits. Constitution: The device of the invention comprises an evaporation vessel filled with leak fluids to a predetermined level, an airtight vessel disposed in the evaporation vessel containing hydrophilic porous material partially immersed in the leak fluids and means for heating the hydrophilic material. In this device, leak liquids are absorbed in the hydrophilic porous material, a great amount of water is evaporated from the outer surface of the hydrophilic porous material exposed above the liquid surface, and salts and radioactive material are remained on the inside and the outer surface of the porous material. The evaporated water content is condensated and recovered in a cooler and the remaining salts, etc. are discarded together with the porous material. The volume-reducing property can be improved by constituting the porous material with burnable material. (Takahashi, M.)

Simplified production of multimedia based radiological learning objects using the flash format

International Nuclear Information System (INIS)

Jedrusik, P.; Preisack, M.; Dammann, F.

2005-01-01

Purpose: evaluation of the applicability of the flash format for the production of radiological learning objects used in an e-learning environment. Material and methods: five exemplary learning objects with different didactic purposes referring to radiological diagnostics are presented. They have been intended for the use within the multimedia, internet-based e-learning environment LaMedica. Interactive learning objects were composed using the Flash 5.0 software (Macromedia, San Francisco, USA) on the basis of digital CT and MR images, digitized conventional radiographs and different graphical elements prepared as TIFF files or in a vector graphics format. Results: after a short phase of initial skill adaptation training, a radiologist author was soon able to create independently all learning objects. The import of different types of images and graphical elements was carried out without complications. Despite manifold design options, handling of the program is easy due to clear arrangement and structure, thus enabling the creation of simple as well as complex learning objects that provided a high degree of attractiveness and interaction. Data volume and bandwidth demand for online use was significantly reduced by the flash format compression without a substantial loss of visual quality. (orig.)

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)

Rational use of diagnostic radiology

International Nuclear Information System (INIS)

Racoveanu, N.T.; Volodin, V.

1992-01-01

The escalating number of radiodiagnostic investigations has, as a consequence, an increase in medical irradiation of patients and of cost of radiological services. Radiologists in USA and UK have since early 1970 questioned the efficacy of various radiological investigations and produced substantial evidence that more rational approaches are necessary. WHO initiated, in 1977, a programme in this direction which has issued four technical reports which give practical recommendations on how to rationalize the use of radiological examinations. Three main directions are considered: (1) Abandonment of routine radiological examinations, as procedures with no clinical or epidemiologic significance and which represent a waste of resources and patient dose. (2) Patient selection for various radiological investigations based on clinical criteria (high, intermediate, low yield). Selected patients have an increased prevalence of the given disease and the predictive value of radiological investigation is much higher. (3) Use of diagnostic algorithms with higher cost/efficiency and risk/benefit ratios, improving the outcome of radiological examinations

Trends in Modern Exception Handling

Directory of Open Access Journals (Sweden)

Marcin Kuta

2003-01-01

Full Text Available Exception handling is nowadays a necessary component of error proof information systems. The paper presents overview of techniques and models of exception handling, problems connected with them and potential solutions. The aspects of implementation of propagation mechanisms and exception handling, their effect on semantics and general program efficiency are also taken into account. Presented mechanisms were adopted to modern programming languages. Considering design area, formal methods and formal verification of program properties we can notice exception handling mechanisms are weakly present what makes a field for future research.

A Neutron Radiology Application to Natural Absorption (Imbibition) of Water into Porous Rocks

International Nuclear Information System (INIS)

Middleton, M.F.; de Beer, Frikkie

2005-01-01

Full text: Dynamic neutron radiology provides a method of evaluating the concentration of water in porous media. A study of water imbibition (absorption of a wetting liquid into a porous medium with a non-wetting fluid, air), which is imaged by dynamic neutron radiology , provides an excellent method of determining the fluid diffusivity parameter, D. This parameter enables one to model water-air regimes in surface hydrological systems and aquifers; analogies can also be made for deeper petroleum systems. A methodology of pixel-by-pixel analysis for the estimation of water concentration, as a function of time under natural absorption conditions, is proposed which provides a good mapping of D within a rock sample. The proposed method entails the discrete mapping of the differential equation for horizontal flow of a partial water concentration, c, in an air-filled rock/soil. (authors)

The radiological services laboratory

International Nuclear Information System (INIS)

Hardt, T.L.; Schutt, S.M.; Doran, K.S.; Dihel, D.L.; Lucas, R.O. II; Eifert, T.K.

1992-01-01

A new state of the art radiochemistry laboratory incorporating advanced design and environmental control elements has been constructed in Atlanta, Georgia. The design of the facility is oriented to the efficient production of analytical sample results which meet regulatory requirements while at the same time provides an atmosphere that is pleasurable for analysts and visitors alike. The laboratory building contains two separate and distinct laboratories under one roof. This allows the facility to handle samples with low levels of radioactivity on one side of the lab without fear of contamination of environmental work on the other side. Unlike most laboratories, this facility utilizes a scrubber system and liquid waste holdup system to prevent accidental releases to the environment. The potential spread of radioactive contamination is controlled through the use of negative pressure ventillation zones. Construction techniques, laboratory systems, instrumentation and ergonomic considerations will also be discussed. (author) 1 fig

Optimization in radiological protection

International Nuclear Information System (INIS)

Acosta Perez, Clarice de Freitas

1996-01-01

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

Occupational exposure in interventional radiology

International Nuclear Information System (INIS)

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

2003-01-01

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

Marks in Latin-American radiology

International Nuclear Information System (INIS)

Souza Almeida, S. de.

1987-01-01

An historical retrospective of Latin-American radiology is shortly presented. Several radiologic societies as well as personalities, scientists and doctors are reported emphasizing their contribuition to radiologic Latin-American culture. (M.A.C.) [pt

Rational use of diagnostic radiology

International Nuclear Information System (INIS)

Racoveanu, N.T.; Volodin, V.

1992-01-01

Radiologists in USA and UK have since early 1970 questioned the efficacy of various radiological investigations and produced substantial evidence that more rational approaches are necessary. WHO initiated, in 1977, a programme which has issued four technical reports giving practical recommendations on how to rationalise the use of radiological examinations. Three main directions are considered: (1) Abandonment of routine radiological examinations, as procedures with no clinical or epidemiologic significance and which represent a waste of resources and patient dose. (2) Patient selection for various radiological investigations based on clinical criteria (high, intermediate, low yield). Selected patients have an increased prevalence of the given disease and the predictive value of radiological investigation is much higher. (3) Use of diagnostic algorithms with higher cost/efficiency and risk/benefit ratios, improving the outcome of radiological examinations. (author)

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

International Nuclear Information System (INIS)

Thome, D.J.

1995-01-01

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

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

International Nuclear Information System (INIS)

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

2008-01-01

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

Remote handling machines

International Nuclear Information System (INIS)

Sato, Shinri

1985-01-01

In nuclear power facilities, the management of radioactive wastes is made with its technology plus the automatic techniques. Under the radiation field, the maintenance or aid of such systems is important. To cope with this situation, MF-2 system, MF-3 system and a manipulator system as remote handling machines are described. MF-2 system consists of an MF-2 carrier truck, a control unit and a command trailer. It is capable of handling heavy-weight objects. The system is not by hydraulic but by electrical means. MF-3 system consists of a four-crawler truck and a manipulator. The truck is versatile in its posture by means of the four independent crawlers. The manipulator system is bilateral in operation, so that the delicate handling is made possible. (Mori, K.)

Reconstructive dosimetry and radiation doses evaluation of members of the public due to radiological accident in industrial radiography

International Nuclear Information System (INIS)

Lima, Camila Moreira Araujo de

2016-01-01

Radiological accidents have occurred mainly in the practices recognized as high risk radiological and classified by the IAEA as Categories 1 and 2, and highlighted the radiotherapy, industrial irradiators and industrial radiography. In Brazil, since there were five major cases in industrial radiography, which involved 7 radiation workers and 19 members of the public, causing localized radiation lesions on the hands and fingers. One of these accidents will be the focus of this work. In this accident, a "1"9"2Ir radioactive source was exposed for more than 8 hours in the workplace inside a company, exposing radiation workers, individuals of the public and people from the surrounding facilities, including children of a school. The radioactive source was also handled by a security worker causing severe radiation injuries in the hand and fingers. In this paper, the most relevant and used techniques of reconstructive dosimetry internationally are presented. To estimate the radiation doses received by exposed individuals in various scenarios of radiological accident in focus, the following computer codes were used: Visual Monte Carlo Dose Calculation (VMC), Virtual Environment for Radiological and Nuclear Accidents Simulation (AVSAR) and RADPRO Calculator. Through these codes some radiation doses were estimated, such as, 33.90 Gy in security worker's finger, 4.47 mSv in children in the school and 55 to 160 mSv for workers in the company during the whole day work. It is intended that this work will contribute to the improvement of dose reconstruction methodology for radiological accidents, having then more realist radiation doses. (author)

Ergonomics in radiology

Energy Technology Data Exchange (ETDEWEB)

Goyal, N. [Department of Radiology, University Hospital of Wales, Cardiff (United Kingdom)], E-mail: nimitgoyal@doctors.org.uk; Jain, N.; Rachapalli, V. [Department of Radiology, University Hospital of Wales, Cardiff (United Kingdom)

2009-02-15

The use of computers is increasing in every field of medicine, especially radiology. Filmless radiology departments, speech recognition software, electronic request forms and teleradiology are some of the recent developments that have substantially increased the amount of time a radiologist spends in front of a computer monitor. Computers are also needed for searching literature on the internet, communicating via e-mails, and preparing for lectures and presentations. It is well known that regular computer users can suffer musculoskeletal injuries due to repetitive stress. The role of ergonomics in radiology is to ensure that working conditions are optimized in order to avoid injury and fatigue. Adequate workplace ergonomics can go a long way in increasing productivity, efficiency, and job satisfaction. We review the current literature pertaining to the role of ergonomics in modern-day radiology especially with the development of picture archiving and communication systems (PACS) workstations.

Ergonomics in radiology

International Nuclear Information System (INIS)

Goyal, N.; Jain, N.; Rachapalli, V.

2009-01-01

The use of computers is increasing in every field of medicine, especially radiology. Filmless radiology departments, speech recognition software, electronic request forms and teleradiology are some of the recent developments that have substantially increased the amount of time a radiologist spends in front of a computer monitor. Computers are also needed for searching literature on the internet, communicating via e-mails, and preparing for lectures and presentations. It is well known that regular computer users can suffer musculoskeletal injuries due to repetitive stress. The role of ergonomics in radiology is to ensure that working conditions are optimized in order to avoid injury and fatigue. Adequate workplace ergonomics can go a long way in increasing productivity, efficiency, and job satisfaction. We review the current literature pertaining to the role of ergonomics in modern-day radiology especially with the development of picture archiving and communication systems (PACS) workstations

How Secure Is Your Radiology Department? Mapping Digital Radiology Adoption and Security Worldwide.

Science.gov (United States)

Stites, Mark; Pianykh, Oleg S

2016-04-01

Despite the long history of digital radiology, one of its most critical aspects--information security--still remains extremely underdeveloped and poorly standardized. To study the current state of radiology security, we explored the worldwide security of medical image archives. Using the DICOM data-transmitting standard, we implemented a highly parallel application to scan the entire World Wide Web of networked computers and devices, locating open and unprotected radiology servers. We used only legal and radiology-compliant tools. Our security-probing application initiated a standard DICOM handshake to remote computer or device addresses, and then assessed their security posture on the basis of handshake replies. The scan discovered a total of 2774 unprotected radiology or DICOM servers worldwide. Of those, 719 were fully open to patient data communications. Geolocation was used to analyze and rank our findings according to country utilization. As a result, we built maps and world ranking of clinical security, suggesting that even the most radiology-advanced countries have hospitals with serious security gaps. Despite more than two decades of active development and implementation, our radiology data still remains insecure. The results provided should be applied to raise awareness and begin an earnest dialogue toward elimination of the problem. The application we designed and the novel scanning approach we developed can be used to identify security breaches and to eliminate them before they are compromised.

Diagnostic imaging, a 'parallel' discipline. Can current technology provide a reliable digital diagnostic radiology department

International Nuclear Information System (INIS)

Moore, C.J.; Eddleston, B.

1985-01-01

Only recently has any detailed criticism been voiced about the practicalities of the introduction of generalised, digital, imaging complexes in diagnostic radiology. Although attendant technological problems are highlighted the authors argue that the fundamental causes of current difficulties are not in the generation but in the processing, filing and subsequent retrieval for display of digital image records. In the real world, looking at images is a parallel process of some complexity and so it is perhaps untimely to expect versatile handling of vast image data bases by existing computer hardware and software which, by their current nature, perform tasks serially. (author)

Radiological operating experience at FFTF [Fast Flux Test Facility

International Nuclear Information System (INIS)

Bunch, W.L.; Prevo, P.R.

1986-11-01

The Fast Flux Test Facility has been in operation for approximately five years, including about one thousand days of full power operation of the Fast Test Reactor. During that time the collective dose equivalents received by operating personnel have been about two orders of magnitude lower than those typically received at commercial light water reactors. No major contamination problems have been encountered in operating and maintaining the plant, and release of radioactive gas to the environment has been minimal and well below acceptable limits. All shields have performed satisfactorily. Experience to date indicates an apparent radiological superiority of liquid metal reactor systems over current light water plants

Bismuth Infusion of ABS Enables Additive Manufacturing of Complex Radiological Phantoms and Shielding Equipment

Directory of Open Access Journals (Sweden)

Justin Ceh

2017-02-01

Full Text Available Radiopacity is a critical property of materials that are used for a range of radiological applications, including the development of phantom devices that emulate the radiodensity of native tissues and the production of protective equipment for personnel handling radioactive materials. Three-dimensional (3D printing is a fabrication platform that is well suited to creating complex anatomical replicas or custom labware to accomplish these radiological purposes. We created and tested multiple ABS (Acrylonitrile butadiene styrene filaments infused with varied concentrations of bismuth (1.2–2.7 g/cm3, a radiopaque metal that is compatible with plastic infusion, to address the poor gamma radiation attenuation of many mainstream 3D printing materials. X-ray computed tomography (CT experiments of these filaments indicated that a density of 1.2 g/cm3 of bismuth-infused ABS emulates bone radiopacity during X-ray CT imaging on preclinical and clinical scanners. ABS-bismuth filaments along with ABS were 3D printed to create an embedded human nasocranial anatomical phantom that mimicked radiological properties of native bone and soft tissue. Increasing the bismuth content in the filaments to 2.7 g/cm3 created a stable material that could attenuate 50% of 99mTechnetium gamma emission when printed with a 2.0 mm wall thickness. A shielded test tube rack was printed to attenuate source radiation as a protective measure for lab personnel. We demonstrated the utility of novel filaments to serve multiple radiological purposes, including the creation of anthropomorphic phantoms and safety labware, by tuning the level of radiation attenuation through material customization.

Safety of Cargo Aircraft Handling Procedure

Directory of Open Access Journals (Sweden)

Daniel Hlavatý

2017-07-01

Full Text Available The aim of this paper is to get acquainted with the ways how to improve the safety management system during cargo aircraft handling. The first chapter is dedicated to general information about air cargo transportation. This includes the history or types of cargo aircraft handling, but also the means of handling. The second part is focused on detailed description of cargo aircraft handling, including a description of activities that are performed before and after handling. The following part of this paper covers a theoretical interpretation of safety, safety indicators and legislative provisions related to the safety of cargo aircraft handling. The fourth part of this paper analyzes the fault trees of events which might occur during handling. The factors found by this analysis are compared with safety reports of FedEx. Based on the comparison, there is a proposal on how to improve the safety management in this transportation company.

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

International Nuclear Information System (INIS)

Thome, D.J.

1994-01-01

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

Informatics in radiology: radiology gamuts ontology: differential diagnosis for the Semantic Web.

Science.gov (United States)

Budovec, Joseph J; Lam, Cesar A; Kahn, Charles E

2014-01-01

The Semantic Web is an effort to add semantics, or "meaning," to empower automated searching and processing of Web-based information. The overarching goal of the Semantic Web is to enable users to more easily find, share, and combine information. Critical to this vision are knowledge models called ontologies, which define a set of concepts and formalize the relations between them. Ontologies have been developed to manage and exploit the large and rapidly growing volume of information in biomedical domains. In diagnostic radiology, lists of differential diagnoses of imaging observations, called gamuts, provide an important source of knowledge. The Radiology Gamuts Ontology (RGO) is a formal knowledge model of differential diagnoses in radiology that includes 1674 differential diagnoses, 19,017 terms, and 52,976 links between terms. Its knowledge is used to provide an interactive, freely available online reference of radiology gamuts ( www.gamuts.net ). A Web service allows its content to be discovered and consumed by other information systems. The RGO integrates radiologic knowledge with other biomedical ontologies as part of the Semantic Web. © RSNA, 2014.

Protocol for therapy of people who suffered wounds from radioactive material in radiological and nuclear accidents

International Nuclear Information System (INIS)

Lopes, Amanda Gomes

2015-01-01

The handling of glassware in ampoules, containing solution is very common in research or production laboratories. During manipulation, there is a likelihood of occurrence of incidents such as the breaking of ampoules or glass vials containing material in liquid or powdered form which may cause a wound to the possibility of contamination with handled material. When the solution is radioactive there is a concern due to the risk of incorporation of that material. According to NCRP 156, the scientific literature contains over 2100 cases of wounds contaminated with radionuclides and more than 90% of the reported cases occurred in the hands and arms, but mainly on the fingers. Despite having no cases of wounds reported radioactive material in Brazil or a protocol developed by the National Agencies, applications and hence the manipulation of radionuclides is increasing in the country, rising the possibility of wound occurrence contaminated by radionuclides. In this work was proposed a methodology for management of individuals who suffered wounds from radioactive material in cases of nuclear accidents and radiological emergencies that present intake, which consisted of four steps: definition of the accident scenario, individual triage of the public or workers, proper measurements with detectors PRD, IdentiFINDER2 and germanium in different thicknesses material tissue-equivalent, and later adoption of first aid measures consisting of attendance, monitoring of contaminated personnel, evaluation of effective dose and direct to specialized medical center. As an example of results it follows the case of 241 Am where the best performance was obtained by measurements with the shielded HPGe (7%) and the shielded and collimation of 0.5 cm IdentiFINDER2 (10%). While, unshielded PRD, unshielded or shielded side IdentiFINDER2 and unshielded TeCd showed performance ranging from 30 to 70%. In general, the uncertainties obtained had values below 1.5%. In this work a protocol for

Mobile technology in radiology resident education.

Science.gov (United States)

Korbage, Aiham C; Bedi, Harprit S

2012-06-01

The authors hypothesized that ownership of a mobile electronic device would result in more time spent learning radiology. Current trends in radiology residents' studying habits, their use of electronic and printed radiology learning resources, and how much of the funds allotted to them are being used toward printed vs electronic education tools were assessed in this study. A survey study was conducted among radiology residents across the United States from June 13 to July 5, 2011. Program directors listed in the Association of Program Directors in Radiology e-mail list server received an e-mail asking for residents to participate in an online survey. The questionnaire consisted of 12 questions and assessed the type of institution, the levels of training of the respondents, and book funds allocated to residents. It also assessed the residents' study habits, access to portable devices, and use of printed and electronic radiology resources. Radiology residents are adopters of new technologies, with 74% owning smart phones and 37% owning tablet devices. Respondents spend nearly an equal amount of time learning radiology from printed textbooks as they do from electronic resources. Eighty-one percent of respondents believe that they would spend more time learning radiology if provided with tablet devices. There is considerable use of online and electronic resources and mobile devices among the current generation of radiology residents. Benefits, such as more study time, may be obtained by radiology programs that incorporate tablet devices into the education of their residents. Copyright © 2012 American College of Radiology. Published by Elsevier Inc. All rights reserved.

Actively convected liquid metal divertor

International Nuclear Information System (INIS)

Shimada, Michiya; Hirooka, Yoshi

2014-01-01

The use of actively convected liquid metals with j × B force is proposed to facilitate heat handling by the divertor, a challenging issue associated with magnetic fusion experiments such as ITER. This issue will be aggravated even more for DEMO and power reactors because the divertor heat load will be significantly higher and yet the use of copper would not be allowed as the heat sink material. Instead, reduced activation ferritic/martensitic steel alloys with heat conductivities substantially lower than that of copper, will be used as the structural materials. The present proposal is to fill the lower part of the vacuum vessel with liquid metals with relatively low melting points and low chemical activities including Ga and Sn. The divertor modules, equipped with electrodes and cooling tubes, are immersed in the liquid metal. The electrode, placed in the middle of the liquid metal, can be biased positively or negatively with respect to the module. The j × B force due to the current between the electrode and the module provides a rotating motion for the liquid metal around the electrodes. The rise in liquid temperature at the separatrix hit point can be maintained at acceptable levels from the operation point of view. As the rotation speed increases, the current in the liquid metal is expected to decrease due to the v × B electromotive force. This rotating motion in the poloidal plane will reduce the divertor heat load significantly. Another important benefit of the convected liquid metal divertor is the fast recovery from unmitigated disruptions. Also, the liquid metal divertor concept eliminates the erosion problem. (letter)

Method of processing liquid waste containing fission product

International Nuclear Information System (INIS)

Funabashi, Kiyomi; Kawamura, Fumio; Matsuda, Masami; Komori, Itaru; Miura, Eiichi.

1988-01-01

Purpose: To prepare solidification products of low surface dose by removing cesium which is main radioactive nuclides from re-processing plants. Method: Liquid wastes containing a great amount of fission products are generated accompanying the reprocessing for spent nuclear fuels. After pH adjustment, the liquid wastes are sent to a concentrator to concentrate the dissolved ingredients. The concentrated liquid wastes are pumped to an adsorption tower in which radioactive cesium contributing much to the surface dose is removed. Then, the liquid wastes are sent by way of a surge tank to a mixing tank, in which they are mixed under stirring with solidifying agents such as cements. Then, the mixture is filled in a drum-can and solidified. According to this invention, since radioactive cesium is removed before solidification, it is possible to prepare solidification products at low surface dose and facilitate the handling of the solidification products. (Horiuchi, T.)

Comparison of the distribution of non-radiological and radiological fatal risk in Ontario industries (addendum)

International Nuclear Information System (INIS)

Davis, C.K.; Forbes, W.F.; Hayward, L.M.

1986-09-01

Occupational limits for exposure to ionizing radiation, in force in Canada, are based on recommendations of international bodies, particularly the International Commission on Radiological Protection (ICRP). To determine whether the ICRP assertions concerning the similarity of the distributions of occupational risk at the higher risk levels (from non-radiation and from radiation work) to Canada a study of the high end of the distributions of non-radiological risk of occupational fatalities in the province of Ontario was performed. For the present study total doses from exposure to sources of ionizing radiation for Ontario workers were converted to relative risk rates to allow direct comparison with the non-radiological results. In addition, absolute values for the radiological risk rates (RRR) were derived. The radiological risk estimates are based on workers who work both from nuclear reactions and from X-rays. The conclusion is made that the radiological and non-radiological risk rate (NRRR) distributions are similar in shape, but the RRR are approximately 1 to 27 percent of the NRRR, depending on the industry concerned

Conference: ActiWiz – Optimizing material selection at CERN's accelerators from the radiological point of view

CERN Multimedia

2012-01-01

by Dr. Helmut Vincke (CERN), Chris Theis (CERN). Tuesday, October 30, 2012 from 15:00 to 16:30 at CERN ( 864-1-D02 - BE Auditorium Prévessin ) Description: The operation of a high-energy accelerator inevitably triggers the activation of equipment, which poses a safety hazard. Consequently access and handling constraints have to be imposed to ensure optimized working conditions. One of the key parameters determining the level of radioactivity is the material composition. Considering the radiological impact in addition to the engineering requirements during the selection of material clearly results in a safety benefit as well as a more efficient accelerator operation due to less stringent access and handling constraints. Another aspect is the minimization of future radioactive waste, which constitutes an important part of CERN’s commitment to limit its environmental impact by applying best practices. The ActiWiz software developed at CERN provides an easy to use method to optimize the m...

Radiological assessment and optimization

International Nuclear Information System (INIS)

Zeevaert, T.; Sohier, A.

1998-01-01

The objectives of SCK-CEN's research in the field of radiological assessment and optimization are (1) to implement ALARA principles in activities with radiological consequences; (2) to develop methodologies for radiological optimization in decision-aiding; (3) to improve methods to assess in real time the radiological hazards in the environment in case of an accident; (4) to develop methods and programmes to assist decision-makers during a nuclear emergency; (5) to support the policy of radioactive waste management authorities in the field of radiation protection; (6) to investigate computer codes in the area of multi criteria analysis; (7) to organise courses on off-site emergency response to nuclear accidents. Main achievements in these areas for 1997 are summarised

Assessment of management alternatives for LWR wastes. Volume 5. Assessment of the radiological impact to the public resulting from discharges of radioactive effluents

International Nuclear Information System (INIS)

Centner, B.

1993-01-01

This report deals with the assessment of the radiological impact to the public resulting from discharges of radioactive effluents (liquid and gaseous) in connection with the implementation of the Belgian scenario for the management of PWR waste. Both individual and collective doses have been estimated for a critical group of the population living around the nuclear power plants concerned. This study is part of an overall theoretical exercise aimed at evaluating a selection of management wastes for LWR waste based on economical and radiological criteria

Radiology. 3. rev. and enl. ed.

International Nuclear Information System (INIS)

Reiser, Maximilian; Kuhn, Fritz-Peter; Debus, Juergen

2011-01-01

The text book on radiology covers the following issues: Part A: General radiology: Fundamental physics: radiation biology; radiation protection fundamentals: radiologic methods; radiotherapy; nuclear medicine. Part B: Special radiology: Thorax; heart; urogenital tract and retroperitoneum; vascular system and interventional radiology; esophagus, stomach, small and large intestines; liver, biliary system, pancreas and spleen; mammary glands; central nervous system; spinal cord and spinal canal; basis of the skull, facial bones and eye socket; neck; pediatric imaging diagnostics.

Radiological Worker Training: Radiological Worker 1 lesson plans

International Nuclear Information System (INIS)

1992-10-01

Upon completion of this training course, the participant will have the knowledge to work safely in areas controlled for radiological purposes using proper radiological practices. Upon completion of this unit the participant will be able to identify the fundamentals of radiation, radioactive material and radioactive contamination. The participant will be able to select the correct response from a group of responses which verifies his/her ability to: Define ionizing radiation, radioactive material and radioactive contamination and identify the units used to measure radiation and radioactivity

Federal support of radiological research

International Nuclear Information System (INIS)

Hendee, W.R.

1981-01-01

Pervading the plans and objective outlined herein for continued and enhanced federal support of research in radiology is a challenge of unparalleled magnitude, for the economic foundation on which this support is based has rarely been more precarious. The new administration in Washington may well be the most fiscally constrained in half a century, and its stated interest in reducing federal expenditures could have disastrous consequences for the scientific research effort in this country, including that in radiology and the radiological sciences. The circumvention of these consequences may well require the dedicated effort of the entire scientific community over the next few months and years, including that part representing radiology and the radiological sciences

Ergonomics and patient handling.

Science.gov (United States)

McCoskey, Kelsey L

2007-11-01

This study aimed to describe patient-handling demands in inpatient units during a 24-hour period at a military health care facility. A 1-day total population survey described the diverse nature and impact of patient-handling tasks relative to a variety of nursing care units, patient characteristics, and transfer equipment. Productivity baselines were established based on patient dependency, physical exertion, type of transfer, and time spent performing the transfer. Descriptions of the physiological effect of transfers on staff based on patient, transfer, and staff characteristics were developed. Nursing staff response to surveys demonstrated how patient-handling demands are impacted by the staff's physical exertion and level of patient dependency. The findings of this study describe the types of transfers occurring in these inpatient units and the physical exertion and time requirements for these transfers. This description may guide selection of the most appropriate and cost-effective patient-handling equipment required for specific units and patients.

Equipment for the handling of thorium materials

International Nuclear Information System (INIS)

Heisler, S.W. Jr.; Mihalovich, G.S.

1988-01-01

The Feed Materials Production Center (FMPC) is the United States Department of Energy's storage facility for thorium. FMPC thorium handling and overpacking projects ensure the continued safe handling and storage of the thorium inventory until final disposition of the materials is determined and implemented. The handling and overpacking of the thorium materials requires the design of a system that utilizes remote handling and overpacking equipment not currently utilized at the FMPC in the handling of uranium materials. The use of remote equipment significantly reduces radiation exposure to personnel during the handling and overpacking efforts. The design system combines existing technologies from the nuclear industry, the materials processing and handling industry and the mining industry. The designed system consists of a modified fork lift truck for the transport of thorium containers, automated equipment for material identification and inventory control, and remote handling and overpacking equipment for material identification and inventory control, and remote handling and overpacking equipment for repackaging of the thorium materials

Radiological release analysis for the EFR project

International Nuclear Information System (INIS)

Carluec, B.; Dechelette, S.; Balard, F.

1996-01-01

Tile safety approach of the European Fast Reactor project (EFR) requires to deal with certain hypothetical CDA and therefore to enhance the containment structure in order to mitigate the consequences. The analyses are performed in order to design a containment taking advantages of die inherent characteristics of the liquid metal fast reactor. Adequate computer codes describing the sequences which follow the core disruptive accident, are used. One of the main tool is the computer code CONTAIN-LMR. The goal of these analyses is to identify the most sensitive phenomena such as the overpressure due to sodium fire, to assess the involvement of some design parameters such as the leaktightness of the structures, the arrangement of the ventilation system- the effects of the implementation of filters or a retention chamber. The results of the calculations allow to propose a robust containment for EFR, and to verify that the radiological releases in the environment can be limited. The paper presents the safety approach of EFR adopted with regard to the accidents leading to a radiological source term, and the main design options retained for the containment of EFR. Then, the methods used to describe the phenomena and some representative calculations, will be presented. The main useful information and knowledge which derive from these studies for the designers conclude the paper. (author)

21 CFR 892.1980 - Radiologic table.

Science.gov (United States)

2010-04-01

... 21 Food and Drugs 8 2010-04-01 2010-04-01 false Radiologic table. 892.1980 Section 892.1980 Food and Drugs FOOD AND DRUG ADMINISTRATION, DEPARTMENT OF HEALTH AND HUMAN SERVICES (CONTINUED) MEDICAL DEVICES RADIOLOGY DEVICES Diagnostic Devices § 892.1980 Radiologic table. (a) Identification. A radiologic...

Application of Fuzzy Theory to Radiological Emergency Preparedness

International Nuclear Information System (INIS)

Han, Moon Hee; Jeong, Hyo Joon; Kim, Eun Han; Suh, Kyung Suk; Hwang, Won Tae

2005-01-01

Emergency preparedness for nuclear facility is considered as an important part for public health and safety. In an emergency, it is not easy to get the information which is needed for the operation of an emergency system. Even though the lack of the information, decision-maker should make an early decision for the public. And the real situation is often not crisp and deterministic. The concept of fuzzy set provides the mathematical formulations which can characterize the uncertain variables in the models related to radiological emergency preparedness. And it provides a method which can describe the characteristics of uncertain variables represented by the fuzzy membership functions, and the effects of distribution can be handled with the fuzzy relation and the fuzzy reasoning. By the application of linguistic variables and fuzzy algorithms, it is possible to provide an approximate and effective tool to describe the system which is too complex or ill defined to use precise mathematical analysis

RADRELAY RADIOLOGICAL DATA LINK DEVICE

International Nuclear Information System (INIS)

Harpring, L.; Frank Heckendorn, F.

2007-01-01

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

How to Handle Abuse

Science.gov (United States)

... Handle Abuse KidsHealth / For Kids / How to Handle Abuse What's in this article? Tell Right Away How Do You Know Something Is Abuse? ... babysitter, teacher, coach, or a bigger kid. Child abuse can happen anywhere — at ... building. Tell Right Away A kid who is being seriously hurt ...

Waste Handling Building Conceptual Study

International Nuclear Information System (INIS)

G.W. Rowe

2000-01-01

The objective of the ''Waste Handling Building Conceptual Study'' is to develop proposed design requirements for the repository Waste Handling System in sufficient detail to allow the surface facility design to proceed to the License Application effort if the proposed requirements are approved by DOE. Proposed requirements were developed to further refine waste handling facility performance characteristics and design constraints with an emphasis on supporting modular construction, minimizing fuel inventory, and optimizing facility maintainability and dry handling operations. To meet this objective, this study attempts to provide an alternative design to the Site Recommendation design that is flexible, simple, reliable, and can be constructed in phases. The design concept will be input to the ''Modular Design/Construction and Operation Options Report'', which will address the overall program objectives and direction, including options and issues associated with transportation, the subsurface facility, and Total System Life Cycle Cost. This study (herein) is limited to the Waste Handling System and associated fuel staging system

Practices of Handling

DEFF Research Database (Denmark)

Ræbild, Ulla

to touch, pick up, carry, or feel with the hands. Figuratively it is to manage, deal with, direct, train, or control. Additionally, as a noun, a handle is something by which we grasp or open up something. Lastly, handle also has a Nordic root, here meaning to trade, bargain or deal. Together all four...... meanings seem to merge in the fashion design process, thus opening up for an embodied engagement with matter that entails direction giving, organizational management and negotiation. By seeing processes of handling as a key fashion methodological practice, it is possible to divert the discourse away from...... introduces four ways whereby fashion designers apply their own bodies as tools for design; a) re-activating past garment-design experiences, b) testing present garment-design experiences c) probing for new garment-design experiences and d) design of future garment experiences by body proxy. The paper...

Radiological hazards

International Nuclear Information System (INIS)

Hamilton, M.

1984-01-01

The work of the (United Kingdom) National Radiological Protection Board is discussed. The following topics are mentioned: relative contributions to genetically significant doses of radiation from various sources; radon gas in non-coal mines and in dwelling houses; effects of radiation accidents; radioactive waste disposal; radiological protection of the patient in medicine; microwaves, infrared radiation and cataracts; guidance notes for use with forthcoming Ionising Radiations Regulations; training courses; personal dosimetry service; work related to European Communities. (U.K.)

Health surveillance of radiological work

International Nuclear Information System (INIS)

Pauw, H.; Vliet, J.V.D.; Zuidema, H.

1988-01-01

Shielding x-ray devices and issuing film badges to radiological workers in 1936 can be considered the start of radiological protection in the Philips enterprises in the Netherlands. Shielding and equipment were constantly improved based upon the dosimetry results of the filmbadges. The problem of radioactive waste led to the foundation of a central Philips committee for radiological protection in 1956, which in 1960 also issued an internal license system in order to regulate the proper precautions to be taken : workplace design and layout, technological provisions and working procedures. An evaluation of all radiological work in 1971 learnt that a stricter health surveillance program was needed to follow up the precautions issued by the license. On one hand a health surveillance program was established and on the other hand all types of radiological work were classified. In this way an obligatory and optimal health surveillance program was issued for each type of radiological work

Radiological safety assessment of Thoron inhalation hazards during DDU handling at UMP, Trombay

International Nuclear Information System (INIS)

Shailesh, M.; Belhe, M.S.; Malti; Narayani, K.; Satpati, S.K.

2012-01-01

Uranium Extraction Division, Bhabha Atomic Research Centre, Mumbai has been producing nuclear grade uranium metal from Ammonium di-uranate received from IRE to meet the fuel requirement of research reactors of Bhabha Atomic Research Centre at Uranium Metal Plant (UMP) in Trombay. In UMP, uranium oxide powder (U 3 O 8 and UO 3 ) is first reduced to uranium dioxide in reduction reactor and is converted to uranium tetra fluoride in hydro fluorination reactor. After removing moisture and acid vapour in expulsion area, reduction of uranium tetrafluoride is carried out with magnesium in magnesio-thermic reduction (MTR) reactor, pure uranium metal ingot with magnesium fluoride slag is produced. Finally natural uranium ingot is separated from slag in ingot discharging area. However deeply depleted uranium (DDU) metal was produced from uranium oxide (reprocessed uranium) received from PREFRE, Tarapur, as a special campaign. External radiation hazards are not dominant during the processing of natural uranium in uranium metal Plant. However it was observed that during processing of DDU metal, external and internal hazards are significant because of daughter products of thoron. Inhalation dose due to thoron was found less during charging of UO 3 powder operation than ingot discharge operation because of pneumatic powder transport system used for charging operation. It is estimated that after introduction of new blower system in different powder handling operation areas, the potential effective inhalation dose due to thoron inhalation may get reduced by 60% - 80%

Membrane treatment of liquid wastes from radiological decontamination operations.

Science.gov (United States)

Svittsov, A A; Khubetsov, S B; Volchek, K

2011-01-01

The paper focuses on the evaluation of membrane filtration for the treatment of liquid radioactive streams generated in area decontamination operations. In this work, semi-permeable membranes were demonstrated to be effective reducing the volume of wastewater containing cesium and cobalt by two orders of a magnitude. The efficiency of membrane separation was enhanced by employing additives that enlarged the size of target radionuclide species and improved their rejection by the membranes. This was achieved by chelation with synthetic water-soluble polymers and by adsorption on micro particles of adsorbent coupled with micelle formation. The effect of wastewater composition and that of the radionuclide-binding additives on the volume reduction was investigated. Membrane treatment is expected to help simplify further processing and decrease disposal costs.

SRV-automatic handling device

International Nuclear Information System (INIS)

Yamada, Koji

1987-01-01

Automatic handling device for the steam relief valves (SRV's) is developed in order to achieve a decrease in exposure of workers, increase in availability factor, improvement in reliability, improvement in safety of operation, and labor saving. A survey is made during a periodical inspection to examine the actual SVR handling operation. An SRV automatic handling device consists of four components: conveyor, armed conveyor, lifting machine, and control/monitoring system. The conveyor is so designed that the existing I-rail installed in the containment vessel can be used without any modification. This is employed for conveying an SRV along the rail. The armed conveyor, designed for a box rail, is used for an SRV installed away from the rail. By using the lifting machine, an SRV installed away from the I-rail is brought to a spot just below the rail so that the SRV can be transferred by the conveyor. The control/monitoring system consists of a control computer, operation panel, TV monitor and annunciator. The SRV handling device is operated by remote control from a control room. A trial equipment is constructed and performance/function testing is carried out using actual SRV's. As a result, is it shown that the SRV handling device requires only two operators to serve satisfactorily. The required time for removal and replacement of one SRV is about 10 minutes. (Nogami, K.)

History of the radiological protection in Mexico

International Nuclear Information System (INIS)

Ortiz M, J. R.

2008-12-01

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

An overview of dental radiology: a primer on dental radiology

International Nuclear Information System (INIS)

Manny, E.F.; Carlson, K.C.; McClean, P.M.; Rachlin, J.A.; Segal, P.

1980-01-01

To provide medical and scientific background on certain selected technologies generally considered to be of particular significance, the National Center for Health Care Technology (NCHCT) has commissioned a series of overview papers. This is one of several projects entered into jointly by the Bureau of Radiological Health (BRH) and NCHCT relating to the use of radiation for health care. Dental radiation protection has been a long-time interest of BRH. Both past and on-going efforts to minimize population radiation exposure from electronic products have included specific action programs directed at minimizing unnecessary radiation exposure to the population from dental radiology. Current efforts in quality assurance and referral criteria are two aspects of NCHCT's own assessment of this technology which are described within the larger picture presented in this overview. The issues considered in this document go beyond the radiation exposure aspects of dental x-ray procedures. To be responsive to the informational needs of NCHCT, the assessment includes various other factors that influence the practice of dental radiology. It is hoped this analysis will serve as the basis for planning and conducting future programs to improve the practice of dental radiology

Grain Handling and Storage.

Science.gov (United States)

Harris, Troy G.; Minor, John

This text for a secondary- or postecondary-level course in grain handling and storage contains ten chapters. Chapter titles are (1) Introduction to Grain Handling and Storage, (2) Elevator Safety, (3) Grain Grading and Seed Identification, (4) Moisture Control, (5) Insect and Rodent Control, (6) Grain Inventory Control, (7) Elevator Maintenance,…

Radiology's value chain.

Science.gov (United States)

Enzmann, Dieter R

2012-04-01

A diagnostic radiology value chain is constructed to define its main components, all of which are vulnerable to change, because digitization has caused disaggregation of the chain. Some components afford opportunities to improve productivity, some add value, while some face outsourcing to lower labor cost and to information technology substitutes, raising commoditization risks. Digital image information, because it can be competitive at smaller economies of scale, allows faster, differential rates of technological innovation of components, initiating a centralization-to-decentralization technology trend. Digitization, having triggered disaggregation of radiology's professional service model, may soon usher in an information business model. This means moving from a mind-set of "reading images" to an orientation of creating and organizing information for greater accuracy, faster speed, and lower cost in medical decision making. Information businesses view value chain investments differently than do small professional services. In the former model, producing a better business product will extend image interpretation beyond a radiologist's personal fund of knowledge to encompass expanding external imaging databases. A follow-on expansion with integration of image and molecular information into a report will offer new value in medical decision making. Improved interpretation plus new integration will enrich and diversify radiology's key service products, the report and consultation. A more robust, information-rich report derived from a "systems" and "computational" radiology approach will be facilitated by a transition from a professional service to an information business. Under health care reform, radiology will transition its emphasis from volume to greater value. Radiology's future brightens with the adoption of a philosophy of offering information rather than "reads" for decision making. Staunchly defending the status quo via turf wars is unlikely to constitute a

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)

Gout. Radiological aspects

International Nuclear Information System (INIS)

Restrepo Suarez, Jose Felix; Pena Cortes, Mario; Rondon Herrera, Federico; Iglesias Gamarra, Antonio; Calvo Paramo, Enrique

2000-01-01

In this paper we reviewed the clinical and radiological aspects of gout, showing the most frequent radiological findings that can guide to the correct diagnosis of the disease. The cases that we presented here have been analyzed for many years in our rheumatology service, Universidad Nacional de Colombia, Hospital San Juan de Dios, Bogota

Diagnostic and interventional radiology

Energy Technology Data Exchange (ETDEWEB)

Vogl, Thomas J. [Klinikum der Johann Wolfgang Goethe-Universitaet, Frankfurt am Main (Germany). Inst. fuer Diagnostische und Interventionelle Radiologie; Reith, Wolfgang [Universitaetsklinikum des Saarlandes, Homburg/Saar (Germany). Klinik fuer Diagnostische und Interventionelle Neuroradiologie; Rummeny, Ernst J. (ed.) [Technische Univ. Muenchen Klinikum rechts der Isar, Muenchen (Germany). Inst. fuer Radiologie

2016-08-01

This exceptional book covers all aspects of diagnostic and interventional radiology within one volume, at a level appropriate for the specialist. From the basics through diagnosis to intervention: the reader will find a complete overview of all areas of radiology. The clear, uniform structure, with chapters organized according to organ system, facilitates the rapid retrieval of information. Features include: Presentation of the normal radiological anatomy Classification of the different imaging procedures according to their diagnostic relevance Imaging diagnosis with many reference images Precise description of the interventional options The inclusion of many instructive aids will be of particular value to novices in decision making: Important take home messages and summaries of key radiological findings smooth the path through the jungle of facts Numerous tables on differential diagnosis and typical findings in the most common diseases offer a rapid overview and orientation Diagnostic flow charts outline the sequence of diagnostic evaluation All standard procedures within the field of interventional radiology are presented in a clinically relevant and readily understandable way, with an abundance of illustrations. This is a textbook, atlas, and reference in one: with more than 2500 images for comparison with the reader's own findings. This comprehensive and totally up-to-date book provides a superb overview of everything that the radiology specialist of today needs to know.

Medical radiology terminology

International Nuclear Information System (INIS)

1986-01-01

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

The radiological technologist

International Nuclear Information System (INIS)

Bundy, A.L.

1988-01-01

Radiologists rely upon the talents of the technologists with whom they work. Indeed, a good technologist will only enhance the radiologist's performance. Radiological technologists no longer solely take radiographs, but are involved in many more detailed areas of imaging, such as computered tomography, magnetic resonance imaging, nuclear radiology, ultrasound, angiography, and special procedures. They are also required to make decisions that affect the radiological examination. Besides the degree in radiological technology (RT), advanced degrees in nuclear medicine technology (NMT) and diagnostic medical sonography (RDMS) are attainable. The liability of the technologist is not the same as the radiologist involved, but the liability is potentially real and governed by a subdivision of jurisprudence known as agency law. Since plaintiffs and attorneys are constantly searching for new frontiers of medical liability, it is wise for the radiologist and technologist to be aware of the legalities governing their working relationship and to behave accordingly. The legal principles that apply to this working relationship are discussed in this chapter, followed by a presentation of some relevant and interesting cases that have been litigated

Occupational radiological protection in diagnostic radiology

International Nuclear Information System (INIS)

Mota, H.C.

1983-01-01

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

Silicon surface barrier detectors used for liquid hydrogen density measurement

Science.gov (United States)

James, D. T.; Milam, J. K.; Winslett, H. B.

1968-01-01

Multichannel system employing a radioisotope radiation source, strontium-90, radiation detector, and a silicon surface barrier detector, measures the local density of liquid hydrogen at various levels in a storage tank. The instrument contains electronic equipment for collecting the density information, and a data handling system for processing this information.

Radiological Control Manual. Revision 0, January 1993

Energy Technology Data Exchange (ETDEWEB)

1993-04-01

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

TRANSPORT/HANDLING REQUESTS

CERN Multimedia

Groupe ST/HM

2002-01-01

A new EDH document entitled 'Transport/Handling Request' will be in operation as of Monday, 11th February 2002, when the corresponding icon will be accessible from the EDH desktop, together with the application instructions. This EDH form will replace the paper-format transport/handling request form for all activities involving the transport of equipment and materials. However, the paper form will still be used for all vehicle-hire requests. The introduction of the EDH transport/handling request form is accompanied by the establishment of the following time limits for the various services concerned: 24 hours for the removal of office items, 48 hours for the transport of heavy items (of up to 6 metric tons and of standard road width), 5 working days for a crane operation, extra-heavy transport operation or complete removal, 5 working days for all transport operations relating to LHC installation. ST/HM Group, Logistics Section Tel: 72672 - 72202

Integrative teaching in Radiology. A survey

International Nuclear Information System (INIS)

Dettmer, S.; Weidemann, J.; Wacker, F.; Fischer, V.

2015-01-01

To survey integrative teaching in radiology at German universities. A questionnaire about radiological education was sent electronically to all 37 chairpersons of university radiology departments in Germany. The questions included the course type, teaching methods, concept, perception, and advantages and disadvantages of integrative teaching. Statistical analysis was performed with nonparametric statistics and chi-square test. The survey was considered representative with a return rate of 68%. Integrative teaching is established at 4/5 of all departments. Integrative teaching is well accepted with an acceptance rate that is significantly higher in so-called 'Modellstudiengaengen' (model courses of study) (100%) compared to conventional courses of study (72%). The advantages of integrative teaching include linking of content (92%) and preparation for interdisciplinary work (76%). The disadvantages include high effort (75%) and time (67%) for organization. Furthermore, there is a risk that basic radiological facts and knowledge cannot be conveyed and that the visibility of radiology as an independent discipline is lost. Conventional radiological teaching has a similarly high acceptance (84%) compared to integrative courses (76%). Integrative teaching has a high acceptance among chairpersons in radiology in Germany despite the greater effort. A good interdisciplinary collaboration is essential for integrative teaching and at the same time this can be conveyed to the students. However, the visibility of radiology as a discipline and the possibility to cover basic radiological content must be ensured. Therefore, both conventional courses and integrative teaching seems reasonable, especially in cross-disciplinary subjects such as radiology.

NaK handling and removal

International Nuclear Information System (INIS)

Desreumaux, J.; Rodriguez, G.; Guigon, A.; Verdelli, J.; Thomine, G.

1997-01-01

Sodium-potassium alloy is used in specific application in French Fast Breeder Reactors as: cold traps, NaK bubbler for argon purification, valves and also in experimental irradiation devices. lt has been preferred to sodium because it is liquid from + 7 deg. C for the most common peritectic alloy. After its use, NaK is considered as a hazardous waste (nuclear or not) due to its high reactivity with air and water. The most important risk remains in handling NaK systems which have not been operated for some time. The NaK will be covered with a crust of the superoxide K02 which is a strong oxidising agent. Thermodynamically, K02 will react with most organic material or metallic dust or swarfs and can also react with additional NaK to give sufficient heat to boil part of the NaK, resulting in a sudden increase in pressure and small explosions. We describe the formation given to experimenters in our Sodium School and the CEA's experience in treating specific devices for transportation, decanting of tanks, tank opening and NaK removal. (author)

Damping of liquid sloshing by foams

Science.gov (United States)

Sauret, A.; Boulogne, F.; Cappello, J.; Dressaire, E.; Stone, H. A.

2015-02-01

When a container is set in motion, the free surface of the liquid starts to oscillate or slosh. Such effects can be observed when a glass of water is handled carelessly and the fluid sloshes or even spills over the rims of the container. However, beer does not slosh as readily as water, which suggests that foam could be used to damp sloshing. In this work, we study experimentally the effect on sloshing of a liquid foam placed on top of a liquid bath. We generate a monodisperse two-dimensional liquid foam in a rectangular container and track the motion of the foam. The influence of the foam on the sloshing dynamics is experimentally characterized: only a few layers of bubbles are sufficient to significantly damp the oscillations. We rationalize our experimental findings with a model that describes the foam contribution to the damping coefficient through viscous dissipation on the walls of the container. Then we extend our study to confined three-dimensional liquid foam and observe that the behavior of 2D and confined 3D systems are very similar. Thus, we conclude that only the bubbles close to the walls have a significant impact on the dissipation of energy. The possibility to damp liquid sloshing using foam is promising in numerous industrial applications such as the transport of liquefied gas in tankers or for propellants in rocket engines.

Flat-screen detector systems in skeletal radiology

International Nuclear Information System (INIS)

Grampp, S.; Czerny, C.; Krestan, C.; Henk, C.; Heiner, L.; Imhof, H.

2003-01-01

Implementation of flat-panel detectors and digital integration of the technique instead of the use of conventional radiographs leads to a shortening of the work process. With flat-panel technology the image production process is shortened by more than 30%. Major advantages in the implementation of integrated RIS, PACS and flat-panel detector system are increases in quality because most mistakes in picture labeling can be avoided, easier handling without the need for cassettes, and the possibility of image post-processing. The diagnostic quality of the images in the field of musculoskeletal radiology is, in comparison to conventional radiographs, at least adequate and in most cases markedly improved with a marked reduction in radiation exposure of around 30-50%. With respect to the numerous advantages of the digital techniques and especially flat-panel technology there is a very high likelihood that conventional radiographs will be substituted in the coming years, even though the cost of the new technology is currently significantly higher compared to conventional systems. (orig.) [de

Quality control in dental diagnostic radiology : anomalous in the use of radiological equipment

International Nuclear Information System (INIS)

Alcaraz, M.; Martinez-Beneyto, Y.; Jodar, S.; Velasco, E.; Garcia-Vera, M. C.

2004-01-01

7,176 official quality control reports on dental diagnostic radiology were studied, relating to dental clinics located in 37 Spanish provinces covering 16 different autonomous Regions. The reports were issued as a result of the entry into force of Royal Decree 2071/1995 on quality control in General Diagnostic Radiology facilities, this Royal Decree was replaced by R. D. 1976/1999. The reports were writen by the UTPR (Technical Unit of Radiological Protection) Agsigma S. A. L., a company approved by the Nuclear Safety Council, and they correspond with the official reports issued during 1996-2001. This meants that a 5-year period has been monitored in order to observe the impacts of the establlishment of this legislation on quality control in intraoral dental diagnostic radiology facilities. The results show that 72.79% of the reports checked in 2001 would comply with the European Union's official recommendation (70 kVp, 8 mA> 1.5 mm of Al and 20 cm collimator length). Significant alterations have detected in a third (30.59%) of the radiological equipment. (Author) 36 refs

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

International Nuclear Information System (INIS)

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

2017-01-01

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

Laenderyggens degeneration og radiologi

DEFF Research Database (Denmark)

Jacobsen, Steffen; Gosvig, Kasper Kjaerulf; Sonne-Holm, Stig

2006-01-01

Low back pain (LBP) is one of the most common conditions, and at the same time one of the most complex nosological entities. The lifetime prevalence is approximately 80%, and radiological features of lumbar degeneration are almost universal in adults. The individual risk factors for LBP and signi......Low back pain (LBP) is one of the most common conditions, and at the same time one of the most complex nosological entities. The lifetime prevalence is approximately 80%, and radiological features of lumbar degeneration are almost universal in adults. The individual risk factors for LBP...... and significant relationships between radiological findings and subjective symptoms have both been notoriously difficult to identify. The lack of consensus on clinical criteria and radiological definitions has hampered the undertaking of properly executed epidemiological studies. The natural history of LBP...

Recent trend of diagnostic radiology

International Nuclear Information System (INIS)

Kim, S.Y.; Kim, H.K.

1979-01-01

Present status and recent trend of diagnostic radiology have been reviewed. The interrelationships and Characteristics of various fields of radiology such as computed tomography, X-ray radiology, and nuclear medicine were discussed. The mevit of computed tomography and the promising use of short lived, accelerator produced radionuclides, and radiotherapy in nuclear medicine were emphasized. (author)

Role of radiology in occupational medicine

International Nuclear Information System (INIS)

Vehmas, T.

2004-01-01

This review discusses the contribution of radiology to occupational medicine as well as work-related problems in radiology dept.s. Research issues are emphasized. Radiology has been used especially when diagnosing occupational respiratory and locomotive system problems and solvent-induced encephalo- and hepatopathy. The aim of research in these areas is usually to characterize occupational diseases and to identify physico-chemical hazards in the work place by comparing between groups of workers and non-exposed controls. Radiological imaging allows an objective characterization of the disease, and it may clarify the pathogenesis of the process and provide a useful epidemiological tool. Advanced statistical methods are often needed to adjust analyses for confounding variables. As the diagnostic requirements are increasing, more sensitive and sophisticated radiological methods, such as high-resolution computed tomography, magnetic resonance imaging and magnetic resonance spectroscopy, may be required for the early recognition of occupational health risks. This necessitates good cooperation between occupational health units and well-equipped imaging dept.s. Considering occupational problems in radiology departments, the increasing use of digital radiology requires ergonomic measures to control and prevent locomotive problems caused by work with computers. Radiation protection measures are still worth concern, especially in interventional radiology

Military radiology during the first world conflict

International Nuclear Information System (INIS)

Le Vot, J.

2016-01-01

Published at the occasion of the centenary of the First World War, this article proposes an historical overview of the emergence and development of military medical radiology during this conflict. The author first describes the situation of radiology in the different armies and countries on the eve of the war as this application of radiology is relatively recent (it is based on Roentgen's discovery in 1895). He indicates the first steps of emergence of radiology department in military hospitals, the interest of military physicians in radiology and the availability of mobile equipment which had been actually presented at the parade on the 14 July 1914. The author then highlights some important personalities who have been important actors of the development, application and use of radiology and of military radiology during the war. He proposes an overview of radiological equipment in 1914, of the variety of vehicles adapted to transport and use such equipment. He also comments how radiology professionals were trained

Cask system design guidance for robotic handling

International Nuclear Information System (INIS)

Griesmeyer, J.M.; Drotning, W.D.; Morimoto, A.K.; Bennett, P.C.

1990-10-01

Remote automated cask handling has the potential to reduce both the occupational exposure and the time required to process a nuclear waste transport cask at a handling facility. The ongoing Advanced Handling Technologies Project (AHTP) at Sandia National Laboratories is described. AHTP was initiated to explore the use of advanced robotic systems to perform cask handling operations at handling facilities for radioactive waste, and to provide guidance to cask designers regarding the impact of robotic handling on cask design. The proof-of-concept robotic systems developed in AHTP are intended to extrapolate from currently available commercial systems to the systems that will be available by the time that a repository would be open for operation. The project investigates those cask handling operations that would be performed at a nuclear waste repository facility during cask receiving and handling. The ongoing AHTP indicates that design guidance, rather than design specification, is appropriate, since the requirements for robotic handling do not place severe restrictions on cask design but rather focus on attention to detail and design for limited dexterity. The cask system design features that facilitate robotic handling operations are discussed, and results obtained from AHTP design and operation experience are summarized. The application of these design considerations is illustrated by discussion of the robot systems and their operation on cask feature mock-ups used in the AHTP project. 11 refs., 11 figs

Production management of window handles

Directory of Open Access Journals (Sweden)

Manuela Ingaldi

2014-12-01

Full Text Available In the chapter a company involved in the production of aluminum window and door handles was presented. The main customers of the company are primarily companies which produce PCV joinery and wholesalers supplying these companies. One chosen product from the research company - a single-arm pin-lift window handle - was described and its production process depicted technologically. The chapter also includes SWOT analysis conducted in the research company and the value stream of the single-arm pin-lift window handle.

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.)

A fast and simple approach for the estimation of a radiological source from localised measurements after the explosion of a radiological dispersal device

International Nuclear Information System (INIS)

Urso, L.; Kaiser, J.C.; Woda, C.; Helebrant, J.; Hulka, J.; Kuca, P.; Prouza, Z.

2014-01-01

After an explosion of a radiological dispersal device, decision-makers need to implement countermeasures as soon as possible to minimise the radiation-induced risks to the population. In this work, the authors present a tool, which can help providing information about the approximate size of source term and radioactive contamination based on a Gaussian Plume model with the use of available measurements for liquid or aerosolised radioactivity. For two-field tests, the source term and spatial distribution of deposited radioactivity are estimated. A sensitivity analysis of the dependence on deposition velocity is carried out. In case of weak winds, a diffusive process along the wind direction is retained in the model. (authors)

7 CFR 58.443 - Whey handling.

Science.gov (United States)

2010-01-01

... 7 Agriculture 3 2010-01-01 2010-01-01 false Whey handling. 58.443 Section 58.443 Agriculture... Procedures § 58.443 Whey handling. (a) Adequate sanitary facilities shall be provided for the handling of whey. If outside, necessary precautions shall be taken to minimize flies, insects and development of...

Integrative teaching in radiology - a survey.

Science.gov (United States)

Dettmer, S; Weidemann, J; Fischer, V; Wacker, F K

2015-04-01

To survey integrative teaching in radiology at German universities. A questionnaire about radiological education was sent electronically to all 37 chairpersons of university radiology departments in Germany. The questions included the course type, teaching methods, concept, perception, and advantages and disadvantages of integrative teaching. Statistical analysis was performed with nonparametric statistics and chi-square test. The survey was considered representative with a return rate of 68 %. Integrative teaching is established at 4/5 of all departments. Integrative teaching is well accepted with an acceptance rate that is significantly higher in so-called "Modellstudiengängen" [model courses of study] (100 %) compared to conventional courses of study (72 %). The advantages of integrative teaching include linking of content (92 %) and preparation for interdisciplinary work (76 %). The disadvantages include high effort (75 %) and time (67 %) for organization. Furthermore, there is a risk that basic radiological facts and knowledge cannot be conveyed and that the visibility of radiology as an independent discipline is lost. Conventional radiological teaching has a similarly high acceptance (84 %) compared to integrative courses (76 %). Integrative teaching has a high acceptance among chairpersons in radiology in Germany despite the greater effort. A good interdisciplinary collaboration is essential for integrative teaching and at the same time this can be conveyed to the students. However, the visibility of radiology as a discipline and the possibility to cover basic radiological content must be ensured. Therefore, both conventional courses and integrative teaching seems reasonable, especially in cross-disciplinary subjects such as radiology. Both integrative teaching and conventional radiological teaching are highly accepted. The advantages include the linking of multidisciplinary content and the preparation for interdisciplinary cooperation

Computers in radiology. The sedation, analgesia, and contrast media computerized simulator: a new approach to train and evaluate radiologists' responses to critical incidents

International Nuclear Information System (INIS)

Medina, L.S.; Racadio, J.M.; Schwid, H.A.

2000-01-01

Background. Awareness and preparedness to handle sedation, analgesia, and contrast-media complications are key in the daily radiology practice. Objective. The purpose is to create a computerized simulator (PC-Windows-based) that uses a graphical interface to reproduce critical incidents in pediatric and adult patients undergoing a wide spectrum of radiologic sedation, analgesia and contrast media complications. Materials and methods. The computerized simulator has a comprehensive set of physiologic and pharmacologic models that predict patient response to management of sedation, analgesia, and contrast-media complications. Photorealistic images, real-time monitors, and mouse-driven information demonstrate in a virtual-reality fashion the behavior of the patient in crisis. Results. Thirteen pediatric and adult radiology scenarios are illustrated encompassing areas such as pediatric radiology, neuroradiology, interventional radiology, and body imaging. The multiple case scenarios evaluate randomly the diagnostic and management performance of the radiologist in critical incidents such as oversedation, anaphylaxis, aspiration, airway obstruction, apnea, agitation, bronchospasm, hypotension, hypertension, cardiac arrest, bradycardia, tachycardia, and myocardial ischemia. The user must control the airway, breathing and circulation, and administer medications in a timely manner to save the simulated patient. On-line help is available in the program to suggest diagnostic and treatment steps to save the patient, and provide information about the medications. A printout of the case management can be obtained for evaluation or educational purposes. Conclusion. The interactive computerized simulator is a new approach to train and evaluate radiologists' responses to critical incidents encountered during radiologic sedation, analgesia, and contrast-media administration. (orig.)

Radiological studies on Egyptian mummies

International Nuclear Information System (INIS)

Pahl, W.M.

1982-01-01

The goal of this work as part of a mummy study project is to obtain the maximum amount of information through radiological methods with the minimum destruction of the object. For this proven radiological methods were used as well as conventional radiological methods which had not yet been used with mummy research and modern radiological methods using an electronic basis relative to their importance for the study of medical archaeological materials. It is shown that the knowledge which is gained from the use of a combination of classical radiological methods and computed tomography cannot be enhanced by an autopsy of the study objects. Since because of this the objects can be kept in their original condition, a later checking of the results is guaranteed with the possibility of clearing up remaining open questions by means of further developed methods. (orig.) [de

How to Read Your Radiology Report

Science.gov (United States)

... Site Index A-Z How to Read Your Radiology Report Imaging studies such as magnetic resonance imaging ( ... radiology report. top of page Sections of the Radiology Report Type of exam The type of exam ...

Radiology in the 21st century

International Nuclear Information System (INIS)

Carson, P.L.; Seltzer, S.E.; Gore, J.C.; Heiiman, R.S.; Abrams, H.L.; Davis, K.A.; Henkelman, M.R.

1987-01-01

On the leading edge in ''high-tech'' medicine, radiology is experiencing several revolutions simultaneously that promise an exciting future. New imaging methods and digital technologies not only offer novel ways to view tissues but also provide opportunities for quantitative evaluation of function and even permit determination of metabolic status. New approaches to technology assessment are being explored that alter the ways in which equipment and procedures are introduced into clinical medicine. With the plethora of radiology services available, the radiologist must serve as a consultant in the triage of patients in radiology and the dissemination of information from radiology. For similar reasons, training in diagnostic radiology may eventually accommodate to the concept of specialization along organ-system lines. Without question, radiology is destined for an exciting period as it moves into the 21st century

A multi-slice sliding cell technique for diffusion measurements in liquid metals

Science.gov (United States)

Zhong, Langxiang; Hu, Jinliang; Geng, Yongliang; Zhu, Chunao; Zhang, Bo

2017-09-01

The long capillary and shear-cell techniques are traditionally used for diffusion measurements in liquid metals. Inspired by the idea of the shear-cell method, we have built a multi-slice sliding cell device for inter-diffusion measurements in liquid metals. The device is designed based on a linear sliding movement rather than a rotational shearing as used in the traditional shear-cell method. Compared with the normal shear-cell method, the present device is a more compact setup thus easier to handle. Also, it is expected to be easier to monitor with X-rays or neutrons if used in in situ experiments. A series of benchmark time-dependent diffusion experiments in Al-Cu melts carried out with the present technique reveal that accurate diffusion constants can be achieved only after a sufficient time. For short annealing times, the initial shearing process causing convective flow dominates the measurement and leads to an increase of the measured diffusion coefficient by a factor three. The diffusion data obtained for Al-Cu liquids are consistent with the most accurate data measured by the in situ X-ray radiography method under well controlled conditions of no temperature gradient or other perturbation. High accuracy and easy handling as well as superior adaptability make the present technique suitable for diffusion studies in liquid metals.

Development of commercial robots for radwaste handling

International Nuclear Information System (INIS)

Colborn, K.A.

1988-01-01

The cost and dose burden associated with low level radwaste handling activities is a matter of increasing concern to the commercial nuclear power industry. This concern is evidenced by the fact that many utilities have begun to revaluate waste generation, handling, and disposal activities at their plants in an effort to improve their overall radwaste handling operations. This paper reports on the project Robots for Radwaste Handling, to identify the potential of robots to improve radwaste handling operations. The project has focussed on the potential of remote or automated technology to improve well defined, recognizable radwaste operations. The project focussed on repetitive, low skill level radwaste handling and decontamination tasks which involve significant radiation exposure

Interventional Radiology in Paediatrics.

Science.gov (United States)

Chippington, Samantha J; Goodwin, Susie J

2015-01-01

As in adult practice, there is a growing role for paediatric interventional radiology expertise in the management of paediatric pathologies. This review is targeted for clinicians who may refer their patients to paediatric interventional radiology services, or who are responsible for patients who are undergoing paediatric interventional radiology procedures. The article includes a brief overview of the indications for intervention, techniques involved and the commonest complications. Although some of the procedures described are most commonly performed in a tertiary paediatric centre, many are performed in most Children's hospitals.

Lessons learned from radiological accidents at medical exposures in radiotherapy; Lições aprendidas com acidentes radiológicos nas exposições médicas em radioterapia

Energy Technology Data Exchange (ETDEWEB)

Fagundes, J.S.; Ferreira, A.F. [Faculdade Casa Branca, SP (Brazil); Lima, C.M.A. [MAXIM Cursos, Rio de Janeiro, RJ (Brazil); Silva, F.C.A. da, E-mail: franciscodasilva13uk@gmail.com [Instituto de Radioproteção e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

2017-07-01

An exposure is considered accidental in radiotherapy when there is a substantial deviation in the prescription of treatment. In this work, an analysis of published radiological accidents, both in Brazil and internationally, was performed during medical exposures in radiotherapy treatments, removing the main lessons learned. Of the research carried out, we highlight Brazil with four radiological accidents and one death in the period between 2011 and 2014; the United States of America with 169 accidents with two deaths from 2000 to 2010 and France from 2001 to 2014 had 569 deaths without patients. Lessons learned have been described, for example, that maintenance personnel training should specify limitations or restrictions on the handling or adjustment of critical parts on the accelerator. It is recommended to apply the 10 main lessons learned due to radiological accidents during medical exposures in radiotherapy treatments to avoid future events.

Radiologic technology educators and andragogy.

Science.gov (United States)

Galbraith, M W; Simon-Galbraith, J A

1984-01-01

Radiologic technology educators are in constant contact with adult learners. However, the theoretical framework that radiologic educators use to guide their instruction may not be appropriate for adults. This article examines the assumptions of the standard instructional theory and the most modern approach to adult education-- andragogy . It also shows how these assumptions affect the adult learner in a radiologic education setting.

Postoperative radiology

International Nuclear Information System (INIS)

Burhenne, H.J.

1989-01-01

This paper reports on the importance of postoperative radiology. Most surgical procedures on the alimentary tract are successful, but postoperative complications remain a common occurrence. The radiologist must be familiar with a large variety of possible surgical complications, because it is this specialty that is most commonly called on to render a definitive diagnosis. The decision for reoperation, for instance, is usually based on results from radiologic imaging techniques. These now include ultrasonography, CT scanning, needle biopsy, and interventional techniques in addition to contrast studies and nuclear medicine investigation

Preoperational checkout of the remote-handled transuranic waste handling at the Waste Isolation Pilot Plant

International Nuclear Information System (INIS)

1987-09-01

This plan describes the preoperational checkout for handling Remote-Handled Transuranic (RH-TRU) Wastes from their receipt at the Waste Isolation Pilot Plant (WIPP) to their emplacement underground. This plan identifies the handling operations to be performed, personnel groups responsible for executing these operations, and required equipment items. In addition, this plan describes the quality assurance that will be exercised throughout the checkout, and finally, it establishes criteria by which to measure the success of the checkout. 7 refs., 5 figs

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

Report of the radiological protection procedures adapted in the Goiania General Hospital for assistance to the victims of the radiological accident with Cesium 137

International Nuclear Information System (INIS)

1989-08-01

A caesium-137 capsule, illegal removed from a desactivated health center of the Instituto Goiano de Radioterapia, was disrupted causing a serious radiological accident. The dimensions of the accident were worsened due to some facts such as: the caesium-137 was in the chloride from, which is a very soluble compound the accident was notify to the competent authorities only several days after the capsule was removal and during this period of time some people handled the souce directly, without knowing its potential danger. This paper descibes the measures adopted in the Goiania General Hospital to restrict the exposure of workers and members of the public and to minimize the consequences of unavoidable exposures in such a way to assure that the annual dose limits were not exceeded. An efficiency evaluation of the methods adopted for the decontamination of the victims was made and its described in the report. (author) [pt

Preference Handling for Artificial Intelligence

OpenAIRE

Goldsmith, Judy; University of Kentucky; Junker, Ulrich; ILOG

2009-01-01

This article explains the benefits of preferences for AI systems and draws a picture of current AI research on preference handling. It thus provides an introduction to the topics covered by this special issue on preference handling.

Religious Serpent Handling and Community Relations.

Science.gov (United States)

Williamson, W Paul; Hood, Ralph W

2015-01-01

Christian serpent handling sects of Appalachia comprise a community that has long been mischaracterized and marginalized by the larger communities surrounding them. To explore this dynamic, this article traces the emergence of serpent handling in Appalachia and the emergence of anti-serpent-handling state laws, which eventually failed to curb the practice, as local communities gave serpent handling groups support. We present two studies to consider for improving community relations with serpent handling sects. In study 1, we present data relating the incidence of reported serpent-bite deaths with the rise of anti-serpent-handling laws and their eventual abatement, based on increasing acceptance of serpent handlers by the larger community. Study 2 presents interview data on serpent bites and death that provide explanations for these events from the cultural and religious perspective. We conclude that first-hand knowledge about serpent handlers, and other marginalized groups, helps to lessen suspicion and allows them to be seen as not much different, which are tendencies that are important for promoting inter-community harmony.

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

International Nuclear Information System (INIS)

Mueller, P.G.

2000-01-01

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

Progress of liquid metal technology and application in energy industries

International Nuclear Information System (INIS)

Miyazaki, Keiji; Kamei, Mitsuru; Nei, Hiromichi.

1990-01-01

Liquid metals are excellent energy transport media, and recently remarkable development has been observed in the technology of handling sodium and the machinery and equipment. In nuclear fusion, the development of the use of lithium as the coolant is advanced. For space technology, attention has been paid from the early stage to various liquid metals. For general industries, liquid metals have been used for high temperature heat pipes and the utilization of solar heat, and mercury vapor turbines were manufactured for trial. Besides, attention is paid anew to liquid metal MHD electric power generation. The development of the NaS batteries for electric cars and electric power storage and the interchange of liquid metal technology with the fields of iron and steel, metallurgy and so on advance. It is expected that liquid metal technology bears future advanced energy engineering while deepening the interchange with other advanced fields also in order to reactivate atomic energy technology. Liquid metals have the features of high electric and thermal conductivities, chemical activity and opaque property as metals, and fluidity and relatively high boiling point and melting point as liquids. FBRs, fusion reactors and the power sources for space use are described. (K.I.)

Radiological Protection Science and Application

International Nuclear Information System (INIS)

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

2016-01-01

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

Potential radiological exposure rates resulting from hypothetical dome failure at Tank W-10

International Nuclear Information System (INIS)

1994-07-01

The main plant area at Oak Ridge National Laboratory (ORNL) contains 12 buried Gunite tanks that were used for the storage and transfer of liquid radioactive waste. Although the tanks are no longer in use, they are known to contain some residual contaminated sludges and liquids. In the event of an accidental tank dome failure, however unlikely, the liquids, sludges, and radioactive contaminants within the tank walls themselves could create radiation fields and result in above-background exposures to workers nearby. This Technical Memorandum documents a series of calculations to estimate potential radiological exposure rates and total exposures to workers in the event of a hypothetical collapse of a Gunite tank dome. Calculations were performed specifically for tank W-10 because it contains the largest radioactivity inventory (approximately half of the total activity) of all the Gunite tanks. These calculations focus only on external, direct gamma exposures for prescribed, hypothetical exposure scenarios and do not address other possible tank failure modes or routes of exposure. The calculations were performed with established, point-kernel gamma ray modeling codes

Potential radiological exposure rates resulting from hypothetical dome failure at Tank W-10

Energy Technology Data Exchange (ETDEWEB)

1994-07-01

The main plant area at Oak Ridge National Laboratory (ORNL) contains 12 buried Gunite tanks that were used for the storage and transfer of liquid radioactive waste. Although the tanks are no longer in use, they are known to contain some residual contaminated sludges and liquids. In the event of an accidental tank dome failure, however unlikely, the liquids, sludges, and radioactive contaminants within the tank walls themselves could create radiation fields and result in above-background exposures to workers nearby. This Technical Memorandum documents a series of calculations to estimate potential radiological exposure rates and total exposures to workers in the event of a hypothetical collapse of a Gunite tank dome. Calculations were performed specifically for tank W-10 because it contains the largest radioactivity inventory (approximately half of the total activity) of all the Gunite tanks. These calculations focus only on external, direct gamma exposures for prescribed, hypothetical exposure scenarios and do not address other possible tank failure modes or routes of exposure. The calculations were performed with established, point-kernel gamma ray modeling codes.

Safe handling of tritium

International Nuclear Information System (INIS)

1991-01-01

The main objective of this publication is to provide practical guidance and recommendations on operational radiation protection aspects related to the safe handling of tritium in laboratories, industrial-scale nuclear facilities such as heavy-water reactors, tritium removal plants and fission fuel reprocessing plants, and facilities for manufacturing commercial tritium-containing devices and radiochemicals. The requirements of nuclear fusion reactors are not addressed specifically, since there is as yet no tritium handling experience with them. However, much of the material covered is expected to be relevant to them as well. Annex III briefly addresses problems in the comparatively small-scale use of tritium at universities, medical research centres and similar establishments. However, the main subject of this publication is the handling of larger quantities of tritium. Operational aspects include designing for tritium safety, safe handling practice, the selection of tritium-compatible materials and equipment, exposure assessment, monitoring, contamination control and the design and use of personal protective equipment. This publication does not address the technologies involved in tritium control and cleanup of effluents, tritium removal, or immobilization and disposal of tritium wastes, nor does it address the environmental behaviour of tritium. Refs, figs and tabs

Radiological attacks and accidents. Medical consequences

International Nuclear Information System (INIS)

Sakuta, Hidenari

2007-01-01

Probability of the occurrence of radiological attacks appears to be elevated after the terrorist attacks against the United States on September 11 in 2001. There are a lot of scenarios of radiological attack: simple radiological device, radiological disperse device (RDD or dirty bomb), attacks against nuclear reactor, improvised nuclear device, and nuclear weapons. Of these, RDD attack is the most probable scenario, because it can be easily made and can generate enormous psychological and economic damages. Radiological incidents are occurring to and fro in the world, including several cases of theft to nuclear facilities and unsuccessful terrorist attacks against them. Recently, a former Russian spy has allegedly been killed using polonium-210. In addition, serious radiological accidents have occurred in Chernobyl, Goiania, and Tokai-mura. Planning, preparation, education, and training exercise appear to be essential factors to cope with radiological attacks and accidents effectively without feeling much anxiety. Triage and psychological first aid are prerequisite to manage and provide effective medial care for mass casualties without inducing panic. (author)

How Retailers Handle Complaint Management

DEFF Research Database (Denmark)

Hansen, Torben; Wilke, Ricky; Zaichkowsky, Judy

2009-01-01

This article fills a gap in the literature by providing insight about the handling of complaint management (CM) across a large cross section of retailers in the grocery, furniture, electronic and auto sectors. Determinants of retailers’ CM handling are investigated and insight is gained as to the......This article fills a gap in the literature by providing insight about the handling of complaint management (CM) across a large cross section of retailers in the grocery, furniture, electronic and auto sectors. Determinants of retailers’ CM handling are investigated and insight is gained...... as to the links between CM and redress of consumers’ complaints. The results suggest that retailers who attach large negative consequences to consumer dissatisfaction are more likely than other retailers to develop a positive strategic view on customer complaining, but at the same time an increase in perceived...

Educational course in emergency radiology

International Nuclear Information System (INIS)

Velkova, K.; Stoeva, M.; Cvetkova, S.; Hilendarov, A.; Petrova, A.; Stefanov, P.; Simova, E.; Georgieva, V.; Sirakov, N.

2012-01-01

Emergency radiology is the part of radiology primarily focused on acute diagnosing conditions in ER patients. This advanced area of radiology improves the quality of care and treatment of patients and of the emergency medicine as a whole. The educational course in Emergency (ER) Radiology is available for medical students in their 8th and 9th semester. The main objective of the ER course is to obtain knowledge about the indications, possibilities and diagnostic value of the contemporary imaging methods in ER cases. Therapeutic methods under imaging control are also covered by the course. The curriculum of the course consists of 6 lectures and 12 practical classes. (authors)

The Radiological Research Accelerator Facility

International Nuclear Information System (INIS)

Hall, E.J.; Marino, S.A.

1990-07-01

The Radiological Research Accelerator Facility (RARAF) is based on a 4-MV Van de Graaff accelerator, which is used to generate a variety of well-characterized radiation beams for research in radiobiology, radiological physics, and radiation chemistry. It is part of the Center for Radiological Research (CRR) -- formerly the Radiological Research Laboratory (RRL) -- of Columbia University, and its operation is supported as a National Facility by the US Department of Energy (DOE). Fifteen different experiments were run during these 12 months, approximately the same as the previous two years. Brief summaries of each experiment are included. Accelerator usage is summarized and development activities are discussed. 7 refs., 4 tabs

Radiological diagnostics of muscle diseases

International Nuclear Information System (INIS)

Weber, M.A.; Essig, M.; Kauczor, H.U.

2007-01-01

Muscular diseases are a heterogeneous group of diseases with difficult differential diagnosis. This article reviews morphological and functional radiological techniques for assessment of muscular diseases. Morphological techniques can describe edema-like changes, lipomatous and atrophic changes of muscular tissue. However, these imaging signs are often not disease-specific. As a result, clinicians assign radiology a secondary role in the management of muscular diseases. Meanwhile, functional radiological techniques allow the assessment of muscle fiber architecture, skeletal muscle perfusion, myocellular sodium-homoeostasis, lipid- and energy-phosphate metabolism, etc. By detecting and spatially localizing pathophysiological phenomena, these new techniques can increase the role of radiology in muscular diseases. (orig.)

Growth of high purity semiconductor epitaxial layers by liquid phase ...

Indian Academy of Sciences (India)

Unknown

semiconductor materials in high purity form by liquid phase epitaxy (LPE) technique. Various possible sources of impurities in such ... reference to the growth of GaAs layers. The technique of growing very high purity layers ... the inner walls of the gas lines and (e) the containers for storing, handling and cleaning of the mate-.

Physics of Radiology

CERN Document Server

Johns, Harold Elford

1983-01-01

Authority, comprehensivity and a consummate manner of presentation have been hallmarks of The Physics of Radiology since it first saw publication some three decades past. This Fourth Edition adheres to that tradition but again updates the context. It thoroughly integrates ideas recently advanced and practices lately effected. Students and professionals alike will continue to view it, in essence, as the bible of radiological physics.

7 CFR 926.9 - Handle.

Science.gov (United States)

2010-01-01

... the Department of Agriculture (Continued) AGRICULTURAL MARKETING SERVICE (Marketing Agreements and Orders; Fruits, Vegetables, Nuts), DEPARTMENT OF AGRICULTURE DATA COLLECTION, REPORTING AND RECORDKEEPING REQUIREMENTS APPLICABLE TO CRANBERRIES NOT SUBJECT TO THE CRANBERRY MARKETING ORDER § 926.9 Handle. Handle...

Radiological aspects of Gaucher disease

International Nuclear Information System (INIS)

Katz, Robert; Booth, Tom; Hargunani, Rikin; Wylie, Peter; Holloway, Brian

2011-01-01

Advances in imaging and the development of commercially available enzyme therapy have significantly altered the traditional radiology of Gaucher disease. The cost of treatment and need for monitoring response to therapy have magnified the importance of imaging. There are no recent comprehensive reviews of the radiology of this relatively common lysosomal storage disease. This article describes the modern imaging, techniques and radiological manifestations of Gaucher disease. (orig.)

Radiological aspects of Gaucher disease

Energy Technology Data Exchange (ETDEWEB)

Katz, Robert; Booth, Tom; Hargunani, Rikin; Wylie, Peter; Holloway, Brian [Royal Free Hospital, Radiology Department, London (United Kingdom)

2011-12-15

Advances in imaging and the development of commercially available enzyme therapy have significantly altered the traditional radiology of Gaucher disease. The cost of treatment and need for monitoring response to therapy have magnified the importance of imaging. There are no recent comprehensive reviews of the radiology of this relatively common lysosomal storage disease. This article describes the modern imaging, techniques and radiological manifestations of Gaucher disease. (orig.)

Radiological characterisation - Know your objective

International Nuclear Information System (INIS)

Lindow, Veronica; Moeller, Jennifer

2012-01-01

When developing a programme for mapping the radiological characteristics of a facility to be decommissioned it is important to take into account the objectives of the programme. Will the results be used to plan for radiological control and selection of appropriate decontamination and dismantling techniques? Will the radiological inventory be used for dimensioning of future waste repositories? These are two examples of the applications for such studies, which could require that a radiological characterisation programme be adapted to provide the data appropriate to the intended use. The level of detail and scope needed for a radiological characterisation will also vary depending on how the data will be used. An application to free-release a facility requires a comprehensive survey and well documented analysis in order to ensure that no radioactive contamination above prescribed levels is present. A bounding calculation to determine the maximum anticipated volumes and activity of radioactive waste requires a different approach. During the past few years, older decommissioning studies for the Swedish nuclear power plants have been updated (or are in the process of being updated). The decommissioning study's main purpose is to estimate the cost for decommissioning. The cost estimation is based on material and activity inventories, which in turn is based on previous and, in some cases, updated radiological characterisations of the facilities. The radiological inventory is an important part of the study as it affects the cost of decommissioning but also the uncertainties and accuracy of the cost estimation. The presentation will discuss the challenges in specifying a radiological characterisation programme with multiple objectives, together with insights on how data delivered can be applied to yield results suitable for the intended purpose, without introducing excessive conservatism. The intent of the presentation is to define issues that can be of use in various aspects

340 waste handling complex: Deactivation project management plan

International Nuclear Information System (INIS)

Stordeur, R.T.

1998-01-01

This document provides an overview of the strategy for deactivating the 340 Waste Handling Complex within Hanford's 300 Area. The plan covers the period from the pending September 30, 1998 cessation of voluntary radioactive liquid waste (RLW) transfers to the 340 Complex, until such time that those portions of the 340 Complex that remain active beyond September 30, 1998, specifically, the Retention Process Sewer (RPS), can also be shut down and deactivated. Specific activities are detailed and divided into two phases. Phase 1 ends in 2001 after the core RLW systems have been deactivated. Phase 2 covers the subsequent interim surveillance of deactivated and stand-by components during the period of continued RPS operation, through the final transfer of the entire 340 Complex to the Environmental Restoration Contractor. One of several possible scenarios was postulated and developed as a budget and schedule planning case

Streamlining interventional radiology admissions: The role of the interventional radiology clinic and physician's assistant

International Nuclear Information System (INIS)

White, R.I. Jr.; Rizer, D.M.; Shuman, K.; White, E.J.; Adams, P.; Doyle, K.; Kinnison, M.

1987-01-01

During a 5-year period (1982-1987), 376 patients were admitted to an interventional radiology service where they were managed by the senior physician and interventional radiology fellows. Sixty-eight percent of patients were admitted for angioplasty and 32% for elective embolotherapy/diagnostic angiography. A one-half-day, twice weekly interventional radiology clinic and employment of a physician's assistant who performed preadmission history and physicals and wrote orders accounted, in part, for a decrease in hospital stay length from 3.74 days (1982-1983) to 2.41 days (1986-1987). The authors conclude that use of the clinic and the physician's assistant streamlines patient flow and the admitting process and is partially responsible for a decreased length of stay for patients admitted to an interventional radiology service

Radiology. 3. rev. and enl. ed.; Radiologie

Energy Technology Data Exchange (ETDEWEB)

Reiser, Maximilian [Klinikum der Universitaet Muenchen (Germany). Inst. fuer Klinische Radiologie; Kuhn, Fritz-Peter [Klinikum Kassel (Germany). Inst. fuer Diagnostische und Interventionelle Radiologie; Debus, Juergen [Radiologische Universitaetsklinik, Heidelberg (Germany). Abt. Radioonkologie und Strahlentherapie

2011-07-01

The text book on radiology covers the following issues: Part A: General radiology: Fundamental physics: radiation biology; radiation protection fundamentals: radiologic methods; radiotherapy; nuclear medicine. Part B: Special radiology: Thorax; heart; urogenital tract and retroperitoneum; vascular system and interventional radiology; esophagus, stomach, small and large intestines; liver, biliary system, pancreas and spleen; mammary glands; central nervous system; spinal cord and spinal canal; basis of the skull, facial bones and eye socket; neck; pediatric imaging diagnostics.

Evidence-based Practice of Radiology.

Science.gov (United States)

Lavelle, Lisa P; Dunne, Ruth M; Carroll, Anne G; Malone, Dermot E

2015-10-01

Current health care reform in the United States is producing a shift in radiology practice from the traditional volume-based role of performing and interpreting a large number of examinations to providing a more affordable and higher-quality service centered on patient outcomes, which is described as a value-based approach to the provision of health care services. In the 1990 s, evidence-based medicine was defined as the integration of current best evidence with clinical expertise and patient values. When these methods are applied outside internal medicine, the process is called evidence-based practice (EBP). EBP facilitates understanding, interpretation, and application of the best current evidence into radiology practice, which optimizes patient care. It has been incorporated into "Practice-based Learning and Improvement" and "Systems-based Practice," which are two of the six core resident competencies of the Accreditation Council for Graduate Medical Education and two of the 12 American Board of Radiology milestones for diagnostic radiology. Noninterpretive skills, such as systems-based practice, are also formally assessed in the "Quality and Safety" section of the American Board of Radiology Core and Certifying examinations. This article describes (a) the EBP framework, with particular focus on its relevance to the American Board of Radiology certification and maintenance of certification curricula; (b) how EBP can be integrated into a residency program; and (c) the current value and likely place of EBP in the radiology information technology infrastructure. Online supplemental material is available for this article. © RSNA, 2015.

Remote handling at LAMPF

International Nuclear Information System (INIS)

Grisham, D.L.; Lambert, J.E.

1983-01-01

Experimental area A at the Clinton P. Anderson Meson Physics Facility (LAMPF) encompasses a large area. Presently there are four experimental target cells along the main proton beam line that have become highly radioactive, thus dictating that all maintenance be performed remotely. The Monitor remote handling system was developed to perform in situ maintenance at any location within area A. Due to the complexity of experimental systems and confined space, conventional remote handling methods based upon hot cell and/or hot bay concepts are not workable. Contrary to conventional remote handling which require special tooling for each specifically planned operation, the Monitor concept is aimed at providing a totally flexible system capable of remotely performing general mechanical and electrical maintenance operations using standard tools. The Monitor system is described

[Instruction in dental radiology