Quality assurance in the transport of radiography sources

International Nuclear Information System (INIS)

Parihar, Manju; Singh, R.K.; Upadhyay, K.C.; Agarwal, S.P.

2001-01-01

One of the applications of radioisotopes in industry is non destructive testing (NDT) where the industrial radiography sources are often transported in public domain for site radiography. About 1100 cameras are deployed in our country. This transport of the sources can lead to significant radiological impact in case of accidents unless all precautions are taken. It is, therefore, required to have a systematic programme of controls and inspections in the transport of radioactive source. In this paper, we discuss the quality assurance programme that should be applied in various stages of the transport of radioactive sources to ensure a safe transport and prompt delivery of the radioactive consignment at its destination. (author)

Radiological security for industrial radiography

International Nuclear Information System (INIS)

Montoya G, Manuel.

1985-04-01

This report comprises the basic notions of nucleonics, simple calculations for point sources, X-rays, calculations for coatings, standards for radiation protection and industrial radiography instruments. The preceding sums up with the biological effects of ionizing radiation. This is a guide for people who wish to pass examinations, to get the license for radiological safety, for operators on gamma-graphic sources, which work in the country. It is a requirement for work with this kind of radioactive sources

Physical protection of mobile radioactive sources commonly used in the well logging and industrial radiography industries

International Nuclear Information System (INIS)

Barlow, Maegon E.

2016-01-01

The mission of the U.S. Department of Energy/National Nuclear Security Administration's (NNSA) Office of Radiological Security (ORS) is to protect high-activity radiological materials around the globe. ORS works domestically within the United States and collaborates with over 80 countries to protect medical, industrial, research and other radiological sources from being used by malicious actors in a radiological dispersal device (RDD) or radiation exposure device (RED). One area of specific concern is mobile radioactive sources, such as those used in radiography to inspect welds or metal integrity, and those in the oil and gas industry to characterize exploration and production wells in pursuit of oil caches. These mobile radiological sources are of sufficient Curie quantities to be categorized as desirable sources for malicious actors. This presentation will provide an overview of a mobile source tracking system developed by ORS in conjunction with Pacific Northwest National Laboratory (PNNL), and will discuss how the system can contribute to source security, as well as next steps to pilot this technology

Workshop on industrial isotope radiography: Programme and lectures

International Nuclear Information System (INIS)

1979-01-01

The booklet contains the texts of lectures delivered in the Workshop on Industrial Radiography held at Bombay during 24-25 July 1979. The lectures cover some topics of relevance to industrial radiography. The topics are radiation protection and legislative aspects in industrial radiography; problems in field radiography in fertilizer industry, petrochemical industry and heavy engineering industry; occupational exposures in industrial radiography; and a review of the progress and recent trends in industrial radiographic techniques and equipment. (M.G.B.)

Accidents in industrial radiography in Brazil from 2005 to 2010

International Nuclear Information System (INIS)

Lopes, Ricardo Tadeu

2011-01-01

Analysis of accidents occurring in industrial radiography in Brazil from 2005 until 2010 led to the study of the main characteristics of the events, their risks and dangers. This study outlines the main doubts on the subject, through a simplified analysis of the contents of high dose reports sent to CNEN by the companies that provide services for industrial radiography and from examining the growing number of radioactive sources for industrial radiography in Brazil, over this period. We classified the recorded events, as incidents, accidents, negligence, sabotage, and others, and studied their main consequences. We concluded that from 76 accidents that occurred during that period - 25 were real accidents, 13 minor accidents and 22 were inadvertent incidents. We found that the rate of growth in the number of sources is much greater than the rate of growth of accidents, with a ratio of 7.57 between them. The continuation of this study over some years, will allow the construction of a pyramid of accidents like the one developed by the Insurance Company of North America, specifically for industrial radiography to forecast the number of incidents and accidents that lead to serious or fatal injury. (author)

Industrial radiography in the Philippines: safety concerns

International Nuclear Information System (INIS)

David, Jocelyn L.; Artificio, Thelma P.; Cerbolles, Justina S.; Caseria, Estrella S.; Agron, Inocencio A.

2005-01-01

Industrial radiography utilizes the highest activity (5.55 tera becquerel (TBq) to 7.4 TBq) among the various mobile application of radioisotopes. It is highly possible that radiographers exceed the annual dose limits for workers occupationally exposed to radiation (as prescribed in the Code of PNRI Regulations part 3) if they do not give cautious consideration to the factors that determine the radiation dose, namely: the gamma source dose rates, time distance and shielding. To enhance the safety culture among radiographers, various strategies are recommended to be undertaken by the Philippine Nuclear Research Institute as well as the licensed companies undertaking activities in industrial radiography. (Authors)

Low cost automatic cable winder for industrial radiography projector

International Nuclear Information System (INIS)

Nor Arymaswati Abdullah; Abdul Nassir Ibrahim; Shaharudin Sayuti; Glam Hadzir Patai Mohamad; Masrol Nizam Salleh; Arshad Yasin; Nur Aira Abdul Rahman

2009-04-01

Radiography is a well-established technique that is widely used to detect internal flaws in welds, castings and to check for misconstruction in assemblies. In general it is to verify weld quality in engineering structures such as the fabrication of pressure vessels, pipelines and storage tanks. It can be used on all metals, from light metals such as aluminium to dense metals such as lead. One of the techniques is industrial radiography projector. Industrial radiography projector is used to store radioactive materials when it is not required to expose the material under test. The projector will come together with a guide tube and control unit (cable winder and drive cable). When the source is to be used to radiograph an item, the cable winder will wind-out the source from projector to the desired location through a guide tube. Upon completion of the work the source will be retracted back into its safe shielded position in this projector. In common procedure, the operator has to be close to the exposures projector while wind-out or wind-in the source from and into the projector. This made the radiography operator receive the highest exposure among the radiation operator and this agreed by IAEA. This paper describes a winder cable that can be used to guide the movement of radiography source out of and into the projector that can be controlled by a remote control system. The system comprises of a gear, reversible motor and low frequency automatic controller. This system is powered by DC chargeable battery. (author)

Radiological safety aspects of industrial radiography

International Nuclear Information System (INIS)

Hanekom, A.P.

1983-01-01

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

The 10 recommendations for prevention of radiation accidents in industrial gamma radiography

International Nuclear Information System (INIS)

Souza, Luana Silva de

2015-01-01

The Industrial Gamma Radiography, as part of Industrial Radiography, stands out as the most widespread and plays an important role in the quality control of different materials and devices. However, IAEA classifies industrial gamma radiography in the Category 2 as very dangerous due to the radiological risk caused by the use of high activity radioactive sources. In March, 2012, a Brazilian Workshop on Prevention of Industrial Gamma Radiography Accident was performed by DIAPI/CNEN with the objective of disseminating knowledge about radiological accidents with radioactive sources in this application. During this Workshop, IRD/CNEN conducted a survey with 75 participants using a form with 22 recommendations to prevent radiological accidents, aiming to select the most voted. This present work aims to perform a detailed statistical study to define the Top 10 Recommendations for industrial gamma radiography operator avoids radiological accidents and to prepare a brochure with these top 10 recommendations to be distributed to all industrial gamma radiography radiation workers. Data analysis was performed using the statistical method 'Frequency Distribution', among the 75 participants categorized as General, RPO, and Other Workers of the area. The results were obtained for each category, accounting for the total of 22 recommendations in its percentage and number of votes, and the top 10 recommendations were defined to prevent radiological accidents. The first place and most important recommendation is 'Always use a personal alarm monitor throughout the work'. One of the conclusions is that the brochure with the Top 10 Recommendations shows to be understandable and useful for dissemination and training of radiation workers to avoid radiological accidents in industrial gamma radiography. (author)

Educational aspects of industrial radiography

International Nuclear Information System (INIS)

Krishnamurthy, K.; Wamorkar, R.R.; Singh, G.

1979-01-01

The state of art of training and education in non-destructive testing in India, with special reference to industrial radiography is reviewed. Basic requirement of industry and potential of radioisotopes in industrial inspection are also described. Need for an organised training programme in industrial isotope radiography to exploit potentials for benefit of industry concurrent with the safety is stressed. A comprehensive training programme tailored to meet the needs of Indian industry is outlined. Benefits obtained from the course to the industry since the beginning of the training programme are briefly reviewed. (auth.)

Industrial Radiography | Radiation Protection | US EPA

Science.gov (United States)

2017-08-07

Manufacturers use a method called industrial radiography to check for cracks or flaws in materials. Radiation is used in industrial radiography to show problems not visible from the outside without damaging the material.

A mobile-device based applications software for industrial gamma radiography

International Nuclear Information System (INIS)

Acharya, Rajesh V.; Mitra, Anant; Kumar, Saroj; Lakshminarayana, Y.; Walinjkar, Parag; Kumar, Umesh

2013-12-01

The paper discusses a mobile device based application software for performing calculations required in industrial film radiography using radioisotope sources. The application enables the user to find residual life of a radioactive source, saving multiple source details in the phone memory, exposure time calculation required in gamma radiography and running multiple countdown clocks for accurate and convenient counting of exposure time. The application is also able to provide vibrating and audio alarms when the countdown finishes, automatic SMS facility to multiple users informing details of low activity sources in custody and cordon-off distances for open-source radiography. The application has been developed to work under Android, I-phone (Apple), Blackberry (RIM), Windows, Symbian operating systems and J2ME enabled feature phones. A simplified version of this application with limited features runs on java enabled low-cost mobile phones and tablets. (author)

Radiological emergency system in Madagascar, case of loss of a source of industrial radiography

International Nuclear Information System (INIS)

Randriantsizafy, R.D.; Raoelina Andriambololona; Zafimanjato, J.L.R.

2012-06-01

In Madagascar, a national radiological emergency response is not formally established. However, an Ad Hoc Committee of safety and nuclear safety and radiological is in place. The committee is composed of several Government entities and the role of each is identified. This Ad Hoc Committee has demonstrated its effectiveness for real action in 2010 with the loss of industrial radiography Container with Ir-192 source, the emergency is classified in threat category IV. Concerning the theft, the communication with the public and the other state entities, the search for the source and the source recovery were conducted in coordination between the different members. And of course, the lessons were reported during the operation which lasted more than three months

Industrial radiography

International Nuclear Information System (INIS)

Aloni, A.; Magal, O.

1992-02-01

This publication is meant to be a manual for industrial radiography. As such the manual concentrates on the practical aspects, presenting existing radiographic system and techniques of operation to satisfy specified quality requirements. The manual also reviews the safety aspect of performing radiographic work. (author) systems

Radiation protection for industrial radiography in the aerospace industry

International Nuclear Information System (INIS)

Morgan, W.E.

1980-01-01

The Boeing Company employs 80 industrial radiographers, operates 90 radiation sources, and takes 10,000 exposures per month. This paper describes the major components of Boeing's radiation protection program: hazard analysis, facilities and equipment design, program administration, and evaluation. In the hazard analysis, each source of radiation is analyzed to determine its hazard and relationship to both man and the environment around it. Once the degree of the hazard is known, facilities and equipment are designed to contain the hazard. This can be anything from a four foot concrete shielded room for an industrial radiographic accelerator, to a piece of rope that isolates an Iridium-192 source during a field radiographic inspection on an aircraft. The administrative functions provide the necessary records, command media, and a radiation source certification program. This certification authorizes the source of radiation to be used under specific conditions agreed upon by both the Radiation Protection Organization and Industrial Radiography Management. The radiation protection program is evaluated through medical exams, personnel monitoring, and area radiation surveys. (H.K.)

Monte Carlo investigation of design aspects of indigenously developed 120 Ci 60Co based industrial radiography device

International Nuclear Information System (INIS)

Palam Selvam, T.; Vishwakarma, R.S.; Sahoo, Dhiren K.; Sharma, Manoj K.; Srivastava, Piyush

2016-01-01

Industrial Radiography is an indispensable, versatile and well-established non destructive testing (NDT). Industrial radiography is carried out by using industrial radiography gamma exposure devices (IGRED) housing 60 Co and 192 Ir radioactive sources, and Industrial X-ray machines/accelerators. IGRED is an assembly of components which includes source housing, exposure mechanism, source drive system, pig tail, and source conduit. In the present study, we investigated the shielding design aspects of 120 Ci 60 Co-based IRGED using the Monte Carlo methods (MCNP version 3.1). The design details were provided by Board of Radiation and Isotope Technology (BRIT). As the objective is to finalize the suitable design of the device, we also included additional designs. The work also included measurements around the device using TLDs

Development of tungsten collimators for industrial radiography

International Nuclear Information System (INIS)

Varkey, P.A.; Verma, P.B.; Jayakumar, T.K.; Mammachan, M.K.

2001-01-01

Collimators are essential components of industrial radiography set up as it provides radiation safety to persons involved in the radiography work. A collimator with optimum design features also helps in reducing the scattered radiation which in turn results in radiographs having better sensitivity. This papers describes the salient design features of the tungsten collimators developed by the BRIT, for industrial radiography. (author)

10 CFR 34.13 - Specific license for industrial radiography.

Science.gov (United States)

2010-01-01

... 10 Energy 1 2010-01-01 2010-01-01 false Specific license for industrial radiography. 34.13 Section 34.13 Energy NUCLEAR REGULATORY COMMISSION LICENSES FOR INDUSTRIAL RADIOGRAPHY AND RADIATION SAFETY... industrial radiography. An application for a specific license for the use of licensed material in industrial...

Radiography using californium-252 neutron sources

International Nuclear Information System (INIS)

Ray, J.W.

1975-01-01

The current status in the technology of neutron radiography using californium-252 neutron sources is summarized. Major emphasis is on thermal neutron radiography since it has the widest potential applicability at the present time. Attention is given to four major factors which affect the quality and useability of thermal neutron radiography: source neutron thermalization, neutron beam extraction geometry, neutron collimator dimensions, and neutron imaging methods. Each of these factors has a major effect on the quality of the radiographs which are obtained from a californium source neutron radiography system and the exposure times required to obtain the radiographs; radiograph quality and exposure time in turn affect the practicality of neutron radiography for specific nondestructive inspection applications. A brief discussion of fast neutron radiography using californium-252 neutron sources is also included. (U.S.)

Construct a procedure to verify radiation protection for apparatus of industrial gamma radiography

International Nuclear Information System (INIS)

Nghiem Xuan Long; Trinh Dinh Truong; Dinh Chi Hung; Le Ngoc Hieu

2013-01-01

Apparatus for industrial gamma radiography include an exposure container, source guide tube, remote control hand crank assembly and other attached equipment. It is used a lot in inspection and evaluation of projects. In Vietnam, there are now more than 50 companies in radiography field and more than 100 apparatus are being used on the site. Therefore, the verification and evaluation is very necessary and important. This project constructs a procedure to verify a radiation protection for apparatus in the industrial gamma radiography for its application in Vietnam. (author)

Personnel exposures in industrial radiography

International Nuclear Information System (INIS)

Shenoy, K.S.; Patel, P.H.

1979-01-01

The manifold increase in production, and ease of availability of radioisotopes in India have been responsible for a tremendous increase in use of radioisotopes in industrial radiography during past fifteen years. Among various applications of radioisotopes the industrial radiography involves a large potential risk of occupational radiation exposures. The dose records of past fifteen years in respect of all radiation workers maintained by the Personnel Monitoring Group of Division of Radiological Protection of the Bhabha Atomic Research Centre, Bombay, have been analysed. Analysis of excessive exposure (exceeding 400 mrem/fortnight) reveals that this figure is increasing at an alarming rate among the radiation workers of this category. In spite of various regulatory controls the dose per person per week has remained higher as compared to the same in other categories. This combined with the increase in number of radiation workers every year would soon contribute significantly to the per capita dose for radiation workers. Use of adequately shielded fool-proof remote control equipment and training of all personnel in safe handling of radiation sources seem to be the only solution to arrest the rate of increase in personnel exposures of this category. (auth.)

Charter of good practices in industrial radiography

International Nuclear Information System (INIS)

2010-01-01

This document describes good practices in the field of industrial radiography. After having presented the main prevention and radiation protection principles, the actors inside and outside of the company, and actors intervening during an operation subcontracting in industrial radiography, this report analyzes the activity: prerequisites for work preparation, prevention coordination, work preparation, transportation, work achievement, return on experience. It addresses personnel training and information, and the dosimetric and medical monitoring of technicians in industrial radiography. Some aspects are addressed in appendix: principles (justification, optimization, and limitation), regulations, intervention form, exposure form, and so on

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)

Resolution 12/2004 Guideline for implementation of safety regulations in the practice of industrial radiography

International Nuclear Information System (INIS)

2004-01-01

1. This guide is intended to clarify, in relation to its application in practice Industrial Radiography, the provisions of: a) Joint Resolution CITMA-MINSAP, of December 15, 2002, Regulation: B asic Radiation Safety Standards , hereinafter Regulation NBS; b) Resolution No. 25/98 of CITMA Regulation. A uthorization Practices Associated with the use of ionizing radiation , hereinafter Resolution 25/98; c) Resolution 121/2000 CITMA Regulation: F or the Safe Transport of Radioactive materials , hereinafter Resolution 121/2000; and in d) Joint Resolution CITMA-MINSAP, Regulation: S election, Training and Authorization of personnel performing Employment Practices Associated Radiation Ionizing . 2. For the purposes of applying this Guide considers the practice of Industrial Radiography includes the following techniques: a) Industrial Radiography with use of gamma radiation sources; b) crawler radiography equipment; and c) Industrial Radiography with X-rays

Code of practice in industrial radiography

International Nuclear Information System (INIS)

Karma, S. E. M.

2010-12-01

The aim of this research is to developing a draft for a new radiation protection code of practice in industrial radiography without ignoring that one issued in 1998 and meet the current international recommendation. Another aim of this study was to assess the current situation of radiation protection in some of the industrial radiography department in Sudan. To achieve the aims of this study, a draft of a code of practice has been developed which is based on international and local relevant recommendations. The developed code includes the following main issues: regulatory responsibilities, radiation protection program and design of radiation installation. The practical part of this study includes scientific visits to two of industrial radiography departments in Sudan so as to assess the degree of compliance of that department with what state in the developed code. The result of each scientific visits revealed that most of the department do not have an effective radiation protection program and that could lead to exposure workers and public to unnecessary dose. Some recommendations were stated that, if implemented could improve the status of radiation protection in industrial radiography department. (Author)

Safety culture in industrial radiography facility

International Nuclear Information System (INIS)

Vincent-Furo, Evelyn

2015-02-01

This project reviewed published IAEA materials and other documents on safety culture with specific references to industrial radiography. Safety culture requires all duties important to safety to be carried out correctly, with alertness, due thought and full knowledge, sound judgment and a proper sense of accountability. The development and maintenance of safety culture in an operating organization has to cover management systems, policies, responsibilities, procedures and organizational arrangements. The essence is to control radiation hazard, optimize radiation protection to prevent or reduce exposures and mitigate the consequences of accidents and incidents. To achieve a high degree of safety culture appropriate national and international infrastructure should exist to ensure effective training of workers and management system that supports commitment to safety culture at all level of the organization; management, managers and workforce. The result of the review revealed that all accidents in industrial radiography facilities were due to poor safety culture practices including inadequate regulatory control oversight. Some recommendations are provided and if implemented could improve safety culture leading to good safety performance which will significantly reduce accidents and their consequences in industrial radiography. These examples call for a review of safety culture in Industrial radiography. (au)

Radiological protection procedures for industrial applications of computed radiography

International Nuclear Information System (INIS)

Aquino, Josilto Oliveira de

2009-03-01

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

Industrial sources in Norway -- Regulations and requirements

International Nuclear Information System (INIS)

Saxeboel, G.

2001-01-01

On 12 May 2000, a new Act on radiation protection passed the Norwegian parliament. The report explains the requirements for the licensing process of sealed industrial sources and provides information, in particular, on the national inventory of industrial gauges, industrial radiography and logging sources. (author)

Digital radiography is promising in industrial testing

International Nuclear Information System (INIS)

Del Fabbro, F.

2015-01-01

Digital radiography has recently entered the industrial world as a tool for non-destructive testing. There are 3 types of digital radiography: computed radiography (CR), direct radiography (DR) and computed tomography (CT). In computed radiography, traditional silver-halide films are replaced by photostimulable phosphor imaging plates that are activated through laser scanning and digitized. Direct radiography uses a flat panel detector (FPD) composed of X-ray detectors that performs an immediate digital conversion of the image that can be read by a computer. DR is a perfect tool for industrial testing but the fragility of the FPD panels reduces its uses. Computed tomography is based on the principle of DR to get data corresponding to successive cross-section images of the object. These data are processed by a software to get a 3-dimensional image of the object. CT was first developed for medical use but requires some improvement to become more accurate, faster, particularly for big objects. In recent years DR has enjoyed the highest growth rate in digital radiography. (A.C.)

Charter of good practices in industrial radiography; Charte de bonnes pratiques en radiographie industrielle

Energy Technology Data Exchange (ETDEWEB)

NONE

2010-07-01

This document describes good practices in the field of industrial radiography. After having presented the main prevention and radiation protection principles, the actors inside and outside of the company, and actors intervening during an operation subcontracting in industrial radiography, this report analyzes the activity: prerequisites for work preparation, prevention coordination, work preparation, transportation, work achievement, return on experience. It addresses personnel training and information, and the dosimetric and medical monitoring of technicians in industrial radiography. Some aspects are addressed in appendix: principles (justification, optimization, and limitation), regulations, intervention form, exposure form, and so on

Developing a training program for radiation protection officers in industrial radiography

International Nuclear Information System (INIS)

Kinda, R.

2013-04-01

Non-Destructive Testing employs a variety of techniques which are used to test objects e.g. pipes, vessels, welded joints, castings and other devices for imperfections without interfering with their physical structure. The common methods of testing include magnetic particle, ultrasound, dye penetrant and industrial radiography using gamma emitting radiation sources and electronic x-ray emitting devices. Other methods used are acoustic emission testing, acoustic resonance testing, electromagnetic testing, infrared testing and leak testing. This project work focuses on training of RPOs in the areas where radiation is used, as improper use may lead to high radiation exposure. In order to ensure adequate protection and safety of staff and the public, the Radiation Protection Officers need to be thoroughly trained. With proper training the Radiation Protection Officer will have the ability to interpret legislative instruments and understand the requirements. The RPO will also be able to develop a Radiation Protection Plan and train fellow staff on radiation safety issues. A number of companies currently specialize in Industrial Radiography and this number is growing on a yearly basis. Since the increased use of radiation sources cannot be curbed, training Radiation Protection Officers will improve the radiation safety standards within these companies and promote the safe use of the radiation sources. Therefore this project covers the fundamental elements required to train Radiation Protection Officers in Industrial Radiography. (author)

10 CFR 34.42 - Radiation Safety Officer for industrial radiography.

Science.gov (United States)

2010-01-01

... 10 Energy 1 2010-01-01 2010-01-01 false Radiation Safety Officer for industrial radiography. 34.42 Section 34.42 Energy NUCLEAR REGULATORY COMMISSION LICENSES FOR INDUSTRIAL RADIOGRAPHY AND RADIATION... Radiation Safety Officer for industrial radiography. The RSO shall ensure that radiation safety activities...

INDUSTRIAL RADIOGRAPHY STUDENT GUIDE AND LABORATORY EXERCISES.

Science.gov (United States)

Bureau of Adult, Vocational, and Technical Education (DHEW/OE), Washington, DC. Div. of Vocational and Technical Education.

THIS INSTRUCTOR'S GUIDE TO AN 80-HOUR COURSE IN INDUSTRIAL RADIOGRAPHY IS COORDINATED WITH LESSONS IN THE STUDENT GUIDE AND LABORATORY EXERCISES AND IS BASED ON MATERIAL IN THE COURSE MANUAL, INDUSTRIAL RADIOGRAPHY. THE COURSE IS INTENDED TO TRAIN HIGH SCHOOL GRADUATES AS BEGINNING RADIOGRAPHERS WHO ARE EXPECTED TO BE ABLE TO EXTEND THEIR…

Radiation protection and safety in industrial radiography

International Nuclear Information System (INIS)

1999-01-01

The use of ionizing radiation, particularly in medicine and industry, is growing throughout the world, with further expansion likely as technical developments result from research. One of the longest established applications of ionizing radiation is industrial radiography, which uses both X radiation and gamma radiation to investigate the integrity of equipment and structures. Industrial radiography is widespread in almost all Member States. It is indispensable to the quality assurance required in modern engineering practice and features in the work of multinational companies and small businesses alike. Industrial radiography is extremely versatile. The equipment required is relatively inexpensive and simple to operate. It may be highly portable and capable of being operated by a single worker in a wide range of different conditions, such as at remote construction sites, offshore locations and cross-country pipelines as well as in complex fabrication facilities. The associated hazards demand that safe working practices be developed in order to minimize the potential exposure of radiographers and other persons who may be in the vicinity of the work. The use of shielded enclosures (fixed facilities), with effective safety devices, significantly reduces any radiation exposures arising from the work. This Safety Report summarizes good and current state of the art practices in industrial radiography and provides technical advice on radiation protection and safety. It contains information for Regulatory Authorities, operating organizations, workers, equipment manufacturers and client organizations, with the intention of explaining their responsibilities and means to enhance radiation protection and safety in industrial radiography

Cytogenic investigations of serious overexposures to an industrial gamma radiography source

International Nuclear Information System (INIS)

Sevan'kaev, A.V.; Lloyd, D.C.; Edwards, A.A.; Moquet, J.E.; Nugis, V.Yu.; Mikhailova, G.M.; Potetnya, O.I.; Khvostunov, I.K.; Guskova, A.K.; Baranov, A.E.; Nadejina, N.M.

2002-01-01

This paper describes the sequence of events, medical aspects and dose estimations for two radiographers and their driver who were seriously exposed to an iridium-192 industrial radiography source that became detached from its wind-out cable. The men came to medical attention about 1 month later by which time all three were severely leucopenic and one had skin burns on both hands. Doses were estimated by (i) physics calculations combined with their accounts of the event, (ii) the levels of depression of their blood neutrophils, (iii) electron spin resonance on tooth enamel and (iv) blood lymphocyte chromosomal analyses by the conventional dicentric and the fluorescence in situ hybridisation methods. Intercomparison of these methods for estimating doses showed a good level of agreement. In brief, the averaged whole body dose for the most seriously exposed man was about 2.5-3.0 Gy and for the others it was 1.0-2.0 Gy. (author)

Minimising radiation exposure due to source assembly-related deficiencies in industrial gamma radiography exposure devices (IGREDs)

International Nuclear Information System (INIS)

Sivaraman, G.; Kannan, R.; Nandakumar, A.N.; Subrahmanya, M.J.; Murthy, B.K.S.

2000-01-01

Industrial radiographers receive higher doses as compared to radiation workers in medicine, agriculture, research, etc. Hence, it is essential that industrial gamma radiography exposure device (IGRED) be provided with efficient and effective safety systems in their design and operation to ensure smooth operation and minimise radiation exposures to the operators and public. Even though all these exposure devices have undergone stringent tests for radiographic exposure devices under international or national standards, certain deficiencies were noticed when scientists of Radiological Physics and Advisory Division (RPAD), carried out radiography equipment inspection of IGREDs. Some examples are briefly described here. The use of depleted Uranium pencil in some models led to the source pencil getting jammed due to formation of Uranium Oxide and bulging of the pencil. The solution was to replace the uranium pencil with high quality tungsten pencils or stainless steel clad pencils. In one type of pencils the source assembly would flare up after some use obstructing the smooth movement of the source assembly. The suggestion to subject the source assemblies to heat treatment solved the problem. In another type, the source pencil was getting corroded in high humid condition and affected the source movement. When the composition of the source pencil was changed it could withstand high humid condition. Another model had a hook type coupling between source assembly and drive cable. This often resulted in disengagement of the source assembly from the drive cable. Suggestions were made to change the coupling to ball and socket coupling for smooth functioning and for 'fail-safe' operation. During early days of the use of remote operated IGRED, in one particular model of the IGRED, the Iridium source wafers were directly loaded in a single encapsulation. Once the welding gave way and the source wafers got strewn. Subsequently, the source pellets/wafers were doubly encapsulated

Findings of the inspection grading system on industrial radiography

International Nuclear Information System (INIS)

Gloria Doloressa

2011-01-01

The use of industrial radiography techniques evolve rapidly and widely. Various jobs in industry require the examination of welding techniques / connecting pipes and metal construction. The use of industrial radiography is one type of utilization of nuclear energy must get control so that its use does not cause harmful impacts to worker safety, community, and environment. Regulations is done through inspections, in order to supervise the observance of the terms in the licensing and legislation in the field of nuclear safety. The main purpose of inspection is to ensure the utilization of radiation sources of radiation have been used with. Findings of the inspection is a decline in the performance of licensees in meeting safety requirements. The Grading System to the findings of the inspection needs to be done to improve the effectiveness and efficiency of inspection, and it is expected that the company can improve the management of radiation safety. (author)

The industrial radiography of defects inside the European Community

International Nuclear Information System (INIS)

Roeper, Burkhardt; Kaempf, B.

1976-03-01

The concept of the industrial radiography applied to defect invesigation is defined. The following topics are successively discussed: the development of the industrial 'defect radiography', apparatus and auxiliary equipments used in the field, the market, the constructors, trade currents in 'defect radiography' inside the Community and in the outer market; prognostics on future requirements in the fields

Code of practice for the safe use of industrial radiography equipment (1989)

International Nuclear Information System (INIS)

1989-12-01

This code supersedes the Code of practice for the control and safe handling of sealed radioactive sources used in industrial radiography, published by the National Health and Medical Research Council (NHMRC) in 1968. It differs significantly from the former code because radiation protection practice and recommended standards have changed. The code covers the design, construction and requirements for the safe use of X-radiography equipment and gamma-radiography equipment. It provides illustrative working rules, detailed emergency procedures and comprehensive responsibilities and duties for all personnel involved in supplying and using industrial radiography equipment. The code details those equipment requirements, personnel requirements and work practices that the NHMRC considers necessary to keep exposures to ionizing radiation as low as reasonably achievable. Some equipment and facilities currently in use may not meet all of the mandatory requirements of this code. These requirements have been included in the code to encourage progress towards future compliance in the expectation that, in the interim, statutory authorities will apply them with discretion

The 10 recommendations for prevention of radiation accidents in industrial gamma radiography; As 10 recomendacoes mais importantes para prevencao de acidentes radiologicos em gamagrafia industrial

Energy Technology Data Exchange (ETDEWEB)

Souza, Luana Silva de

2015-07-01

The Industrial Gamma Radiography, as part of Industrial Radiography, stands out as the most widespread and plays an important role in the quality control of different materials and devices. However, IAEA classifies industrial gamma radiography in the Category 2 as very dangerous due to the radiological risk caused by the use of high activity radioactive sources. In March, 2012, a Brazilian Workshop on Prevention of Industrial Gamma Radiography Accident was performed by DIAPI/CNEN with the objective of disseminating knowledge about radiological accidents with radioactive sources in this application. During this Workshop, IRD/CNEN conducted a survey with 75 participants using a form with 22 recommendations to prevent radiological accidents, aiming to select the most voted. This present work aims to perform a detailed statistical study to define the Top 10 Recommendations for industrial gamma radiography operator avoids radiological accidents and to prepare a brochure with these top 10 recommendations to be distributed to all industrial gamma radiography radiation workers. Data analysis was performed using the statistical method 'Frequency Distribution', among the 75 participants categorized as General, RPO, and Other Workers of the area. The results were obtained for each category, accounting for the total of 22 recommendations in its percentage and number of votes, and the top 10 recommendations were defined to prevent radiological accidents. The first place and most important recommendation is 'Always use a personal alarm monitor throughout the work'. One of the conclusions is that the brochure with the Top 10 Recommendations shows to be understandable and useful for dissemination and training of radiation workers to avoid radiological accidents in industrial gamma radiography. (author)

The Information System on Occupational Exposure in Medicine, Industry and Research (ISEMIR): Industrial Radiography

Energy Technology Data Exchange (ETDEWEB)

NONE

2014-08-15

Industrial radiography work is often carried out under difficult working conditions, such as in confined spaces, in extreme cold or heat, or during the night. Working under such adverse conditions might result in operational situations in which occupational radiation protection may be compromised. Experience shows that incidents involving industrial radiography sources have sometimes resulted in high doses to workers, causing severe health consequences such as radiation burns and, in a few cases, death. It has been long known that there is significant potential for industrial radiography personnel to receive non-trivial occupational exposure. However, a global perspective is lacking, as is the availability of a systematic means for improving occupational radiation protection in industrial radiography worldwide. In 2006, the IAEA published IAEA Safety Standards Series No. SF-1, Fundamental Safety Principles, jointly sponsored by the European Atomic Energy Community, the Food and Agriculture Organization of the United Nations (FAO), the International Labour Organization (ILO), the International Maritime Organization, the OECD Nuclear Energy Agency (OECD/NEA), the Pan American Health Organization (PAHO), the United Nations Environment Programme (UNEP) and the World Health Organization (WHO). That publication sets out the fundamental safety objective and principles of protection and safety. In 2014, the IAEA published IAEA Safety Standards Series No. GSR Part 3, Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards (the BSS), jointly sponsored by the European Commission, the FAO, the ILO, OECD/NEA, the PAHO, UNEP and the WHO. The BSS sets out the requirements that are designed to meet fundamental safety objectives and to apply the principles specified in IAEA Safety Standards Series No. SF-1. The establishment of safety requirements and provision of guidance on occupational radiation protection is a major component of the support

The Information System on Occupational Exposure in Medicine, Industry and Research (ISEMIR): Industrial Radiography

International Nuclear Information System (INIS)

2014-08-01

Industrial radiography work is often carried out under difficult working conditions, such as in confined spaces, in extreme cold or heat, or during the night. Working under such adverse conditions might result in operational situations in which occupational radiation protection may be compromised. Experience shows that incidents involving industrial radiography sources have sometimes resulted in high doses to workers, causing severe health consequences such as radiation burns and, in a few cases, death. It has been long known that there is significant potential for industrial radiography personnel to receive non-trivial occupational exposure. However, a global perspective is lacking, as is the availability of a systematic means for improving occupational radiation protection in industrial radiography worldwide. In 2006, the IAEA published IAEA Safety Standards Series No. SF-1, Fundamental Safety Principles, jointly sponsored by the European Atomic Energy Community, the Food and Agriculture Organization of the United Nations (FAO), the International Labour Organization (ILO), the International Maritime Organization, the OECD Nuclear Energy Agency (OECD/NEA), the Pan American Health Organization (PAHO), the United Nations Environment Programme (UNEP) and the World Health Organization (WHO). That publication sets out the fundamental safety objective and principles of protection and safety. In 2014, the IAEA published IAEA Safety Standards Series No. GSR Part 3, Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards (the BSS), jointly sponsored by the European Commission, the FAO, the ILO, OECD/NEA, the PAHO, UNEP and the WHO. The BSS sets out the requirements that are designed to meet fundamental safety objectives and to apply the principles specified in IAEA Safety Standards Series No. SF-1. The establishment of safety requirements and provision of guidance on occupational radiation protection is a major component of the support

An overview of industrial radiography accidents in India during the period 1987-1997

International Nuclear Information System (INIS)

Kumar, A.; Subramanya, M.J.; Raghavendran, C.P.; Murthy, B.K.S.; Vishwakarma, R.R.; Kannan, R.; Sharma, A.; Bhatt, B.C.

1998-01-01

Use of gamma radiation sources for non-destructive testing of welds, castings and vital components in several industries in India has recorded a steep rise in the last three decades. There are over 1000 industrial gamma radiography exposure devices (IGRED) in over 400 institutions in the country. Most of these employ Co-60 and Ir-192 gamma sources. In spite of regulatory control and procedures there have been accidents with the IGREDs resulting in significant radiation exposures and in some cases, injuries to members of public and radiography personnel. This paper analyses the accidents which occurred in India during the ten year period of 1987-1997, management of such accidents, steps taken to avoid recurrence of these accidents based on the lessons learnt. (author)

Licensing for industrial gamma and X-ray radiography installation in Peru

International Nuclear Information System (INIS)

Medina G, E.

1988-01-01

According the regulations for ionizing radiation source installations an application to the Peruvian National Authority should be forwarded in order to get the construction on operation license both industrial gamma and X-ray. Radiography is considered as well as personnel aspects. The proceedings are described

Code of practice for the safe use of industrial radiography equipment (1989)

International Nuclear Information System (INIS)

1989-12-01

This code supersedes the Code of Practice for the control and safe handling of sealed radioactive sources use din industrial radiography, published by the National Health and Medical Research Council (NHMRC) in 1968. It differs significantly from the former code because radiation protection practice and recommended standards have changed. The code covers the design, construction and requirements for the safe use of X-radiography equipment and gamma-radiography equipment. It provides illustrative working rules, detailed emergency procedures and comprehensive responsibilities and duties for all personnel involved in supplying and using industrial radiography equipment. The code details those equipment requirements, personnel requirements and work practices that the NHMRC considers necessary to keep exposures to ionizing radiation as low as reasonably achievable. Some equipment and facilities currently in use may not meet all of the mandatory requirements of this code. These requirements have been included in the code to encourage progress towards future compliance in the expectation that, in the interim, statutory authorities will apply them with discretion. 9 refs., tabs., ills

Contemporary practice education: Exploring student perceptions of an industrial radiography placement for final year diagnostic radiography students

International Nuclear Information System (INIS)

Wareing, A.K.; Henderson, I.

2015-01-01

Introduction: There is a paucity of evidence in diagnostic radiography evaluating a career path into industrial imaging despite several higher education institutes stating this route as a career option on graduation. The link between a career in industrial radiography and diagnostic routes is unknown although there are anecdotal examples of individuals transferring between the two. Successfully obtaining a first post job following graduation in diagnostic radiography can be challenging in the current financial climate. A partnership was formed with an energy sector company that offered non-destructive testing/non-destructive evaluation (NDT/NDE) employing industrial radiographic technicians. Method: As an initial pilot, 5 (n = 5) final year diagnostic radiography students visited an industrial radiography site and underwent theoretical and practical training. Following this placement they engaged in a focus group and the student perceptions/responses were explored and recorded. Results: Common themes were identified and categorised via a thematic analysis. These were; radiation safety, physics and technology, widening access, graduate attributes/transferable skill sets and working conditions. Conclusion: Student discussion focussed around the benefits of working conditions in healthcare, the value of technology, safety and physics education in alternative placements and the transferability of skills into other/industrial sectors (e.g. NDT/NDE). Contemporary practice placements are a useful pedagogical approach to develop complex conceptual theoretical constructs, such as radiation physics. An in depth evaluation between the two industries skill sets is postulated. Additionally, this could offer alternative/emerging roles to interested diagnostic radiographers potentially meeting the skill shortage in industrial radiography. - Highlights: • Research in this area is novel. No evidence could be found to evaluate the links. • Students had theoretical

SIMPLE for industrial radiography

International Nuclear Information System (INIS)

Azhar Azmi; Abd Nassir Ibrahim; Siti Madiha Muhammad Amir; Glam Hadzir Patai Mohamad; Saidi Rajab

2004-01-01

The first thing industrial radiographers have to do before commencing radiography works is to determine manually the amount of correct exposure that the film need to be exposed in order to obtain the right density. The amount of exposure depends on many variables such as type of radioisotope, type of film, nature of test-object and its orientation, and specific arrangement related to object location and configuration. In many cases radiography works are rejected because of radiographs fail to meet certain reference criteria as defined in the applicable standard. One of the main reasons of radiograph rejection is due to inadequate exposure received by the films. SIMPLE is a software specially developed to facilitate the calculation of gamma-radiography exposure. By using this software and knowing radiographic parameters to be encountered during the work, it is expected that human error will be minimized, thus enhancing the quality and productivity of NDT jobs. (Author)

Radiation exposures of workers resulting from the transport of gamma radiography sources in Germany

International Nuclear Information System (INIS)

Sentuc, F.N.; Schwarz, G.

2006-01-01

Gamma radiation sources are widely used for industrial purposes e.g. for non-destructive material testing. Many of these sources are permanently installed at a facility within instruments e.g. for level or thickness gauging. Other radioactive sources are implemented in portable devices for industrial gamma radiography which have to be carried to the various remote usage sites. In Germany, approximately 20 000 - 25 000 shipments of gamma radiography sources are proceeding annually on public transport routes. Since routine radiation monitoring programmes do not permit task-specific determination of occupational doses e.g. doses incurred during the movement phase and handling related doses, work has been carried out with the objective to determine the radiation exposures of the personnel attributable to transportation. For this purpose, a survey was launched in 2005 collecting data about e.g. the number and conditions of transports, the activity and type of transported radiation sources and the radiation level within the driver's cab to allow a dose assessment to be made for transport workers. The results of this survey covering the most important companies for gamma radiography services in Germany are presented in this paper. (authors)

Safety guide of safe use of industrial radiography

International Nuclear Information System (INIS)

1994-01-01

The objective of this guidance is to present general regulations for the safe use and radiation protection of industrial radiography. Storage and inspection of apparatus, personal instructions for working in radiography facilities are offered

Working safely in gamma radiography. A training manual for industrial radiographers

International Nuclear Information System (INIS)

McGuire, S.A.; Peabody, C.A.

1982-09-01

This manual is designed for classroom training in working safely in industrial radiography using gamma sources. The purpose is to train radiographers' assistants to work safely as a qualified gamma radiographer. The contents cover the essentials of radiation, radiation protection, emergency procedures, gamma cameras, and biological effects of radiation

Radiologic accidents in industrial gamma radiography - Brazilian cases

International Nuclear Information System (INIS)

Silva, Francisco Cesar Augusto da

1997-01-01

Three severe radiological accidents in industrial gamma radiography happened in Brazil during the period of 1985 to 1988. Five operators and nineteen public people were involved. These accidents caused some injuries in parts of the body, mainly hands and fingers. The main causes were faults in source monitoring, inadequate routine procedures and unknowing of radiation warning symbol by public people. The present paper shows the Brazilian cases of radiological accidents and makes some analysis of them. (author)

Digital and analogue industrial radiography, application fields

International Nuclear Information System (INIS)

Willems, Peter; Millord, Erik Yardin

2000-01-01

Full text: Reusable phosphor screens for computer radiography (CR), amorphous selenium screens for direct radiography (DR), film digitalisation (FD) constitute imaging methods accepted by industry and are used for non-destructive radiographic testing (RT). Economic pressures are involving and affecting digital RT technology. Standards and codes for film radiography and radioscopy qualification do no longer cover the wide range of digital RT applications. It will be our task to optimise the performance of digital RT characterisation and to create appropriate examination methods to use all these new and existent technologies. In the meantime, an increasing automation and control of manual methods of analogue radiography can as well be expected. (author)

10 CFR 34.61 - Records of the specific license for industrial radiography.

Science.gov (United States)

2010-01-01

... 10 Energy 1 2010-01-01 2010-01-01 false Records of the specific license for industrial radiography. 34.61 Section 34.61 Energy NUCLEAR REGULATORY COMMISSION LICENSES FOR INDUSTRIAL RADIOGRAPHY AND... Records of the specific license for industrial radiography. Each licensee shall maintain a copy of its...

Working safely in gamma radiography. A training manual for industrial radiographers

Energy Technology Data Exchange (ETDEWEB)

McGuire, S.A.; Peabody, C.A.

1982-09-01

This manual is designed for classroom training in working safely in industrial radiography using gamma sources. The purpose is to train radiographers' assistants to work safely as a qualified gamma radiographer. The contents cover the essentials of radiation, radiation protection, emergency procedures, gamma cameras, and biological effects of radiation. (ACR)

Assessment of whole-body occupational radiation exposure in industrial radiography practices in Bangladesh during 2010-2014

International Nuclear Information System (INIS)

Rahman, M.S.; Hoque, A.; Khan, R.K.; Siraz, M.M.M.; Begum, A.

2016-01-01

Presently, ten industrial radiography facilities are operating in Bangladesh using X-ray or gamma-ray sources. During the last 5-year, 14 industrial radiography facilities were received individual monitoring service using thermoluminescent dosimeters (TLDs) from the Health Physics Division (HPD), Atomic Energy Centre, Dhaka under Bangladesh Atomic Energy Commission. HPD is the only individual monitoring service provider in Bangladesh due to external sources of ionizing radiation. The number of monitored industrial radiography facilities ranged from 7 to 14 while the number of worker ranged from 72 to 133 during the study period. The annual average effective doses received from external radiation in industrial radiography workers and the distributions of the annual effective doses by dose intervals are presented. The distribution of the occupational doses shows that the majority (about 75 %) of workers received doses below 1 mSv for the last 5-years. Even though, very few workers (about 1%) received doses higher than average annual dose limit (20 mSv), but no workers received doses higher than 100 mSv in 5 consecutive years. The average annual effective dose of industrial radiography workers in Bangladesh is higher than the corresponding values in Tanzania, Greece, Poland, Australia, UK and lower than in Bosnia and Herzegovina, USA and Canada. However, the average annual effective dose is comparable to the corresponding values in China, Brazil, Germany and India. The status and trends in occupational doses show that radiation protection situation at the majority of the workplace were satisfactory. In spite of that, additional measures are required due to big differences observed in the maximum individual doses over the last 5-year. (author)

Assessment of whole-body occupational radiation exposure in industrial radiography practices in Bangladesh during 2010-2014

Energy Technology Data Exchange (ETDEWEB)

Rahman, M.S.; Hoque, A.; Khan, R.K.; Siraz, M.M.M., E-mail: msrahman74@hotmail.com [Health Physics Division, Atomic Energy Centre, Shahbag, Dhaka (Bangladesh); Begum, A. [Physical Science Division, Bangladesh Atomic Energy Commission, Dhaka (Bangladesh)

2016-07-01

Presently, ten industrial radiography facilities are operating in Bangladesh using X-ray or gamma-ray sources. During the last 5-year, 14 industrial radiography facilities were received individual monitoring service using thermoluminescent dosimeters (TLDs) from the Health Physics Division (HPD), Atomic Energy Centre, Dhaka under Bangladesh Atomic Energy Commission. HPD is the only individual monitoring service provider in Bangladesh due to external sources of ionizing radiation. The number of monitored industrial radiography facilities ranged from 7 to 14 while the number of worker ranged from 72 to 133 during the study period. The annual average effective doses received from external radiation in industrial radiography workers and the distributions of the annual effective doses by dose intervals are presented. The distribution of the occupational doses shows that the majority (about 75 %) of workers received doses below 1 mSv for the last 5-years. Even though, very few workers (about 1%) received doses higher than average annual dose limit (20 mSv), but no workers received doses higher than 100 mSv in 5 consecutive years. The average annual effective dose of industrial radiography workers in Bangladesh is higher than the corresponding values in Tanzania, Greece, Poland, Australia, UK and lower than in Bosnia and Herzegovina, USA and Canada. However, the average annual effective dose is comparable to the corresponding values in China, Brazil, Germany and India. The status and trends in occupational doses show that radiation protection situation at the majority of the workplace were satisfactory. In spite of that, additional measures are required due to big differences observed in the maximum individual doses over the last 5-year. (author)

Implementation of radiation protection programme in industrial radiography centers in Iran

Energy Technology Data Exchange (ETDEWEB)

Deevband, M. [Radiation Protection Department, Tehran (Iran, Islamic Republic of); Ghiassi Negad, M. [Radiation Protection Department, Tehran (Iran, Islamic Republic of); Borhan Azad, S. [Radiation Protection Department, Tehran (Iran, Islamic Republic of); Tavakoli, M. [Esfahan Univ. (Iran, Islamic Republic of)

2006-07-01

Industrial radiography is one of the essential methods in the modern technology to guarantee the quality control of many types of devices, pieces and machines operation, and usually involves intense radiation sources, which can expose people at work to significant amounts of radiation. According to the reports of United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR 2000), the average occupational effective dose in this field is 3.37 mSv/y. The level of dose received by industrial radiographers was assessed in more than 1300 radiation workers in 120 industrial radiography companies. The level of radiation safety regulations and radiation protection programme implemented in Iranian industries was also studied. The results indicated that the average effective dose to the radiographers and collective effective dose are 1.65 mSv/y and 2.43 Man.Sv respectively. The results also showed that 88% of radiographers have received less than 5 mSv/y and only 1% received the annual dose more than 20 mSv. The lack of emergency instruction was found in 47% of companies and in 35% of companies there was not found any compatible emergency instrument. Suitable temporary storage and transportation facility was no also found in 30% of companies. Based on the results found in this study, the enforcement of the radiation protection low and industrial radiography code of practice for responsible persons and health physics officers are recommended. (authors)

Implementation of radiation protection programme in industrial radiography centers in Iran

International Nuclear Information System (INIS)

Deevband, M.; Ghiassi Negad, M.; Borhan Azad, S.; Tavakoli, M.

2006-01-01

Industrial radiography is one of the essential methods in the modern technology to guarantee the quality control of many types of devices, pieces and machines operation, and usually involves intense radiation sources, which can expose people at work to significant amounts of radiation. According to the reports of United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR 2000), the average occupational effective dose in this field is 3.37 mSv/y. The level of dose received by industrial radiographers was assessed in more than 1300 radiation workers in 120 industrial radiography companies. The level of radiation safety regulations and radiation protection programme implemented in Iranian industries was also studied. The results indicated that the average effective dose to the radiographers and collective effective dose are 1.65 mSv/y and 2.43 Man.Sv respectively. The results also showed that 88% of radiographers have received less than 5 mSv/y and only 1% received the annual dose more than 20 mSv. The lack of emergency instruction was found in 47% of companies and in 35% of companies there was not found any compatible emergency instrument. Suitable temporary storage and transportation facility was no also found in 30% of companies. Based on the results found in this study, the enforcement of the radiation protection low and industrial radiography code of practice for responsible persons and health physics officers are recommended. (authors)

Equipment for x- and gamma ray radiography

International Nuclear Information System (INIS)

Abd Nasir Ibrahim; Azali Muhammad; Ab Razak Hamzah; Abd Aziz Mohamed; Mohammad Pauzi Ismail

2004-01-01

The following topics related to the equipment for x - and gamma ray radiography are discussed in this chapter. The topics are x-ray source for Industrial Radiography: properties of x-ray, generation of x-ray, mechanism of x-ray production, x-ray equipment, power supply, distribution of x-ray intensity along the tube: gamma ray source for Industrial Radiography: properties of gamma rays, gamma ray sources, gamma ray projectors on cameras, source changing. Care of Radiographic Equipments: Merits and Demerits of x and Gamma Rays

SisRadiologia: a new software tool for analysis of radiological accidents and incidents in industrial radiography

International Nuclear Information System (INIS)

Lima, Camila M. Araujo; Silva, Francisco C.A. da; Araujo, Rilton A.

2013-01-01

According to the International Atomic Energy Agency (IAEA), many efforts have been made by Member states, aiming a better control of radioactive sources. Accidents mostly happened in practices named as high radiological risk and classified by IAEA in categories 1 and 2, being highlighted those related to radiotherapy, large irradiators and industrial radiography. Worldwide, more than 40 radiological accidents have been recorded in the industrial radiography. Worldwide, more than 40 radiological accidents have been recorded in the industrial radiography area, involving 37 workers, 110 members of the public and 12 fatalities. Records display 5 severe radiological accidents in industrial radiography activities in Brazil, in which 7 workers and 19 members of the public were involved. Such events led to hands and fingers radiodermatitis, but to no death occurrence. The purpose of this study is to present a computational program that allows the data acquisition and recording in the company, in such a way to ease a further detailed analysis of radiological event, besides providing the learning cornerstones aiming the avoidance of future occurrences. After one year of the 'Industrial SisRadiologia' computational program application - and mostly based upon the workshop about Analysis and Dose Calculation of Radiological Accidents in Industrial Radiography (Workshop sobre Analise e Calculo de dose de acidentes Radiologicos em Radiografia Industrial - IRD 2012), in which several Radiation Protection officers took part - it can be concluded that the computational program is a powerful tool to data acquisition, as well as, to accidents and incidents events recording and surveying in Industrial Radiography. The program proved to be efficient in the report elaboration to the Brazilian Regulatory Authority, and very useful in workers training to fix the lessons learned from radiological events.

A Compact 5 MeV S-Band Electron Linac Based X-Ray Source for Industrial Radiography

CERN Document Server

Auditore, Lucrezia; De Pasquale, Domenico; Emanuele, Umberto; Italiano, Antonio; Trifirò, Antonio; Trimarchi, Marina

2005-01-01

A compact and reliable X-ray source, based on a 5 MeV, 1 kW, S-band electron linac, has been set up at the Dipartimento di Fisica, Universit\\'a di Messina. This source, coupled with a GOS scintillator screen and a CCD camera, represents an innovative transportable system for industrial radiography and X-ray tomography. Optimization of the parameters influencing the e-gamma conversion and the X-ray beam characteristics have been studied by means of the MCNP-4C2 code. The converter choice is the result of the study of the e-gamma conversion performances for different materials and materials thicknesses. Also the converter position with respect to the linac exit window was studied. The chosen converter consists in a Ta-Cu target inserted close to the linac window. The Cu layer acts as a filter both on the electrons from the source and on the low energy X-rays. The X-ray beam angular profile was studied by means of GafChromic films with and without collimation. In the final source project, a collimation system pr...

Incident in industrial gamma radiography in Argentina

International Nuclear Information System (INIS)

Alonso Jimenez, Maria T.; Ermacora, Marcela

2008-01-01

In the present work a description of an industrial gamma radiography incident is made and an analysis of the events which led to it is presented. The event took place during a routine regulatory inspection carried out by personnel of the Nuclear Regulatory Authority in the year 2004 to a storage facility of projectors and containers belonging to a company licensed to operate gamma radiography equipment. On arriving to the store authorized by the ARN, placed in an industrial site, it was verified that it was empty and without surveillance. The inspectors contacted the person responsible for radiological protection, who went to the place and declared that the totality of the equipment and radioactive sources had been moved to a private country house. The reason for this change, according to the statement, was that the company had gone bankrupt and the authorized storage facility had remained without surveillance and without personnel in charge. In the country house, inside the room meant as a store, high environmental equivalent dose rates were detected. After verifying the dose rates in each of the projectors, it was checked that one of them measured high dose rates. For this reason, it was isolated and the source recovery was done, due to the suspicion that it had remained in a non-shielded position. After projecting it several times towards a lead container due to the fact that high dose rates were still being measured, the person responsible for radiological protection proceeded to extract the source from the guide tube, finding that it had been transferred in the reverse order. According to the record of movements of equipment and radioactive sources of the company, the source transference had been done, in the previous store in the month of March 2004, by a radiographer who did not work at the company any longer and whose permit had expired. The results of the estimations of the doses received during the process of the source recovery are presented. Finally, an

Standing of industrial radiography in South Africa

International Nuclear Information System (INIS)

Marais, J.J.

1983-01-01

In this article a look is taken at industrial radiography in South Africa to determine where radiographic testing is being used, and for what reasons. The status of training of industrial radiographers is considered and it is compared to radiographic techniques used in South Africa

Industrial radiography X and Gamma

International Nuclear Information System (INIS)

Torres M, Nelson; Torres B, Miguel; Montanez, Juan.

1986-04-01

This publication gives a practical orientation on industrial radiography. The first chapters deal with basic facts that are useful for professional work in this field. It comprises topics such as generation of X-rays, equipment being used, radiographic films, sensibility, and the penetrameters used. This publication also describes the most used radiographic techniques and the processing of the radiographic film. It contains practical recommendations on how to obtain a good radiographic inspection. It states the reasons for defects in the radiographies. Two annexes are attached which include tables for the selection of penetrameters according to the ASME and DIN codes as well as the time needed for development and fixing according to the temperature

Radiation protection, safety and associated problems in industrial radiography

International Nuclear Information System (INIS)

Le Roux, P.R.

1990-01-01

Industrial radiography is an indispensable tool for non-destructive testing. Its use entails potential radiation exposure to the operator as well as to the public. Since such radiation has the potential to be harmful, there is a need to limit radiation exposure to a level at which the risk is believed to be acceptable to the individual and to society. The Radiation Protection Society and the Department of National Health believe that the level of protection provided for radiation workers should be comparable with that in other 'safe' industries. The total risk for radiation workers includes the risk of non-radiation related accidents in the various occupations, as well as the special risks of radiation exposure. Industrial radiographers have one of the poorest safety records of all non-medical radiation workers. Operator errors and management errors seem to be the primary contributors to most accidental high exposures. It is necessary to remember that industrial radiography has to be carried out in a wide variety of work places under many different working conditions, both by day and by night. High energy end emissivity (X-ray output or source activity) is required for the radiation to be transmitted through specimens, because these are normally constructed of thick and dense materials such as steel. Additionally, most radiographic sources must be portable to permit use in field locations. On the negative side it must be mentioned that studies undertaken abroad conclude that the most important factors contributing to unsafe operations are human related. Careful planning of the method of work is essential if unnecessary risks are to be avoided. The most effective way of reducing accidents would seem to be to train employees to adhere to established and well documented procedures, to exercise common sense and sound judgement, and to use the protective equipment and devices provided in the manner specified. 2 tabs., 3 refs

Radiation safety aspects in application of isotopes for industrial radiography in Bangladesh

Energy Technology Data Exchange (ETDEWEB)

Bakht, D. [Titas Gas Transmission and Distribution Company, Dhaka (Bangladesh)

1997-10-01

Industrial Radiography arose out of the widespread applications of X-rays pioneered by Roentgen about 100 years back. It is routinely used in studying the integrity of structural materials and like most countries in the world, its use in Bangladesh is increasing at a faster rate. This is because Bangladesh is a developing country of 3rd world and in the backdrop of agrarian poverty ridden economy, its population may exceed 125 millions by 2000 AD, leaving some 12 millions people unemployed. To support them, therefore, immense activities are activated in different sectors. Accordingly, increasing importance on NDT is given and in most cases particular application of Gamma radiography is preferred using Iridium Isotope Ir-192. Consequently the points of implications of isotopes are in Open Field and Inservice Inspection Radiography, Handling of Radiation Emergencies, Safe Transport of Radioactive Materials and Hazardous Effects and Risk of Ionizing Radiation, etc. Accordingly over exposure of Ir-192 Radionuclides, Accidents and Unusual Occurrences: Case Studies, Training Courses on Safety and Regulation of Sealed Sources, Licenses for Radiography Operation including Safe Disposal of Isotopes are the salient issues to be viewed in appropriate perspectives. The role played by Bangladesh Atomic Energy Commission and Bangladesh Society for NDT in collaboration with other members of the international committee for NDT are furthering the safe industrialization process

Radiation safety aspects in application of isotopes for industrial radiography in Bangladesh

International Nuclear Information System (INIS)

Bakht, D.

1997-01-01

Industrial Radiography arose out of the widespread applications of X-rays pioneered by Roentgen about 100 years back. It is routinely used in studying the integrity of structural materials and like most countries in the world, its use in Bangladesh is increasing at a faster rate. This is because Bangladesh is a developing country of 3rd world and in the backdrop of agrarian poverty ridden economy, its population may exceed 125 millions by 2000 AD, leaving some 12 millions people unemployed. To support them, therefore, immense activities are activated in different sectors. Accordingly, increasing importance on NDT is given and in most cases particular application of Gamma radiography is preferred using Iridium Isotope Ir-192. Consequently the points of implications of isotopes are in Open Field and Inservice Inspection Radiography, Handling of Radiation Emergencies, Safe Transport of Radioactive Materials and Hazardous Effects and Risk of Ionizing Radiation, etc. Accordingly over exposure of Ir-192 Radionuclides, Accidents and Unusual Occurrences: Case Studies, Training Courses on Safety and Regulation of Sealed Sources, Licenses for Radiography Operation including Safe Disposal of Isotopes are the salient issues to be viewed in appropriate perspectives. The role played by Bangladesh Atomic Energy Commission and Bangladesh Society for NDT in collaboration with other members of the international committee for NDT are furthering the safe industrialization process

Occupational exposure in Greek industrial radiography laboratories (2004-2006) and comparison of doses with other industrial applications

International Nuclear Information System (INIS)

Tritakis, P.; Papadomarkaki, E.; Economides, S.; Carinou, E.; Hourdakis, C.; Kamenopoulou, V.; Dimitriou, P.

2008-01-01

Full text: In this study the Mean Annual Dose (MAD) of all industrial radiography workers in Greece for the time period 2004-2006 is evaluated and correlated to the practice and type of equipment used. All data used in this study come from the National Dose Registry Information System of the Greek Atomic Energy Commission. The present study constitutes the follow up of two previous studies, where a Dose Constraint (DC) for industrial radiography in Greece, equal to 4.0mSv was introduced for the first time. The introduction and systematic use of a dynamic DC value aims to optimize common working practices through a continuous decrease of occupational doses. In the current work a further decrease in the industrial radiography personnel doses is observed and the factors leading to this result are analyzed. Finally, the estimated MAD value for exposed workers in industrial radiography is compared to the ones corresponding to workers in other industrial applications involving the use of ionizing radiation

Accidents in industrial radiography and lessons to be learned. A review of IAEA Safety Report

International Nuclear Information System (INIS)

Modupe, M.S.; Oresegun, O.

1998-01-01

This IAEA Safety Report Series publication is the result of a review of a large selection of accidents in industrial radiography which Regulatory Authorities, professional associations and scientific journals have reported. The review's objective was to draw lessons from the initiating events of the accidents, contributing factors and the consequences. A small, representative selection of accident descriptions is used to illustrate the primary causes of radiography accidents and a set of recommendations to prevent recurrence of such accidents or to mitigate the consequences of those that do occur is provided. By far the most common primary cause of over-exposure was 'Failure to follow operational procedures' and specifically failure to perform radiation monitoring to locate the position of the source. The information in the Safety Report is intended for use by Regulatory Authorities, operating organizations, workers manufacturers and client organizations having responsibilities for radiation protection and safety in industrial radiography. (author)

Radiological incidents in industrial gamma radiography in the Philippines, 1979-1993

International Nuclear Information System (INIS)

Borras, A.M.

1994-01-01

Among the many practices of radiation sources, the practice of industrial gamma radiography in the country has the most number of reported radiological incidents. During the past fourteen (14) years, from 1979-1993, twenty (20) incidents that have occurred were reported to the Institute. This paper presents the nature and extent of the 20 reported incidents as well as the results of the analysis of why these incidents happened. The results of the analysis showed that the causes of these incidents are mainly human error and equipment failure. Hence, the factors that can minimize or prevent the chance of occurrence and/or recurrence of incidents and in minimizing the hazard in case of radiological incidents are: a) proper training and re-training of personnel; b) proper and regular inspection and maintenance of equipment; c) adequate radiation survey; and d) proper storage and inventory of the radiography sealed sources. (author). 3 refs.; 5 figs.; 1 tab

State and prospects of industrial neutron radiography in Germany

International Nuclear Information System (INIS)

Heidt, H.; Stade, J.

1988-01-01

Although the first neutron radiographies in Germany were made nearly 50 years ago, by Kallmann and Kuhn, this nondestructive testing method has not yet been widely used in industry. The main reason is the lack of mobile, intensive and low-cost neutron sources. Another important aspect is the availability of real-time inspection systems equipped with neutron image amplifiers which will accelerate the test and permit to represent dynamic processes. New applications for mobile neutron sources may be expected in aircraft inspection, in testing fibre-reinforced plastics, in different types of ceramic materials, in the building sector, in corrosion protection as well as with various problems encountered with lubrication agents. (orig.) [de

Implementation of the safety assessment in the practice of industrial radiography

International Nuclear Information System (INIS)

Alfonso Pallarés, C.; Pérez Reyes, Y.

2015-01-01

The CNSN as regulatory authority has regulatory control processes based on regulations, permits, inspections and limitation to ensure the supervision and control of the practice of industrial radiography. On the other hand in the light of the new regulations approved and being implemented such as: Resolution 334/2011 CITMA 'Regulation on Notification and authorization of practices and activities associated with the use of ionizing radiation sources' and Resolution 17 / 2012, Security Guide: Security Assessment Practices and Activities associated with the use of ionizing radiation (recommendatory), it is necessary for compliance with regulatory requirements concerning the safety assessment. Since 2009 it has been applied this experience in different medical practices and industry, providing a systematic and consistent basis, to the safety assessment of all facilities and activities, which has helped increase the confidence that has been achieved an adequate level of security. The work was able to identify that there is a group of barriers operating in the risk reduction in various accident sequences and therefore have a relative importance in risk reduction, recommendations in this regard to improve the program management of safety in the practice of industrial radiography. [es

An alternative approach to industrial radiography

International Nuclear Information System (INIS)

Broadhead, P.

1981-01-01

An alternative to industrial X-ray film for industrial radiography is described. The experimental system uses film containing approximately 35% of the silver in an industrial type film, which makes the film easier to process, and uses high resolution phosphor screens, which improves the absorption of X-ray photons. Those properties that affect image quality, namely contrast, modulation transfer function and granularity, are discussed in detail for both types of system. A study of low contrast detail in radiographs indicates that for noise limited information the experimental system offers a higher quality than industrial X-ray film of similar speed. (author)

High Brightness Neutron Source for Radiography. Final report

International Nuclear Information System (INIS)

Cremer, J.T.; Piestrup, Melvin A.; Gary, Charles K.; Harris, Jack L.; Williams, David J.; Jones, Glenn E.; Vainionpaa, J.H.; Fuller, Michael J.; Rothbart, George H.; Kwan, J.W.; Ludewigt, B.A.; Gough, R.A.; Reijonen, Jani; Leung, Ka-Ngo

2008-01-01

of yield of two orders of magnitude. The first fast neutron radiographic images were obtained using neutron cameras and a new fast neutron generator. These early images demonstrated the feasibility of using fast neutrons for imaging and penetrating thick objects of high density and imaging. Fast neutrons can be used to image low atomic number materials (e.g. plastics, explosives, lubricants and ceramics) that are shielded by high density materials (e.g. lead, tungsten and uranium). Fast neutron radiography could be used as a means to screen weapons for flaws and chemical stability. X-ray radiography can not easily do this. Fast neutron imaging is technically difficult and, consequently, a completely undeveloped market. Two of the generators were designed to have small source size and high brightness, ideal for fast-neutron imaging. With these generators we successfully used two fast neutron cameras: one developed by us, and another developed by a collaborator, Commonwealth Scientific and Industrial Research Organization, CSIRO. We have successfully used these cameras to obtain low resolution images of various objects such as pipe fittings filled with water and other mechanical objects. Higher resolution and contrast images are expected by decreasing the source size and increasing generator yield.

An industrial radiography exposure device based on measurement of transmitted gamma-ray intensity

International Nuclear Information System (INIS)

Polee, C; Chankow, N; Srisatit, S; Thong-Aram, D

2015-01-01

In film radiography, underexposure and overexposure may happen particularly when lacking information of specimen material and hollowness. This paper describes a method and a device for determining exposure in industrial gamma-ray radiography based on quick measurement of transmitted gamma-ray intensity with a small detector. Application software was developed for Android mobile phone to remotely control the device and to display counting data via Bluetooth communication. Prior to film exposure, the device is placed behind a specimen to measure transmitted intensity which is inversely proportional to the exposure. Unlike in using the conventional exposure curve, correction factors for source decay, source-to- film distance, specimen thickness and kind of material are not needed. The developed technique and device make radiographic process economic, convenient and more reliable. (paper)

Industrial radiography with Ir-192 using computed radiographic technique

International Nuclear Information System (INIS)

Ngernvijit, Narippawaj; Punnachaiya, Suvit; Chankow, Nares; Sukbumperng, Ampai; Thong-Aram, Decho

2003-01-01

The aim of this research is to study the utilization of a low activity Ir-192 gamma source for industrial radiographic testing using the Computed Radiography (CR) system. Due to a photo-salbutamol Imaging Plate (I P) using in CR is much more radiation sensitive than a type II film with lead foil intensifying screen, the exposure time with CR can be significantly reduced. For short-lived gamma-ray source like Ir-192 source, the exposure time must be proportionally increased until it is not practical particularly for thick specimens. Generally, when the source decays to an activity of about 5 Ci or less, it will be returned to the manufacturer as a radioactive waste. In this research, the optimum conditions for radiography of a 20 mm thick welded steel sample with 2.4 Ci Ir-192 was investigated using the CR system with high resolution image plate, i.e. type Bas-SR of the Fuji Film Co. Ltd. The I P was sandwiched by a pair of 0.25 mm thick Pb intensifying sere en. Low energy scattered radiations was filtered by placing another Pb sheet with a thickness of 3 mm under the cassette. It was found that the CR image could give a contrast sensitivity of 2.5 % using only 3-minute exposure time which was comparable to the image taken by the type II film with Pb intensifying screen using the exposure time of 45 minutes

Performance evaluation of the conventional Brazilian industries radiation protection in the small industrial gauges and industrial radiography areas

International Nuclear Information System (INIS)

Santos, Joyra Amaral dos

1999-08-01

This works evaluates by punctuation the performance in conventional Brazilian industries radiation protection area which make use of small industrial gauges and industrial radiography. It proposes, procedures for industry self-evaluation, besides a new radiation protection plans pattern for the small industrial gauges area. The data source where inspection reports of Dosimetry Radiation Protection Institute/Nuclear Energy Commission conventional Brazilian industries' radiation protection plans, beyond visitation to the inspection place. The performance evaluation has been realized both in the administrative and operational aspects of the industries. About of 60% of the industries have a satisfactory register control which does not happen to the operational control. The performance evaluation advantage is that industries may self-evaluate, foreseeing Dosimetry Radiation Protection Institute's regulation inspections, correcting its irregularities, automatically improving its services. The number of industries which have obtained satisfactory performance in both areas is below 70%, both in administrative and operational aspects. Such number can be considered a low one as it is radiation protection. The procedures propose in this work aim to improve such a situation. (author)

Routine check and annual maintenance for industrial radiography gamma projector

International Nuclear Information System (INIS)

Shaharudin Sayuti; Abdul Nassir Ibrahim; Sukhri Ahmad; Arshad Yassin; Mohd Junaidi Jaapar; Khairul Anuar Mohd Salleh; Abdul Razak Hamzah

2009-04-01

The main objective of this paper is to share some experience pertaining to gamma projector maintenance programme. In Malaysia there are more than 100 gamma projectors, which need to be maintenance annually. Most of these projectors are Tech-Ops 660 series portable gamma radiography systems, which are used primarily for industrial radiography. The portability feature of the system provides both a safe means of transporting the radioactive source and operating flexibility, particularly useful in areas where access is limited. Generally, the national authorised service centre carries out the annual inspection of this system. In Malaysia, Malaysian Nuclear Agency has been recognised as the National Gamma Projector Maintenance Centre by the Atomic Energy Licensing Board (AELB). In this paper, a brief review of the design and operation is included in the discussion of the maintenance procedure, limitations and improvements of the gamma projector maintenance programme. (author)

Computer radiography - indirect digital radiography

International Nuclear Information System (INIS)

Jezierski, G.

2008-01-01

Implementation of the new European standards for industrial radiography with the use of storage phosphor imaging plates will result in the arousing of interest among numerous laboratories in non-destructive testing with application of the new method of testing to replace conventional radiography used so far, i.e. film radiography. Computer radiography is quite commonly used for medical radiography, where the fundamental problem consists in reduction of the radiation dose during the examination of a patient. However, it must be kept in mind that industrial applications have a little bit different requirements when compared with medical radiography. The article describes only new method for radiographic testing. (author)

Neutron radiography

International Nuclear Information System (INIS)

Bayon, G.

1989-01-01

Neutronography or neutron radiography, a non-destructive test method which is similar in its principle to conventional X-ray photography, presently occupies a marginal position among non-destructive test methods (NDT) (no source of suitable performance or cost). Neutron radiography associated with the ORPHEE reactor permits industrial testing; it can very quickly meet a cost requirement comparable to that of conventional test methods. In 1988, 2500 parts were tested on this unit [fr

Analysis of causes of radiation overexposures for radiation workers in industrial radiography

International Nuclear Information System (INIS)

Mahajan, J.M.; Massand, O.P.

2001-01-01

About 5500 radiation workers are monitored from industrial institutions in our country out of which 3600 radiation workers are working in industrial radiography institutions. These workers have a higher potential of receiving overexposure (equivalent dose 3 10 mSv) due to their nature of work. This paper presents analysis of overexposures and their causes for radiation workers working in industrial radiography institutions during the last seven years. (author)

Overview of Brazilian industrial radiography accidents with cutaneous radiation syndrome

International Nuclear Information System (INIS)

Lima, C.M.A.; Silva, F.C.A. da

2017-01-01

It is well documented that industrial radiography is related to radiological accidents, which makes it the highest potential risk for human health. More than 80 radiological accidents happened in the world that includes 6 Brazilian accidents with Cutaneous Radiation Syndrome. Five of them happened with 192 Ir and one with 60 Co radioactive sources. Nineteen members of the public and 8 radiographers were involved. All of them suffered severe hands and fingers injuries. The Brazilian radiological accident happened in 1985 with 16 persons is analyzed showing causes, consequences, radiation doses and lessons learned. (author)

Digital radiography: study of an alternative technique to conventional radiography

International Nuclear Information System (INIS)

Banchet, J.; Tisseur, D.; Thomas, A.

2009-01-01

Digital radiography, already in use in many industrial applications, appears as a potential alternative technique to conventional radiography in the nuclear field (and more especially to the inspection of welded joints). The advantages of digital radiography are a reduced explosion risk (due to the use of lower energy and activity sources), a lower installation time, a reduced exclusion zone, and the absence of effluents. However, to the contrary of the US case, this technique may not be used in France as it is not referenced in the regulating codes (RCCM, etc.). Areva has launched a R and D study in order to characterize the equivalencies between digital and conventional radiography. First results of this study are given

Industrial radiography with phosphor screens

International Nuclear Information System (INIS)

Broadhead, P.

1981-01-01

An experimental system that comprises a film of low silver content and a pair of high resolution phosphor intensifying screens and a commercial industrial X-ray film of similar speed are compared for image quality. It is concluded that the use of phosphor screens offers an increase in image quality when the information is limited by the graininess or quantum mottle of a radiograph which is frequently the case in practical radiography. (author)

Radiologic accidents in industrial gamma radiography - Brazilian cases; Acidentes radiologicos em gamagrafia industrial - casos brasileiros

Energy Technology Data Exchange (ETDEWEB)

Silva, Francisco Cesar Augusto da [Instituto de Radioprotecao e Dosimetria (IRD), Rio de Janeiro, RJ (Brazil)

1997-12-31

Three severe radiological accidents in industrial gamma radiography happened in Brazil during the period of 1985 to 1988. Five operators and nineteen public people were involved. These accidents caused some injuries in parts of the body, mainly hands and fingers. The main causes were faults in source monitoring, inadequate routine procedures and unknowing of radiation warning symbol by public people. The present paper shows the Brazilian cases of radiological accidents and makes some analysis of them. (author) 1 ref., 1 tab.; e-mail: dasilva at ird.gov.br

INDUSTRIAL RADIOGRAPHY COURSE, INSTRUCTORS' GUIDE. VOLUME 2.

Science.gov (United States)

Texas A and M Univ., College Station. Engineering Extension Service.

INFORMATION RELATIVE TO THE LESSON PLANS IN "INDUSTRIAL RADIOGRAPHY COURSE, INSTRUCTOR'S GUIDE, VOLUME I" (VT 003 565) IS PRESENTED ON 52 INFORMATION SHEETS INCLUDING THE SUBJECTS SHIELDING EQUATIONS AND LOGARITHMS, METAL PROPERTIES, FIELD TRIP INSTRUCTIONS FOR STUDENTS, WELDING SYMBOLS AND SIZES, SAMPLE REPORT FORMS, AND TYPICAL SHIPPING…

Radiation protection program of Petrobras in industrial radiography area

International Nuclear Information System (INIS)

Signorini, M.

1988-01-01

Industrial hygiene has as main purpose the preservation of employees physical integrity when exposed to certain agressive agents. PETROBRAS Industrial hygiene program forecasts preventive policies in several specific fields. For the ionizing radiations area it was developed the ''Radiologic Protection Program'' which also deals with specific actions in industrial radiography jobs. These actions are hereinafter presented. (C.M.) [pt

Use of a neutron guide in industrial neutron radiography

International Nuclear Information System (INIS)

Zaccheo, M.; Berthon, J.; Uzureau, G.; Laporte, A.

1983-01-01

This paper describes the neutron radiography facility associated with the Orphee high flux reactor at the Saclay Nuclear Research Centre. Following a brief background review, the paper deals with: the presentation of the facility, with emphasis on all the mechanical systems involved; description of the control and monitoring console; a non-exhaustive list of the facility's potentialities; the advantages and drawbacks of the use of a neutron guide to carry out industrial neutron radiography. (Auth.)

Industrial radiographies

CERN Multimedia

2005-01-01

The Radiation Protection group wishes to remind CERN staff responsible for contractors performing X-ray inspections on the CERN sites that the firms must apply the legislation in force in their country of origin, in particular with regard to the prevention of risks relating to ionizing radiation. Industrial radiography firms called on to work on the CERN sites must also comply with the rules laid down in CERN's Radiation Safety Manual and be registered in the relevant CERN database. Since CERN is responsible for safety on its own site, a number of additional rules have been laid down for this kind of work, as set out in Radiation Protection Procedure PRP30 https://edms.cern.ch/file/346848/LAST_RELEASED/PRP30.pdf The CERN Staff Member responsible for the contract shall register the company and issue notification that an X-ray inspection is to be performed via the web interface at the following address: http://cern.ch/rp-radio

Overview of Brazilian industrial radiography accidents with cutaneous radiation syndrome

Energy Technology Data Exchange (ETDEWEB)

Lima, C.M.A.; Silva, F.C.A. da, E-mail: dasilva@ird.gov.br [Instituto de Radioproteção e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

2017-07-01

It is well documented that industrial radiography is related to radiological accidents, which makes it the highest potential risk for human health. More than 80 radiological accidents happened in the world that includes 6 Brazilian accidents with Cutaneous Radiation Syndrome. Five of them happened with {sup 192}Ir and one with {sup 60}Co radioactive sources. Nineteen members of the public and 8 radiographers were involved. All of them suffered severe hands and fingers injuries. The Brazilian radiological accident happened in 1985 with 16 persons is analyzed showing causes, consequences, radiation doses and lessons learned. (author)

Discussion of ALTERNATIVE systems for industrial radiography using X-ray films

International Nuclear Information System (INIS)

Vaessen B.; Perdieus, P.; Proegler, H.

1995-01-01

Industrial radiography using X-ray films is an established method of NDE. In the last few years, ''novel developments'' have been put on the market as ''alternatives'' to conventional radiography, as e.g. fluorescent screen/film systems, cost-saving films, wide-latitude films, and storage phosphor films. AGFA as a market leader in the sector of X-ray films for industrial radiography has been testing these alternatives, taking into account image quality, sensitivity, handling in terms of portability, reliability, and the essential functions for NDE: (1) Detection of X-radiation; (2) conversion to optical image; (3) evaluation and validation; (4) documentation and archivation. The advantages and drawbacks, the information transfer capabilities, and the performance from the applications point of view are discussed primarily for fluorescent screen/film systems and storage phophor systems. (orig./MM) [de

Application of neutron radiography in Japan

International Nuclear Information System (INIS)

Kobayashi, M.; Wada, N.; Sekita, J.; Sanno-cho, Ota-ku, Tokyo, Japan)

1983-01-01

The history and the present state of neutron radiography in Japan are reviewed. Three types of neutron sources, namely nuclear reactors, accelerators and radioisotopes are now used. The interests on the application on neutron radiography become greater and greater in the industries, such as atomic energy, aeronautics and space etc. (Auth.)

Factors related to screen-film contact in industrial radiography

International Nuclear Information System (INIS)

Talpe, P.

1985-01-01

The relative importance of screen-film contact for industrial radiography is discussed, and the results are presented of an extensive field devaluation of a new type of vacuum prepacked film-screen combination

Lesson learned from two radiological incidents in industrial radiography in Iran

International Nuclear Information System (INIS)

Samimi, Bijan; Deevband Mohammad, Reza; Kardan Mohammad, Reza; Eshraghi, Ahmad

2006-01-01

This paper discussed two incidents occurred in Iran, follow-up investigations as well as lessons learned. Two Industrial Gamma Radiography Projectors (I.G.R.P.) included Ir-192 source with activities 24 and 30 Curies respectively were stolen. One of them was stolen in an industrial area with high security provision and the other one has been stolen at the home town without any security provision. The lessons learned from these incidents are discussed and the results are proposed as recommendations. Investigations show that the reasons for these incidents are as follows: 1. Insufficient training programs for radiographers. 2. Lack of specific emergency procedure for this type of incident in the company. 3. Not efficient National Emergency Plan for this type of threat. 4. Lack of technical and administrative measures to separate radioactive sources from unauthorized persons. 5. Lack of security plan in the company. 6. Insufficient supervision of Radiation Protection Officer (R.P.O.) or responsible person at the site. (authors)

Lesson learned from two radiological incidents in industrial radiography in Iran

Energy Technology Data Exchange (ETDEWEB)

Samimi, Bijan; Deevband Mohammad, Reza; Kardan Mohammad, Reza; Eshraghi, Ahmad [National Radiation Protection Department (NRPD) Atomic Energy Organization of Iran (AEOI) (Iran, Islamic Republic of)

2006-07-01

This paper discussed two incidents occurred in Iran, follow-up investigations as well as lessons learned. Two Industrial Gamma Radiography Projectors (I.G.R.P.) included Ir-192 source with activities 24 and 30 Curies respectively were stolen. One of them was stolen in an industrial area with high security provision and the other one has been stolen at the home town without any security provision. The lessons learned from these incidents are discussed and the results are proposed as recommendations. Investigations show that the reasons for these incidents are as follows: 1. Insufficient training programs for radiographers. 2. Lack of specific emergency procedure for this type of incident in the company. 3. Not efficient National Emergency Plan for this type of threat. 4. Lack of technical and administrative measures to separate radioactive sources from unauthorized persons. 5. Lack of security plan in the company. 6. Insufficient supervision of Radiation Protection Officer (R.P.O.) or responsible person at the site. (authors)

Human performance analysis of industrial radiography radiation exposure events

International Nuclear Information System (INIS)

Reece, W.J.; Hill, S.G.

1995-01-01

A set of radiation overexposure event reports were reviewed as part of a program to examine human performance in industrial radiography for the US Nuclear Regulatory Commission. Incident records for a seven year period were retrieved from an event database. Ninety-five exposure events were initially categorized and sorted for further analysis. Descriptive models were applied to a subset of severe overexposure events. Modeling included: (1) operational sequence tables to outline the key human actions and interactions with equipment, (2) human reliability event trees, (3) an application of an information processing failures model, and (4) an extrapolated use of the error influences and effects diagram. Results of the modeling analyses provided insights into the industrial radiography task and suggested areas for further action and study to decrease overexposures

6 MeV RF Linac for cargo scanning and industrial radiography

International Nuclear Information System (INIS)

2017-01-01

RF Linac-based X-ray sources are very widely used for cargo-scanning and industrial X-ray radiography applications. A 6 MeV on-axis coupled-cavity S-band RF linac has been designed, developed and tested successfully at Electron Beam Centre, Navi Mumbai. This facility falls under the purview of BARC Safety Council, which has conducted safety reviews and awarded regulatory clearances for the operation of the linac system. This paper outlines the salient features of the 6 MeV linac, its safety aspects and test results. A brief history of regulatory aspects is also presented

Regulations for radiation protection in industrial radiography

International Nuclear Information System (INIS)

1974-01-01

These Regulations specify that responsibility for applying radiation protection regulations in industrial radiography rests with the owner of the establishment who will designate a radiation protection officer to this effect. They provide for the organisation of radiation protection, including the measures to be observed, exposure limits, etc. The competent authority for these questions is the State Institute of Radiation Hygiene [fr

Assessment and prevention of the professional risks in the operations of industrial radiography

International Nuclear Information System (INIS)

Pizzorno, M.; Paul, D.; Coletti, F.; Sari Minodier, I.; Azzopardi, G.; Klemenic, O.; Botta, A.

2006-01-01

Industrial radiography is a nocturnal activity, hazardous and little known; it is among the professions the most exposed to ionizing radiation. This study analyse the doses, received the industrial radiographers, their workplace conditions and organization of their tasks. Dosimetry observations on site, together with calculations using the Mercurad code, allowed mean values for reference doses for all the work (including transport, gammatron manipulation, collimator manipulation, shooting) to be established. These value were integrated into a table entitled 'reference doses' in order to provisionally evaluate the doses received by the operators. Distances for security zone demarcation, so as to forbid access to non exposed personnel during shooting, were evaluated. Assessment of the professional risks for industrial radiography, taking into account all the risks (radiological and others), has been made and is under evaluation. This led to measures for prevention based on the material used (collimator, tripod, gamma-stops), on the organization and the conditions of work (for example, time limits permitting a prior visit to the site and preparation for radiography, suitable scaffolding, sufficient lighting, siting of shootings). These prevention measure will be integrated into the new charter of good practice in industrial radiography in the Provence Alpes Cote d'Azur region (south of France). (authors)

Control of radioactive sources in industry through regulatory inspections

International Nuclear Information System (INIS)

Leocadio, J.C.; Ramalho, A.T.; Pinho, A.S.; Lourenco, M.M.J.; Nicola, M.S.; D'Avila, R.L.; Melo, I.F.; Cucco, A.C.S.

2005-01-01

In Brazil, the applications of ionizing radiation in industry are accomplished about 900 radioactive facilities, which handle approximately 3.000 radiation sources. The control of radioactive sources used in industrial installations authorized by the Brazilian Nuclear Energy Commission (CNEN) is accomplished by Servico de Radioprotecao na Industria Radiativa (SERIR) of the Instituto de Radioprotecao e Dosimetria (IRD), Rio de Janeiro, RJ, Brazil. This service carries out regulatory inspections in the practices of industrial radiography, nuclear gauges, industrial irradiators and oil wells logging. The frequency of inspections depends on the type of practice, ranging from a year to 5 years, depending on the risk involved. This paper presents a brief description of the situation of radiation safety in the use of radioactive sources in the industries of the country. The results obtained with regulatory inspections at industrial installations demonstrate that the conditions of safety and radiation protection in these facilities are satisfactory when compared with the technical regulations, both national and international

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

Energy Technology Data Exchange (ETDEWEB)

Aquino, Josilto Oliveira de

2009-03-15

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

Development of Safety Kit for Industrial Radiography Application

International Nuclear Information System (INIS)

Mohd Noorul Ikhsan Ahmad; Amry Amin Abas

2011-01-01

A safety kit for industrial radiography has been developed. The safety kit that consist of a set of technical rod and various size of base that can be used in radiograph of pipe with diameter between half and one and half inch with utilization of collimator. With the kit, radiographers will not having anymore problem to use collimator in their work. The paper discuss about the technical measures of the safety kit and the importance of introducing it to the industry. (author)

Neutron radiography

International Nuclear Information System (INIS)

Hrdlicka, Z.

1977-01-01

Neutron radiography is a radiographic method using a neutron beam of a defined geometry. The neutron source usually consists of a research reactor, a specialized neutron radiography reactor or the 252 Cf radioisotope source. There are two types of the neutron radiography display system, viz., a system producing neutron radiography images by a photographic process or a system allowing a visual display, eg., using a television monitor. The method can be used wherever X-ray radiography is used except applications in the radiography of humans. The neutron radiography unit at UJV uses the WWR-S reactor as the neutron source and both types of the above mentioned display system. (J.P.)

Applications of neutron radiography for the nuclear power industry

Energy Technology Data Exchange (ETDEWEB)

Craft, Aaron E.; Barton, John P.

2016-11-01

The World Conference on Neutron Radiography (WCNR) and International Topical Meeting on Neutron Radiography (ITMNR) series have been running over 35 years. The most recent event, ITMNR-8, focused on industrial applications and was the first time this series was hosted in China. In China, more than twenty new nuclear power plants are in construction and plans have been announced to increase the nuclear capacity further by a factor of three within fifteen years. There are additional prospects in many other nations. Neutron tests were vital during previous developments of materials and components for nuclear power applications, as reported in this conference series. For example a majority of the 140 papers in the Proceedings of the First WCNR are for the benefit of the nuclear power industry. Included are reviews of the diverse techniques being applied in Europe, Japan, the United States, and at many other centers. Many of those techniques are being utilized and advanced to the present time. Neutron radiography of irradiated nuclear fuel provides more comprehensive information about the internal condition of irradiated nuclear fuel than any other non-destructive technique to date. Applications include examination of nuclear waste, nuclear fuels, cladding, control elements, and other critical components. In this paper, the techniques developed and applied internationally for the nuclear power industry since the earliest years are reviewed, and the question is asked whether neutron test techniques can be of value in development of the present and future generations of nuclear power plants world-wide.

Videoscopic assessment of the maintenance status of gamma radiography exposure containers employed in Brazil

International Nuclear Information System (INIS)

Candeias, J P; Estrada, J J S; Pinho, A S; D'Avila, R L; Ramalho, A T

2007-01-01

Industrial radiography is the most frequent method of non-destructive testing (NDT) used by Brazilian industrial facilities for investigating the material integrity of a test object. In Brazil, industrial radiography employs around 220 x-ray and 290 gamma radiography machines. About 90% of the latter uses iridium ( 192 Ir) sources. The large majority of 192 Ir projectors in operation in Brazil have been in continuous usage for more than 25 years, which means that they are old and worn-out. Usually the majority of accidents concerning gamma radiography occur during the return of the source into the exposure container. Poor maintenance or imperfections of the internal channel of the exposure container can lead to accidental source exposure. In the present work the internal tube of 65 gamma machines from nine Brazilian companies that render gamma radiography services were analysed using an industrial videoscope. The internal images from the projectors were compared with the internal image of an apparatus that had never been used, i.e. has never received a radioactive source. From the 65 machines evaluated, nine showed irregularities of the internal tube. It was also observed that each company follows a different methodology for the maintenance and lubrication of the exposure containers and drive cables

Videoscopic assessment of the maintenance status of gamma radiography exposure containers employed in Brazil.

Science.gov (United States)

Candeias, J P; Estrada, J J S; Pinho, A S; D'Avila, R L; Ramalho, A T

2007-03-01

Industrial radiography is the most frequent method of non-destructive testing (NDT) used by Brazilian industrial facilities for investigating the material integrity of a test object. In Brazil, industrial radiography employs around 220 x-ray and 290 gamma radiography machines. About 90% of the latter uses iridium ((192)Ir) sources. The large majority of (192)Ir projectors in operation in Brazil have been in continuous usage for more than 25 years, which means that they are old and worn-out. Usually the majority of accidents concerning gamma radiography occur during the return of the source into the exposure container. Poor maintenance or imperfections of the internal channel of the exposure container can lead to accidental source exposure. In the present work the internal tube of 65 gamma machines from nine Brazilian companies that render gamma radiography services were analysed using an industrial videoscope. The internal images from the projectors were compared with the internal image of an apparatus that had never been used, i.e. has never received a radioactive source. From the 65 machines evaluated, nine showed irregularities of the internal tube. It was also observed that each company follows a different methodology for the maintenance and lubrication of the exposure containers and drive cables.

Videoscopic assessment of the maintenance status of gamma radiography exposure containers employed in Brazil

Energy Technology Data Exchange (ETDEWEB)

Candeias, J P [IME, Military Institute of Engineering, Praca Gal Tiburcio 80, Praia Vermelha, Rio de Janeiro, 22290-270 (Brazil); Estrada, J J S [IME, Military Institute of Engineering, Praca Gal Tiburcio 80, Praia Vermelha, Rio de Janeiro, 22290-270 (Brazil); Pinho, A S [Institute of Radioprotection and Dosimetry (IRD/CNEN), Avenida Salvador Allende, PO Box 37750, Rio de Janeiro, 22780-160 (Brazil); D' Avila, R L [Institute of Radioprotection and Dosimetry (IRD/CNEN), Avenida Salvador Allende, PO Box 37750, Rio de Janeiro, 22780-160 (Brazil); Ramalho, A T [Institute of Radioprotection and Dosimetry (IRD/CNEN), Avenida Salvador Allende, PO Box 37750, Rio de Janeiro, 22780-160 (Brazil)

2007-03-01

Industrial radiography is the most frequent method of non-destructive testing (NDT) used by Brazilian industrial facilities for investigating the material integrity of a test object. In Brazil, industrial radiography employs around 220 x-ray and 290 gamma radiography machines. About 90% of the latter uses iridium ({sup 192}Ir) sources. The large majority of {sup 192}Ir projectors in operation in Brazil have been in continuous usage for more than 25 years, which means that they are old and worn-out. Usually the majority of accidents concerning gamma radiography occur during the return of the source into the exposure container. Poor maintenance or imperfections of the internal channel of the exposure container can lead to accidental source exposure. In the present work the internal tube of 65 gamma machines from nine Brazilian companies that render gamma radiography services were analysed using an industrial videoscope. The internal images from the projectors were compared with the internal image of an apparatus that had never been used, i.e. has never received a radioactive source. From the 65 machines evaluated, nine showed irregularities of the internal tube. It was also observed that each company follows a different methodology for the maintenance and lubrication of the exposure containers and drive cables.

Radiography at CERN

CERN Multimedia

HSE Unit

2014-01-01

What is industrial radiography? It is a non-destructive method with a wide variety of applications, such as inspecting the quality of a weld. It uses high-energy radioactive sources or an X-ray generator.   Is this inspection technique used at CERN? Yes, it is widely used at CERN by the EN-MME Group, which outsources the work to one or more companies, depending on the workload. Is it possible to carry out radiography anywhere at CERN? Yes, it is possible to carry out radiography in any building/accelerator/experiment area at CERN (including in areas which are not normally subject to radiological hazards). When is radiography carried out? It normally takes place outside of working hours (7 p.m. to 6 a.m.). How will I know if radiography is taking place in my building? If this activity is planned in a CERN building, notices will be affixed to all of its main entrance doors at least 24 hours in advance. What are the risks? There is a risk of exposure to very high levels of radiation, dep...

Methodology for digital radiography simulation using the Monte Carlo code MCNPX for industrial applications

International Nuclear Information System (INIS)

Souza, E.M.; Correa, S.C.A.; Silva, A.X.; Lopes, R.T.; Oliveira, D.F.

2008-01-01

This work presents a methodology for digital radiography simulation for industrial applications using the MCNPX radiography tally. In order to perform the simulation, the energy-dependent response of a BaFBr imaging plate detector was modeled and introduced in the MCNPX radiography tally input. In addition, a post-processing program was used to convert the MCNPX radiography tally output into 16-bit digital images. Simulated and experimental images of a steel pipe containing corrosion alveoli and stress corrosion cracking were compared, and the results showed good agreement between both images

Instant radiography: a computerized support system for industrial radiographers

International Nuclear Information System (INIS)

Taiyus, M.K.; Sadique, J.

1995-08-01

This work describes an approach for systematic collection of information, organization of these information to create a database, which is based to create a user friendly software ( Instant Radiography). It helps to reduce the vagaries of radiographic practice and reduces the number of trials needed to get good radiographs. This software considers the interrelated and dependent parameters of radiography, e.g., quality of radiation, properties of films, source-to-film distance(SFD), processing conditions etc. and provides precise numerical values for exposure time and other parameters needed for field work. (author), 2 figs., 15 refs

Regulatory inspection: a powerful tool to control industrial radioactive sources

International Nuclear Information System (INIS)

Silva, F.C.A. da; Leocadio, J.C.; Ramalho, A.T.

2008-01-01

An important contribution for Brazilian development, especially for the quality control of products, is the use of radiation sources by conventional industries. There are in Brazil roughly 3,000 radioactive sources spread out among 950 industries. The main industrial practices involved are: industrial radiography, industrial irradiators, industrial accelerators, well logging petroleum and nuclear gauges. More than 1,800 Radiation Protection Officers (RPOs) were qualified to work in these practices. The present work presents a brief description of the safety control over industrial radioactive installations performed by the Brazilian Regulatory Authority, i.e. the National Commission of Nuclear Energy (CNEN). This paper also describes the national system for radiation safety inspections, the regulation infrastructure and the national inventory of industrial installations. The inspections are based on specific indicators, and their periodicity depends on the risk and type of installation. The present work discusses some relevant aspects that must be considered during the inspections, in order to make the inspections more efficient in controlling the sources. One of these aspects regards the evaluation of the storage place for the sources, a very important parameter for preventing future risky situations. (author)

Design and manufacture of densitometer using in industrial radiography

International Nuclear Information System (INIS)

Nguyen Duc Huyen; Do Minh Duc; Vu Tien Ha; Dang Thanh Dung; Nguyen Do Kien

2016-01-01

Densitometer is a small device used to determine the darkness degree of radiography film. For improving the quality of the image on the film densitometer is indispensable equipment in sector related to the image, especially in the field of industrial imaging, radiographic. In Vietnam there are hundreds of densitometer devices, distributed to over 60 companies performing work on NDT sector and other companies. However, due to lack of maintenance, calibration and repair, many devices have been damaged, or unstable operation without any technical supports from the manufacturers. Up to now, Vietnam does not have any manufacturer (domestic and/or foreign) to research and development of the Densitometer. For these reasons, the scientists of Centre for Non-destructive Evaluation (NDE) with support from Vietnam Atomic Energy Institute (VINATOM) have successfully researched and manufactured the Densitometer using in industrial radiography in 2015.The equipment has been tested in practice and showed stable performance, measurement accuracy: ± 1% 0.02D; darkness range of film: 0.00 to 4.00D; repeated measurement values : ± 0.02D. The device meets ASTM 1079-00 standard for densitometer in industry. Especially, thanks to successful domestic manufacturing, the price of the device is only 60 % compared to the same imported products. (author)

A guide to collect data from abnormal events in industrial radiography

International Nuclear Information System (INIS)

Martins, M.M.; Silva, F.C.; Tahuata, L.

1996-01-01

The review of abnormal radiological events provides important information to evaluate the reasons of their cause. The IAEA and other institutions have dedicated special attention to this subject, studying mainly radiological accidents that affected individuals from the public and workers exposed. According to UNSCEAR, industrial radiography and other radiographic techniques are responsible for the great number of overexposure events. This paper can be used by health physicists and other professionals as a guide to extract the most important information related to abnormal events that happen in industrial radiography. This guide was used in 1992 in the information registration data base (1976-1992) of the Brazilian Nuclear Energy Commission (CNEN), where 175 events were identified with a minimal number of information for the analysis. The collected data is presented too. (authors). 6 refs., 1 ill

Industrial applications at the new cold neutron radiography and tomography facility of the HMI

International Nuclear Information System (INIS)

Kardjilov, N.; Hilger, A.; Manke, I.; Strobl, M.; Treimer, W.; Banhart, J.

2005-01-01

The new cold neutron radiography and tomography facility at the Hahn-Meitner-Institut Berlin is suited for the investigation of components and materials from different industrial fields. The high-flux measuring position of the facility allows real-time imaging of fast dynamical processes. Cold neutrons interact stronger with the matter compared to thermal neutrons, which leads to a much better radiography contrast. Some examples of different industry applications like investigations on discharging of a Lithium battery or on oil sediments in a vent pipe are presented

Factors related to the Ecran-Film contact in the industrial radiography

International Nuclear Information System (INIS)

Raets, G.

1983-01-01

The relative importance of ecram-film for industrial radiographies is discussed, and the results are presented after an extensive evaluation of a new combination type of ecran-film prepared in a vacuum. (E.G.) [pt

Establishing local rules for industrial radiography practice using radionuclides

International Nuclear Information System (INIS)

Ambrosio, N.

2012-04-01

Industrial Radiograph used for non-destructive testing of material or equipment constitutes one of the most important applications of radiation sources. Non-destructive testing (NDT) provides a means of verifying the physical integrity of equipment and structures such as vessels, pipes, welded joints, castings and other devices. The physical integrity of such equipment and structures affects not only the safety and quality of the products but also the protection of workers, the public and the environment, as operator of these devises could result in accidents. The development and maintenance of safety culture in an operating organization has to cover management systems, policies, responsibilities, procedures and organizational arrangements.The essence is to control radiation hazard, optimize radiation protection to prevent or reduce exposures and mitigate the consequences of accidents and incidents. To achieve high degree of professionalism, appropriate national and organizational infrastructure is required in addition to ensure effective training of workers, compliance with safety culture and effective quality control. Therefore, this report presents a model Local Rules and procedures necessary for the safe operation of Industrial Radiography devises in order to protect worker, the public and the environment. The model has been developed from examples from published reports. (author)

Digital computed radiography in industrial X-ray testing

International Nuclear Information System (INIS)

Osterloh, K.; Onel, Y.; Zscherpel, U.; Ewert, U.

2001-01-01

Computed radiography is used for X-ray testing in many industrial applications. There are different systems depending on the application, e.g. fast systems for detection of material inhomogeneities and slower systems with higher local resolution for detection of cracks and fine details, e.g. in highly stressed areas or in welded seams. The method is more dynamic than film methods, and digital image processing is possible during testing [de

Non destructive testing and neutron radiography in 1994

International Nuclear Information System (INIS)

Bayon, G.

1994-01-01

Neutron radiography has been considered for a long time as a promising technique; however it plays a minor part in the world of non destructive testing today, due to the lack of suitable neutron sources and lack of new industrial applications. This paper reviews the present status of neutron sources, neutron radiography activities, especially in France (such as the neutron-capture-issued secondary radiation spectrometry), in nuclear, aerospace, aeronautical and metallurgical sectors, and the last applications of neutron dynamic imaging. 9 refs

A radiological health study of industrial gamma radiography in Canada

International Nuclear Information System (INIS)

1979-05-01

As an occupational group, industrial radiographers receive radiation doses second only to reactor workers. This report is a result of a study carried out to research the causes for this relatively high dose and determine if and how it can be improved. The data presented herein were obtained from questionnaires and field visits to organizations involved in gamma radiography and from the Canadian National Dose Registry. Some applications of radiography such as pipeline work give rise to higher than average doses. When all safety measures are conscientiously aplied, the doses are reasonalbe. However, ignorance, carelessness and indifference account for much unnecessary exposure to radiation. (Auth)

New radiation protection concept as important safety factor of industrial radiography

International Nuclear Information System (INIS)

Pavlovic, R.; Pavlovic, S.

1998-01-01

Industrial radiography is a method for non destructive testing of homogeneity of various materials based on different absorption of radiation in different material. X and γ radiation are the most often used. Detrimental effects of radiation are observed since its discovery. In order to prevent harmful effects of radiation without unduly limitations of its use, International Commission on Radiological Protection in collaboration with International Atomic Energy Agency have developed International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources, Safety Series No 115, adopted in 1996. based on ICRP recommendations from 1991. Besides a lot of changes in radiation protection concept and philosophy, decrement of annual dose limits for occupational exposure from 50 to 20 mSv. (author)

Nuclear Malaysia Plasma Focus Device as a X-ray Source For Radiography Applications

International Nuclear Information System (INIS)

Rokiah Mohd Sabri; Abdul Halim Baijan; Siti Aiasah Hashim; Mohd Rizal Mohd Chulan; Wah, L.K.; Mukhlis Mokhtar; Azaman Ahmad; Rosli Che Ros

2013-01-01

A 3.375 kJ plasma focus is designed to operate at 13.5 kV for the purpose of studying x-ray source for radiography in Argon discharge. X-rays is detected by using x-ray film from the mammography radiographic plate. The feasibility of the plasma focus as a high intensity flash x-ray source for good contrast in radiography image is presented. (author)

Radiation protection at industrial radiography in Germany exposures and unusual events

International Nuclear Information System (INIS)

Czarwinski, R.; Haeusler, U.; Frasch, G.

2006-01-01

In the Federal Republic of Germany safety related events in the use and transportation of radioactive materials as well as in the operation of accelerators are registered. The analysis of these events reveals their causation and allows this conclusions on avoidable errors. In this paper, a special insight is given into events in the field of gamma radiography which is a technical application of ionising radiation for non destructive testing of materials. Conclusions from analysis are drawn. In addition, the occupational radiation exposure of workers is presented taking into account that industrial radiography is performed under particular working conditions with different risks. (orig.)

Dose estimation in the crystalline lens of industrial radiography personnel using Monte Carlo Method

International Nuclear Information System (INIS)

Lima, Alexandre Roza de

2014-01-01

The International Commission on Radiological Protection, ICRP, in its publication 103, reviewed recent epidemiological evidence and indicated that, for the eye lens, the absorbed dose threshold for induction of late detriment is around 0.5 Gy. On this basis, on April 21, 2011, the ICRP recommended changes to the occupational dose limit in planned exposure situations, reducing the eye lens equivalent dose limit from 150 mSv to 20 mSv per year, on average, during the period of 5 years, with exposure not to exceed 50 mSv in a single year. This paper presents the dose estimation to eye lens, H p (10), effective dose and doses to important organs in the body, received by industrial gamma radiography workers, during planned or accidental exposure situations. The computer program Visual Monte Carlo was used and two relevant scenarios were postulated. The first is a planned exposure situation scenario where the operator is directly exposed to radiation during the operation. 12 radiographic exposures per day for 250 days per year, which leads to an exposure of 36,000 seconds or 10 hours per year were considered. The simulation was carried out using the following parameters: a 192 Ir source with 1.0 TBq of activity, the source/operator distance varying from 5 m to 10 m at three different heights of 0.2 m, 1.0 m and 2.0 m. The eyes lens doses were estimated as being between 16.9 mSv/year and 66.9 mSv/year and for H p (10) the doses were between 17.7 mSv/year and 74.2 mSv/year. For the accidental exposure situation scenario, the same radionuclide and activity were used, but in this case the doses were calculated with and without a collimator. The heights above ground considered were 1.0 m, 1.5 m e 2.0 m, the source/operator distance was 40 cm and, the exposure time 74 seconds. The eyes lens doses, for 1.5 m, were 12.3 mGy and 0.28 mGy without and with a collimator, respectively. Three conclusions resulted from this work. The first was that the estimated doses show that the new

Application of digital image processing to industrial radiography

International Nuclear Information System (INIS)

Bodson; Varcin; Crescenzo; Theulot

1985-01-01

Radiography is widely used for quality control of fabrication of large reactor components. Image processing methods are applied to industrial radiographs in order to help to take a decision as well as to reduce costs and delays for examination. Films, performed in representative operating conditions, are used to test results obtained with algorithms for the restauration of images and for the detection, characterisation of indications in order to determine the possibility of an automatic radiographs processing [fr

Neutron radiography, techniques and applications

International Nuclear Information System (INIS)

Domanus, J.C.

1987-10-01

After describing the principles of the ''in pool'' and ''dry'' installations, techniques used in neutron radiography are reviewed. Use of converter foils with silver halide films for the direct and transfer methods is described. Advantages of the use of nitrocellulose film for radiographying radioactive objects are discussed. Dynamic imaging is shortly reviewed. Standardization in the field of neutron radiography (ASTM and Euratom Neutron Radiography Working Group) is described. The paper reviews main fields of use of neutron radiography. Possibilities of use of neutron radiography at research reactors in various scientific, industrial and other fields are mentioned. Examples are given of application of neutron radiography in industry and the nuclear field. (author)

Industrial Radiography: Principle and Practical

International Nuclear Information System (INIS)

Abdul Nassir Ibrahim; Azali Muhammad; Ab. Razak Hamzah; Abd. Aziz Mohamed; Mohamad Pauzi Ismail

2008-01-01

The successful and effectiveness of radiography method as a tool to increase quality level and safety of the engineering system and processing plants depend with the level of radiographer knowledge as service provider and also as supervisor. This book was published as effort several local experts to give their knowledge, theory and practical related to radiography technique to the involved public directly or indirectly. This book started with basic physic knowledge that becomes a root to radiography technology. Then, followed by discussion on tools and device that used in radiography work including x-ray machine, gamma projector, film, dark room, and others. Each aspect of radiograph quality also mentioned here to guide the reader on how to produce good radiograph that filled the specification wanted. The good radiograph does not mean anything if it failed to be interpreted correctly. Because of that, this book also explain how to choose good radiograph that qualified to be interpreted and after that how interpretation and evaluation process of object quality inspected was implemented based on image digestion that showed in radiograph. Several code and standard that usually applied in this country also will be referred as well for this work.

Preliminary Development of Conductivity based Test Method for Industrial Radiography Film Developer Solution

International Nuclear Information System (INIS)

Zainuddin, N.S.; Manah, N.S.A.; Khairul Anuar Mohd Salleh; Noorhazleena Azaman

2015-01-01

The strength of industrial radiography film developer solution is one of the most important aspects in radiography film processing. The developer solution reacts with the exposed film to visualize the latent image through chemical-film reaction. As the developer is repeatedly used, the strength decreases until a point where it cannot yield the required film optical density value. This work attempts to investigate the developer solution strength through its conductivity. Obtained data are cross correlated to the required industrial radiography optical density range. Through the experiment, the conductivity of the developer solution decreased as the number of the film processed increase. Thus, the desired optical density of the film cannot be achieved. The conductivity of developer is measured and recorded at interval of six films developed. The optical density of every film is recorded to analyze the change in optical density as the conductivity decreases. Through the procedure, it is suggested that as the conductivity decreases, the optical density of film decreased. Ultimately, the strength level of the developer solution can be determined. (author)

Neutron radiography at the HFR Petten

International Nuclear Information System (INIS)

Markgraf, J.F.W.

1990-03-01

This report contains the five papers on neutron radiography activities at the Petten High Flux Reactor (HFR) presented at the Third World Conference on Neutron Radiography which was held in May 1989 in Osaka, Japan. In addition, a survey on neutron radiography in Europe for industry and research as presented at the SITEF NDT symposium 1989 on European Advances in Non-Destructive Testing, held in Toulouse/France in October 1989 is included. The papers compiled here are concerned with: the neutron radiography services available in Petten; the experience with and applications of neutron radiography at Petten; image evaluation and analysis techniques at Petten; the practical utilization of nitrocellulose film in neutron radiography in Europe; an introduction into the basic principles of neutron radiography; an overview of the neutron radiography facilities in Europe for industry and research; and a survey of typical applications of neutron radiography in industry, research and sciences. It is the intention of this compilation to provide a comprehensive overview of the present Petten activities and European facilities in this young and promising field of non-destructive testing of materials and components from the nuclear and the non-nuclear industries and research organizations, and from the sciences

Which technologies to replace gamma radiography?

International Nuclear Information System (INIS)

Zani-Demange, M.L.; Chauveau, D.

2012-01-01

Gamma radiography with iridium source is largely used in the industrial sector for the control of welds, tubes and pressure vessels as well as for monitoring corrosion. Hazards due to the handling of ionizing radiation sources (Ir 192 ) and constraints due to a more and more demanding regulations call for alternative methods. The French 'Institut de soudure' has led a 4-year long study (Alter-X project) and has identified 3 alternative methods for the iridium gamma radiography: -) the TOFD (Time Of Flight Diffraction) which is based on the analysis of the diffraction of ultrasound waves on the edges of defects; -) phased array ultrasound which is based on a series of elementary sensors that can be handled in an individual manner by specific electronics, the sweeping is no more manual but electronic and enables the operator to localize and size defects deep under the surface; -) digit radiography that is a common radiography in which the film is replaced by a re-usable phosphorus screen that is more sensitive and can be easily digitalized and has no need for a chemical treatment to be read. Digit radiography used with Se 75 (another gamma emitter) gives comparable or even better results than with Ir 192 but with a dose rate cut by half at least. (A.C.)

Comparative study between computed radiography and conventional radiography

International Nuclear Information System (INIS)

Noorhazleena Azaman; Khairul Anuar Mohd Salleh; Sapizah Rahim; Shaharudin Sayuti; Arshad Yassin; Abdul Razak Hamzah

2010-01-01

In Industrial Radiography, there are many criteria that need to be considered based on established standards to accept or reject the radiographic film. For conventional radiography, we need to consider the optical density by using the densitometer when viewing the film on the viewer. But in the computed radiography (CR) we need to evaluate and performed the analysis from the quality of the digital image through grey value. There are many factors that affected the digital image quality. One of the factors which are affected to the digital image quality in the image processing is grey value that related to the contrast resolution. In this work, we performed grey value study measurement on digital radiography systems and compared it with exposed films in conventional radiography. The test sample is a steel step wedge. We found out the contrast resolution is higher in Computed Radiography compared with Conventional Radiography. (author)

Introduction to industrial radiography

International Nuclear Information System (INIS)

Abdul Nassir Ibrahim; Azali Muhammad; Ab. Razak Hamzah; Abd. Aziz Mohamed; Mohamad Pauzi Ismail

2008-01-01

For the first topic in this book, more on introduction to nondestructive testing, also a little bit on another technique such as magnetic testing, liquid penetrated, ultrasonic testing and others. This book mentions more on radiographic testing and for that, more details on this topic such as history, definition and devices that use in this technique. This radiography testing firstly started with the discovering of x-ray by Wilhelm Roentgen (1895). So, on 1913, David Coolidge successfully invented and developed x-ray tube that could made x-ray more intensified and produced highly penetration forces. Radiography in Malaysia firstly started two years after the discovery made by Wilhelm Roentgen when one hospital here used the x-ray machine for medical purposes. Besides using x-ray, radiography also used gamma rays, and for these purpose, they used Co-60 and Ir-192. Now, more company based on NDT established to provide a service on inspection pipe and others. For filled these requirement, radiographer must take an exam to make them expert and trained well to work in this field. There is no advantage using this technique or other technique. So that's why this book was published to make people understand what is radiographic testing truly.

Progress in digital radiography

International Nuclear Information System (INIS)

Cappelle, A.

2016-01-01

Because of its practical aspect digital radiography is more and more used in the industrial sector. There are 2 kinds of digital radiography. First, the 'computed radiography' that uses a photon-stimulated screen, and after radiation exposure this screen must be read by an analyser to get a digit image. The second type is the 'direct radiography' that allows one to get a digit radiograph of the object directly. Digital radiography uses the same radioactive nuclides as radiography with silver films: cobalt, iridium or selenium. The spatial resolution of digital radiography is less good than with classical silver film radiography but digital radiography offers a better visual contrast. (A.C.)

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)

New developments in radiography. An overview

International Nuclear Information System (INIS)

Berger, H.; Orphan, V.

1983-01-01

Techniques for radiographic inspection are undergoing change. Changes in X-ray sources include higher voltage and current, pulse techniques, smaller focal spots, portability, ease-of-use, and high reliability. Detector improvements include better films, screens and scintillators, real-time methods, electrostatic methods and solid state detectors. We now use many radiation for radiography (X-rays, gamma rays, neutrons and charged particles) and can process radiographic information to accomplish such things as image enhancement, tomography and digital radiography. In this review, the authors discuss some of these developments, many of which have not been applied - or widely applied in the nuclear industry

Preliminary results from the application of risk matrix method for safety assessment in industrial radiography

International Nuclear Information System (INIS)

Lopez G, A.; Cruz, D.; Truppa, W.; Aravena, M.; Tamayo, B.

2015-09-01

Although the uses of ionizing radiation in industry are subject to procedures that provide a high level of safety, experience has shown that equipment failure, human errors, or the combination of both that can trigger accidental exposures may occur. Traditionally, the radiation safety checks whether these industrial practices (industrial radiography, industrial irradiators, among others) are sufficiently safe to prevent similar accidental exposures already occurred, so that becomes dependent on the published information and not always answers questions like: What other events can occur, or what other risks are present? Taking into account the results achieved by the Foro Iberoamericano de Organismos Reguladores Radiologicos y Nucleares, its leading position in the use of techniques of risk analysis in radioactive facilities and the need to develop a proactive approach to the prevention of accidents arising from the use of ionizing radiations in the industry, it intends to apply the risk analysis technique known as Risk Matrix to a hypothetical reference entity for the region in which industrial radiography is performed. In this paper the results of the first stage of this study are shown, that is the identification of initiating events (IE) and barriers that help mitigate the consequences of such IE, so that can appreciate the applicability of this method to industrial radiography services, to reduce the risk to acceptable levels. The fundamental advantage associated with the application of this methodology is that can be applied by the professionals working in the service and identifies specific weaknesses that from the point of view of safety there, so they can be prioritized resources depending on risk reduction. (Author)

Quality assurance procedure for functional performance of industrial gamma radiography exposure devices

International Nuclear Information System (INIS)

Kannan, R.; Yadav, R.K.; Rajoo Kumar; Bhatt, B.C.; Sivaraman, G.; Nandkumar, A.N.

2003-05-01

An Industrial Gamma Radiography Exposure Device (IGRED) consists of various moving parts and accessories and wear and tear take place often. This may increase the possibility of radiation incidents and result in avoidable radiation exposure. Quality assurance tests of the equipment for functional performance plays a major role in ensuring that the exposure device and its accessories perform their intended functions and satisfy radiation safety requirements to avert potential exposures to operators. Therefore, in India it is practiced as mandatory requirement that each IGRED is tested for its functional performance and only after ascertaining that features of operational safety are satisfactory, loading of the source into the radiography exposure device can be permitted. This procedure which is being. practiced since the late 1970s, has contributed significantly towards the safe use of IGREDs and minimising the occurrence of radiation accidents. The purpose of this document is to highlight the importance of periodic functional performance check of each IGRED as per the checklist for the testing procedures. It is also proposed to entrust this activity to accredited laboratories, which have the necessary infrastructure to carry out this activity. The prerequisites for accreditation of such laboratories to carry out this activity and the testing procedures to be adopted for checking the functional performance of various models of IGREDs used in this country are given in this report. (author)

Application of image processing methods to industrial radiography

International Nuclear Information System (INIS)

Goutte, R.; Odet, C.; Tuncer, T.; Bodson, F.; Varcin, E.

1985-01-01

This study was carried out with the financial support of the Commission of the European Communities as part of the CECA research program comprising of IRSID, INSA de Lyon and the Framatome and Creusot Loire companies. Its purpose was to evaluate the possibility of using digital enhancement of radiographic images to improve defect visibility in industrial radiography, thereby providing assistance in defect detection and a method for automatic analysis of radiographs. This paper provides full results obtained from work on digital processing of radiographs showing real and artificial defects. Furthermore, work on simulated automatic defect detection is also presented. 2 refs

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

International Nuclear Information System (INIS)

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

2018-01-01

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

Assessment of the Main Deviations Found during Regulatory Inspections in Industrial Gamma Radiography in Argentina

International Nuclear Information System (INIS)

Alonso Jimenez, M.T.; Ermacora, M.G.

2011-01-01

The present paper shows the regulatory work made through inspections concerning radiation safety and security in the area of industrial gamma radiography. An account is shown of the items which should be available in the storage facility where the equipment and radioactive sources are placed as well as in site radiography and which are required to the users of the equipment meant for this practice, in order to ensure compliance with the regulations in force. The objective of this paper is to assess the most frequent deviations to the regulatory standards found during this type of inspections, such as lack of complete and operable radiation protection equipment, lack of available elements bound to act in case of emergency, no delimitation of controlled areas, gamma radiography equipment stored in unlocked position, wear gauge unavailable, record of movements of equipment and radioactive sources not updated, anomalous monthly or annual personal dose values, among the main findings. In particular, in connection with dose reports, some cases of occupational exposed workers exceeding the annual dose limits or investigation levels are highlighted. In addition, the explanations provided by the person responsible for radiation protection of companies in regard to the possible causes or circumstances which might have given rise to such dose values, the conclusions reached and the preventive and corrective measures implemented by these companies are analysed. Finally, an assessment of the annual dose distributions of the occupational exposed workers concerned with this kind of practice in the period 2004-2007 is shown. As a conclusion, the relevance of these deviations according to degradation in safety and security performance and the role of the regulatory work as a promoter of the implementation of safety culture will be emphasized. (authors)

Assessment of the main deviations found during regulatory inspections in industrial gamma radiography in Argentina

International Nuclear Information System (INIS)

Alonso Jimenez, Maria T.; Ermacora, Marcela

2008-01-01

The present paper shows the regulatory work made through inspections concerning radiation safety and security in the area of industrial gamma radiography. An account is shown of the items which should be available in the storage facility where the equipment and radioactive sources are placed as well as in site radiography and which are required to the users of the equipment meant for this practice, in order to ensure compliance with the regulations in force. The objective of this paper is to assess the most frequent deviations to the regulatory standards found during this type of inspections, such as lack of complete and operable radiation protection equipment, lack of available elements bound to act in case of emergency, no delimitation of controlled areas, gamma radiography equipment stored in unlocked position, wear gauge unavailable, record of movements of equipment and radioactive sources not updated, anomalous monthly or annual personal dose values, among the main findings. In particular, in connection with dose reports, some cases of occupational exposed workers exceeding the annual dose limits or investigation levels are highlighted. In addition, the explanations provided by the person responsible for radiation protection of companies in regard to the possible causes or circumstances which might have given rise to such dose values, the conclusions reached and the preventive and corrective measures implemented by these companies are analysed. Finally, an assessment of the annual dose distributions of the occupational exposed workers concerned with this kind of practice in the period 2004-2007 is shown. As a conclusion, the relevance of these deviations according to degradation in safety and security performance and the role of the regulatory work as a promoter of the implementation of safety culture will be emphasized. (author)

Performance evaluation of the conventional Brazilian industries radiation protection in the small industrial gauges and industrial radiography areas; Sistema de avaliacao de desempenho em radioprotecao das industrias convencionais brasileiras nas areas de medidores nucleares e radiografia industrial

Energy Technology Data Exchange (ETDEWEB)

Santos, Joyra Amaral dos

1999-08-01

This works evaluates by punctuation the performance in conventional Brazilian industries radiation protection area which make use of small industrial gauges and industrial radiography. It proposes, procedures for industry self-evaluation, besides a new radiation protection plans pattern for the small industrial gauges area. The data source where inspection reports of Dosimetry Radiation Protection Institute/Nuclear Energy Commission conventional Brazilian industries' radiation protection plans, beyond visitation to the inspection place. The performance evaluation has been realized both in the administrative and operational aspects of the industries. About of 60% of the industries have a satisfactory register control which does not happen to the operational control. The performance evaluation advantage is that industries may self-evaluate, foreseeing Dosimetry Radiation Protection Institute's regulation inspections, correcting its irregularities, automatically improving its services. The number of industries which have obtained satisfactory performance in both areas is below 70%, both in administrative and operational aspects. Such number can be considered a low one as it is radiation protection. The procedures propose in this work aim to improve such a situation. (author)

Consideration of sky-shine radiation effects for the development of Korean regulatory guidance about industrial radiography

International Nuclear Information System (INIS)

Yong Ki Chi; Bokyun Seo; Wantae Kim

2015-01-01

Although most of the sky-shine radiation levels in industrial radiography are below regulatory limits, sky-shine radiation could make a valuable contribution to the total radiation level near shielding facility with little shielding and open field without shielding. Therefore sky-shine radiation should be thoroughly predicted and supervised with the ALARA principle. In this study, we simulated sky-shine radiation for mobile irradiators using MCNP and newly suggested the equation for calculating sky-shine radiation. Also these results were applied to developing Korean regulatory guidance about industrial radiography and to recommending the requirement of the facility design, controlled or supervised area at work places. (author)

An industrial radiation source for food processing

International Nuclear Information System (INIS)

Sadat, R.

1986-01-01

The scientific linacs realized by CGR MeV in France have been installed in several research centers, the medical accelerators of CGR MeV have been installed in radiotherapy centers all over the world, and the industrial linacs have been used for radiography in heavy industries. Based on the experience for 30 years, CGR MeV has realized a new industrial radiation source for food processing. CARIC is going to install a new machine of CGR MeV, CASSITRON, as the demand for radiation increased. This machine has been devised specially for industrial irradiation purpose. Its main features are security, simplicity and reliability, and it is easy to incorporate it into a production line. The use of CASSITRON for food industry, the ionizing effect on mechanically separated poultry meat, the capital and processing cost and others are explained. Only 10 % of medical disposable supplies is treated by ionizing energy in France. The irradiation for food decontamination, and that for industrial treatment are demanded. Therefore, CARIC is going to increase the capacity by installing a CASSITRON for sterilization. The capital and processing cost are shown. The start of operation is expected in March, 1986. At present, a CASSITRON is being installed in the SPI food processing factory, and starts operation in a few weeks. (Kako, I.)

The application and development of radiography technology based on x-ray

Science.gov (United States)

Chen, Hao; Xu, Zhou; Li, Ming

2009-07-01

Modern Radiography technology was combined with radiation physics and modern imaging processing, which was an important branch of information obtainment and processing. We can get the inside information of the object, by the X ray's attenuation when the ray penetrated the object, and depending on the computer's fast processing, we can see the slice imaging of the object. Computerized Tomography, Computerized Laminography, and Digital Radiography were important parts in Radiography. The institute of applied electronics, CAEP in the research of intense radiation had developed several advanced radiation sources and some advanced radiography imaging systems, for example, S-band small spot linear accelerator, full solid state modulator, C-band linear accelerator, high energy Tera-hertz radiation source and CT technology based on cone beam, DR technology, CL Technology etc. Such imaging systems had been applied in industrial NDT/NDE, security check, medical diagnosis, petroleum and gas pipeline inspection system etc.

Current radiography and tomography applications at Necsa and an envisaged upgrade towards a proposed South African national centre for radiography and tomography (SANCRAT)

Energy Technology Data Exchange (ETDEWEB)

Radebe, M.J.; De Beer, F.C. [Necsa - South African Nuclear Energy Corporation Limited, P. O.Box 582, Pretoria, 0001 (South Africa)

2008-07-01

An upgrade of the current Radiography and Tomography Research facilities is envisaged to enhance the group's support for Necsa's mission to undertake and support nuclear research and utilize penetrating radiation for the benefit of mankind. It is envisage that the SANCRAT will host neutron-, X-ray- and gamma ray penetrating radiation imaging infrastructures that can be utilized by researchers from industry as well as post graduate students from higher educational institutions. Modelling for the upgrade to a multifunctional neutron radiography and tomography facility has been underway. Upgrade plans and implementation has also begun for a 250 kV X-ray radiography set-up, that will exist independent from the neutron facility. Future expansion entails catering for a micro-focus X-ray -, and gamma ray radiography and tomography facilities. The current facilities available consist of one infrastructure facility based on two sources of penetrating radiation, i.e. SAFARI-1 research nuclear reactor as thermal neutron source and a 100 kV X-ray generator. This facility, which hosts the only operational neutron tomography R and D facility in the Southern Hemisphere and in Africa, are being extensively utilized by post graduate students and industry. The facility sees application in a wide range of scientific and engineering disciplines, amongst which is nuclear, geosciences, palaeontology, civil, mechanical, chemical, etc. This paper focus on case studies engaged at the current radiography and tomography facilities over the past 2 years as well as describing the envisaged upgrade initiatives to a fully equipped national centre. (authors)

Current radiography and tomography applications at Necsa and an envisaged upgrade towards a proposed South African national centre for radiography and tomography (SANCRAT)

International Nuclear Information System (INIS)

Radebe, M.J.; De Beer, F.C.

2008-01-01

An upgrade of the current Radiography and Tomography Research facilities is envisaged to enhance the group's support for Necsa's mission to undertake and support nuclear research and utilize penetrating radiation for the benefit of mankind. It is envisage that the SANCRAT will host neutron-, X-ray- and gamma ray penetrating radiation imaging infrastructures that can be utilized by researchers from industry as well as post graduate students from higher educational institutions. Modelling for the upgrade to a multifunctional neutron radiography and tomography facility has been underway. Upgrade plans and implementation has also begun for a 250 kV X-ray radiography set-up, that will exist independent from the neutron facility. Future expansion entails catering for a micro-focus X-ray -, and gamma ray radiography and tomography facilities. The current facilities available consist of one infrastructure facility based on two sources of penetrating radiation, i.e. SAFARI-1 research nuclear reactor as thermal neutron source and a 100 kV X-ray generator. This facility, which hosts the only operational neutron tomography R and D facility in the Southern Hemisphere and in Africa, are being extensively utilized by post graduate students and industry. The facility sees application in a wide range of scientific and engineering disciplines, amongst which is nuclear, geosciences, palaeontology, civil, mechanical, chemical, etc. This paper focus on case studies engaged at the current radiography and tomography facilities over the past 2 years as well as describing the envisaged upgrade initiatives to a fully equipped national centre. (authors)

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

Preparation and realization of industrial radiography for the non destructive testing of welds in Nuclear Power Plants: A spatial cognition analysis

International Nuclear Information System (INIS)

Lafon, M.; Tonnoir, S.; Thibault, G.; Lafon, M.; Berthoz, A.

2008-01-01

Controls of welds by radiographies are an efficient non destructive technique but it can be dangerous if not managed following a strict set of rules. EDF acts to avoid risks via several ways (adapted tools, best practices) and seeks for an integration of the radiographies with respect to the other maintenance operations, in order to raise the ratio of availability of the electricity production unit. This study explores an original analysis of industrial radiography: the influence of the representations of the workplace and its utilizations. This document supports the utilization of some space constraints as explanations of difficulties in the industrial radiography activity. The document proposes innovative points of view coming for on-site observations and from a theoretical background 'cognitive sciences' completed by technical propositions. (author)

Handling of radiation emergency involving accidental detachment of 20 Ci iridium-192 source in a guide tube of a radiographic equipment in industrial radiography site

International Nuclear Information System (INIS)

Zaparde, S.P.; Murthy, B.K.S.; Vora, V.B.; Subramanian, G.

1979-01-01

The source capsule containing about 17.2 Ci of iridium-192 got accidently unscrewed in a guide tube of a gamma radiography equipment while carrying out the radiography of the spiral casing at construction site of a Hydroelectric Power Station. Immediately after the incident about 10 meter distance all around the spiral casing was cordoned off. The unscrewed capsule along with the source pellet was transferred to a lead container by raising the closed end of the guide tube of about 1/2 meters in length. The source pencil cable and cap of source capsule were separated from the source pellet. The source pellet was further shielded by a steel container and lead sheets. The source pellet was reloaded in the source capsule with limited facilities available at the work site. The source capsule cap was perfectly screwed by standing behind the L bench temporarily constructed out of lead sheets for the above jobs. During the above operation, the person received a whole body dose of 2000 mR and extrimety dose of 3000 mR. Handling of one more radiation emergency of similar type is described. A few appliances designed and fabricated for use in such emergencies are briefly described. (auth.)

New development in the certification of a component radiation protection officer in industrial radiography

International Nuclear Information System (INIS)

Ismail Bahari; Azwar, M.H.; Mohd Pauzi, M.S.

2001-01-01

The appointment of a Radiation protection Officer (RPO) by companies for activities related to the use of Atomic Energy, including Industrial Radiography is mandated under regulation 23 of the Radiation Protection (Basic Safety Standards) Regulations 1988. The regulations categorically requires the appointment of a competent person to help ensure radiation safety at work. Definition of competency has been spelt out in the regulations and this is translated to include having been trained and tested through examination by the AELB and be able to carry out the duties and responsibilities prescribed by the Act and Regulations. This paper discusses the development in the certification of RPO in the field of industrial radiography and what the new RPO certification scheme together with the Certification of RPO standard (LEMI/TEK/44) will do to increase competency as well as the market value of future RPOs. (Author)

Inspection of welded joints and cords using industrial x-ray and gamma radiography

International Nuclear Information System (INIS)

Escobar R, E.J.

2000-01-01

The first part of this work contains five chapters related to theoretical aspects and basic knowledge of welding metallurgy, welding, welded joint discontinuity, non-destructive testing (NDT) and industrial x-rays. The second part contains experimental works applied and carried out by the Peruvian Institute of Nuclear Energy (IPEN). Due to the importance of identifying and applying the different methods of NDT in the industry's quality control, more emphasis is placed on industrial x-ray and gamma radiography, a method that involves the radiographic inspection of welded joints and cords

Utilization of basic directives radioprotection norm in industrial radiography services CNEN-3.01

International Nuclear Information System (INIS)

Dagnino, R.

1989-01-01

The characteristics of the introduction of the standart CNEN - 3.01 - Diretrizes Basicas de Radioprotecao in industrial radiography field, mainly referred to service companies are presented. Some suggestions are proposed in order that the accomplishment of these principles does not stop the works which use this inspection technique. (author)

Implantation of licensing norm for industrial radiography installations - Norm CNEN-NE-604 Rev.1

International Nuclear Information System (INIS)

Heilbron Filho, P.F.L.; Oliveira, S.M.V. de.

1988-04-01

The results of audits carried out by DIN/CNEN (Department of Nuclear Installations) in firms of Rio de Janeiro and Sao Paulo, Brazil, that use industrial radiography for implantation of the norm of installation licensing, are presented. (M.C.K.) [pt

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

International Nuclear Information System (INIS)

Aquino, Josilto Oliveira de

2003-08-01

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

Identifying high dose activities in industrial site radiography

International Nuclear Information System (INIS)

Heaton, B.

2000-01-01

Although the radiation doses received by industrial radiographers in the UK have progressively fallen over the last few years, with most now receiving less than 1 mSv/y, a few still receive, relative to the rest, much higher doses. As a percentage of all radiographers the number stays surprisingly constant from year to year. This paper describes a survey to identify the work causing these doses and suggest possible solutions. The UK Central Index of Dose Information was interrogated to identify the industrial radiography companies having staff (not necessarily the same person) with doses of greater than 5mSv/y in the last three years for which information was available. This was 15 in total. The people on the staff receiving these doses were identified and a questionnaire sent to the companies concerned requesting information about their work. A general questionnaire about the operation of the company was also included. With the agreement of the company these questionnaires were followed up by a visit to the company to interviews a number of the management and the radiographers if available. Both groups were generally very open about their problems and every discussion had a positive outcome. Several areas of work/reasons for the doses have been identified. These are: pipeline radiography, ultra sound radiographers working on nuclear reactors, complex plant work often with several teams in the area, inability to retreat from the wind out equipment due to height or access problems, site pressure to not follow the best practices and a lack of appreciation when a dose was being received or, alternatively, carelessness. Some o these problem areas are very difficult to resolve. However ways in which the Health and Safety can help influence the doses have been identified together with practical suggestions radiographers could adopt. These will be reported. (author)

Portable digital electronic radiography system

International Nuclear Information System (INIS)

Sawicka, B.D.

1995-01-01

Radiography is a standard nondestructive technique in the industrial testing of materials and components. It is routinely used during the construction, maintenance and repair of nuclear plants. Traditionally, radiography is performed using photographic film (film radiography, FR). Recent developments in solid-state area imaging radiation detectors, miniature electronics and computer software/hardware techniques have brought electronic alternatives to FR. In recent years various electronic radiography (ER) techniques have served as alternatives to FR, these proved beneficial in some applications. While originally developed to provide real time imaging, ER may offer other advantages over FR, depending on the application. Work was undertaken at CRL to review progress in ER techniques and evaluate the possibility of constructing a portable DER (digital electronic radiography) system, for the inspection of power plant components. A suitable DER technique has been developed and a proof of principle portable system constructed. As this paper demonstrates, a properly designed ER system can be small and compact, while providing radiographic examination with acceptable image quality and the benefits of ER imaging. The CRL DER system can operate with radioactive sources typical of FR. While it does not replace FR, our DER system is expected to be beneficial in specific applications for Candu maintenance, reducing cost, labour and time. Practical, cost saving applications of this system are expected to include valve monitoring and foreign object location during maintenance at Candu reactors

Gamma radiography and its technological application

International Nuclear Information System (INIS)

Courtois, G.

1962-01-01

After the presentation of gamma radiography and X-ray radiography, the author compare both techniques showing, in particular, the greater utility of gamma radiography in industrial diagnostic and more particularly on works site diagnostic. Problem of using radiography and safety consideration will be studied. Figures shows two radiography equipment which have been designed for gamma radiography respecting the safety regulations required by the Radioisotope Inter-ministerial Commission. In the second part, different techniques and uses of gamma radiography are briefly described : xerography, neutron radiography, fluoroscopy and imaging amplifier, tomography, betatrons and linear accelerators. Cost analysis will discussed in conclusion. (M.P.)

A preliminary design of mechanical device on industrial digital radiography equipment design

International Nuclear Information System (INIS)

Nur Khasan; Samuel Praptoyo

2015-01-01

A preliminary design of mechanical device on industrial digital radiography equipment has been done. this design is intended as a basis for the manufacture of complete facilities for the realization a prototype on industrial digital radiography equipment. the design and construction were carried out by paying attention to the general configuration of the basic design in which its mechanical design has several components with specific dimensions and heavy mass. this design consist of a main frame holder, flat panel detector support and hydraulic hand stacker for mounting the x-ray machine. this mechanical device design will then be fabricated to facilitate and assist work of digital radiographic retrieval. computer application programs sketch-up is used to draw this design and the analysis stress of autodesk inventor to analysis the strength construction design. the results of this design are the configuration drawing, sketch drawings of construction and the safety factor of construction design with a minimum value of 2.39 as well as a maximum value of 15 when to be simulated by the load 500 Kg which is 4 times of total workload. (author)

Safety lock for radiography exposure device

International Nuclear Information System (INIS)

Gaines, T.M.

1982-01-01

A safety lock for securing a radiation source in a radiography exposure device is disclosed. The safety lock prevents the inadvertent extension of the radiation source from the exposure device. The exposure devices are used extensively in industry for nondestructive testing of metal materials for defect. Unnecessary exposure of the radiographer or operator occurs not infrequently due to operator's error in believing that the radiation source is secured in the exposure device when, in fact, it is not. The present invention solves this problem of unnecessary exposure by releasingly trapping the radiation source in the shield of the radiography exposure device each time the source is retracted therein so that it is not inadvertently extended therefrom without the operator resetting the safety lock, thereby releasing the radiation source. Further, the safety lock includes an indicator which indicates when the source is trapped in the exposure device and also when it is untrapped. The safety lock is so designed that it does not prevent the return of the source to the trapped, shielded position in the exposure device. Further the safety lock includes a key means for locking the radiation source in the trapped position. The key means cannot be actuated until said radiation source is in said trapped position to further insure the safety lock cannot be inadvertently locked with the source untrapped and thus still extendable from the exposure device

Sources of dispersion in industrial radiography

International Nuclear Information System (INIS)

Ruault, P.A.

1985-01-01

Maximum value of divergence produced by the different parameters are summed up. Parameters examined include the emulsion (aging, processing), the source (filtration, energy, angle), the dosimetry, the object and the print. In the case of testing in the same conditions errors are relatively low but for testing the same object after a long time errors can be important [fr

Applications of image plates in neutron radiography and neutron diffraction at BARC, Trombay

International Nuclear Information System (INIS)

Shaikh, A.M.

2013-01-01

Neutron radiography techniques based on Gd, Dy and In metallic foils and X-ray film have been used at this centre since early seventies for various NDT and R and D work in nuclear, defence and aerospace industries. In recent years use of photostimulated luminescence based phosphor imaging plate has been introduced in our work. This has enabled to achieve higher sensitivities and dynamic ranges of recording radiographs with acceptable spatial resolution. It also provides digital image information which is more convenient for quantitative evaluations. Neutron image plates have been used in variety of radiography techniques such as conventional neutron radiography (NR), neutron induced beta radiography (NIBR), hydrogen sensitive epithermal neutron radiography (HYSEN) and for neutron powder diffractometry using Apsara, CIRUS and Dhruva reactors as neutron sources. Recently the image plates have also been used for characterization of thermalized neutron beam from a plasma focus neutron source and recording neutron radiographs. Prior to the utilization image plates have been characterised for their performance. Details of the measurements and applications will be presented. (author)

Experimental Comparison of 2-3MV X-Ray Sources for Flash Radiography

International Nuclear Information System (INIS)

MENGE, PETER RICHARD; JOHNSON, DAVID LEE; MAENCHEN, JOHN E.; OLSON, CRAIG L.; ROVANG, DEAN C.; DROEMER, D.; HUNT, E.; OLIVER, BRYAN VELTEN; ROSE, DAVID VINCENT; WELCH, DALE ROBERT

2002-01-01

High-brightness flash x-ray sources are needed for penetrating dynamic radiography for a variety of applications. Various bremsstrahlung source experiments have been conducted on the TriMeV accelerator (3MV, 60 Ω 20 ns) to determine the best diode and focusing configuration in the 2-3 MV range. Three classes of candidate diodes were examined: gas cell focusing, magnetically immersed, and rod pinch. The best result for the gas cell diode was 6 rad at 1 meter from the source with a 5 mm diameter x-ray spot. Using a 0.5 mm diameter cathode immersed in a 17 T solenoidal magnetic field, the best shot produced 4.1 rad with a 2.9 mm spot. The rod pinch diode demonstrated very reproducible radiographic spots between 0.75 and 0.8 mm in diameter, producing 1.2 rad. This represents a factor of eight improvement in the TriMeV flash radiographic capability above the original gas cell diode to a figure of merit (dose/spot diameter) > 1.8 rad/mm. These results clearly show the rod pinch diode to be the choice x-ray source for flash radiography at 2-3 M V

The spherical pinch as a soft x-ray source for microlithography and other industrial applications

International Nuclear Information System (INIS)

Aithal, S.; Lamari, M.; Panarella, E.

1992-01-01

In the course of the past several years, an R and D program has been carried out at ALFT in order to exploit the Spherical Pinch concept of plasma heating to create a hot plasma of radiation emission characteristics of interest for industrial X-ray microlithography. The program has been successful and a prototype machine has now been built. The plasma is generated by inductively discharging 30 kJ of electrical energy from a condenser bank in a spherically shaped coil. Since the energy transfer efficiency is ∼ 25%, in excess of 7 kJ of energy is deposited into the plasma. The strong implosion thus generated, on compressing a preformed central plasma, creates a source of soft X-rays having the following characteristics: X-ray energy, 1--3, keV; X-ray energy per pulse, ∼ 50, J; Source size, ∼ 1, mm; X-ray flux at--20 cm from source, ∼10, mJ/cm 2 /shot; position reproducibility, 0.1, Hz. These characteristics are very close to what is required by the semiconductor industries for microlithography. For this reason, a commercial unit is now being designed and manufactured and will be available for marketing by the end of 1992. This source of soft X-rays has recently found another industrial application, paper radiography for quality evaluation and control in the paper industry. The possibility of imaging by means of soft X-rays the microstructure of paper on production line enables the operator to adjust the paper manufacturing configuration through variations of the relative speed of the jet compared to that of the wire. A compact X-ray source for paper radiography is now being designed and manufactured, and a prototype machine will be ready by the beginning of 1993. The Spherical Pinch plasma source is a good radiation emitter also in the UV and the deep UV range of the spectrum

Characterization of a gamma-ray source based on a laser-plasma accelerator with applications to radiography

International Nuclear Information System (INIS)

Edwards, R.D.; Sinclair, M.A.; Goldsack, T.J.; Krushelnick, K.; Beg, F.N.; Clark, E.L.; Dangor, A.E.; Najmudin, Z.; Tatarakis, M.; Walton, B.; Zepf, M.; Ledingham, K.W.D.; Spencer, I.; Norreys, P.A.; Clarke, R.J.; Kodama, R.; Toyama, Y.; Tampo, M.

2002-01-01

The application of high intensity laser-produced gamma rays is discussed with regard to picosecond resolution deep-penetration radiography. The spectrum and angular distribution of these gamma rays is measured using an array of thermoluminescent detectors for both an underdense (gas) target and an overdense (solid) target. It is found that the use of an underdense target in a laser plasma accelerator configuration produces a much more intense and directional source. The peak dose is also increased significantly. Radiography is demonstrated in these experiments and the source size is also estimated

Transport of Gamma Radiography Apparatus (Dangerous Goods 1978, no. 7)

International Nuclear Information System (INIS)

1978-01-01

The Minister of Transport amended the Regulations on the Transport of Dangerous Goods of 15 April 1945 by Order dated 24 August 1978. The modifications concern the safety conditions to be complied with for the transport of portable industrial gamma radiography apparatus containing sealed radioactive sources. (NEA) [fr

Military radiography

International Nuclear Information System (INIS)

Anon.

1993-01-01

Historic military uses of radiography are discussed in this chapter: Battle of Adowa in 1986 was the first. Besides describing the early campaigns in which radiography was used, the author discusses the problems faced: a reliable source of electricity; the problems of extreme heat; moving and breakage of equipment. Numerous historical photographs are included. 9 refs

DIANE stationary neutron radiography system image quality and industrial applications

International Nuclear Information System (INIS)

Cluzeau, S.; Huet, J.; Tourneur, P. le

1994-01-01

The SODERN neutron radiography laboratory has operated since February 1993 using a sealed tube generator (GENIE 46). An experimental programme of characterization (dosimetry, spectroscopy) has confirmed the expected performances concerning: neutron flux intensity, neutron energy range, residual gamma flux. Results are given in a specific report [2]. This paper is devoted to the image performance reporting. ASTM and specific indicators have been used to test the image quality with various converters and films. The corresponding modulation transfer functions are to be determined from image processing. Some industrial applications have demonstrated the capabilities of the system: corrosion detection in aircraft parts, ammunitions filling testing, detection of polymer lacks in sandwich steel sheets, detection of moisture in a probe for geophysics, residual ceramic cores imaging in turbine blades. Various computerized electronic imaging systems will be tested to improve the industrial capabilities. (orig.)

Neutron radiography at the Paul Scherrer Institute

International Nuclear Information System (INIS)

Pleinert, H.; Lehmann, E.; Hammer, J.

1994-01-01

Neutron radiography provides an efficient tool of measurement for many applications in fundamental research as well as in industrial non-destructive testing (NDT). A neutron radiography program has been initiated at the Paul Scherrer Institute and implemented since 1992. From the beginning of 1992 until the end of 1993, a neutron facility has been in operation at the SAPHIR research reactor. Several applications have been tested and programs on two main fields of application have been established, focusing on the study of porous materials, especially concrete and granitic rock. The investigations on concrete and other building materials are carried out in cooperation with the Swiss Federal Institute of Technology in Zurich. The experimental activities are currently carried out at the Atominstitute of the Austrian Universities in Vienna, in the framework of a cooperation program with the Atominstitute. The continuation of the activities on a new radiography facility at the spallation source SINQ is planned at the Paul Scherrer Institute. In the following an overview of the method, of the actual and potential applications of neutron radiography at the Paul Scherrer Institute is given. (author) 6 figs., 1 tab., 3 refs

Industrial radiography in the State of Bahia, Brazil: The health protection of workers

International Nuclear Information System (INIS)

Andrade, Ana Emilia Oliveira de

1997-01-01

This study aimed to identify the Regulatory and Inspection Authority for actions developed by industrial radiography enterprises in the State of Bahia, Brazil, concerning health protection of workers exposed to ionizing radiation in industry. Institutions which legislate about this matter at international, national and State level were identified. These legislations were analysed according to recommendations by the Basic Safety Standards from the Atomic Energy International Agency. Medical Supervision is proposed as a factor to warrant protection to worker's health. This is a service evaluation study, encompassing results, processes and structural components. Emphasis is given to the process component which investigated the adequacy of which is performed by employees and workers. Five enterprises which provide industrial radiography services in the State of Bahia were identified, employing forty workers on a temporary basis. This study also observed: intense workforce, a complete process of contracting out in the sector; inadequate conditions of work organization (long work journey, night work, lack of days-off schedule); inefficiency of medical services responsible by worker's protection concerning radiation specific risks as well as other occupational risks, unrelated to main activity. There is a legal basis for Authorities actions, although it has not been completely implemented. These findings embased the elaboration of a proposal of a Surveillance Program for the Worker Exposed to Industrial Radiation, which includes the setting of safety standards and monitoring of workers exposed to ionization radiation in the occupational environment, accident prevention in this activity and the specialized health care to those affected by radio accidents. (author)

New prospect in neutron radiography

International Nuclear Information System (INIS)

Cluzeau, S.

1991-01-01

Neutron radiography is a very useful non-destructive testing (NDT) method which frequently complements classical X-ray inspection. Numerous inspections in some fields are currently performed at reactor-based neutron radiography facilities but many other interesting applications in different fields are at present not considered because the objects to be tested cannot be moved to a reactor. It is the goal of the DIANE project, to allow the utilization of this NDT method in industrial facilities by developing a safe and convenient neutron radiography equipment using an ''on-off'' neutron source. As a result of the efforts of the four European partners, a first laboratory demonstration model is currently in operation in Germany and a fully mobile second one is expected by the end of 1992. Good radiographs are obtained with exposure times in the range of a few seconds to ten minutes using an electronic imaging system. The fast neutron generator uses a sealed neutron tube delivering 5.10 11 neutrons.cm -2 .s -1 in 4 π steradian; with a collimator ratio of about 12, the fluence rate onto the object is then close to 1,5.10 5 thermal neutrons.cm -2 .s -1 . (author)

New microfocus bremsstrahlung source based on betatron B-18 for high-resolution radiography and tomography

Science.gov (United States)

Rychkov, M. M.; Kaplin, V. V.; Malikov, E. L.; Smolyanskiy, V. A.; Stepanov, I. B.; Lutsenko, A. S.; Gentsel'man, V.; Vas'kovskiy, I. K.

2018-01-01

New microfocus source of hard bremsstrahlung (photon energy > 1 MeV), based on the betatron B-18 with a narrow Ta target inside, for high-resolution radiography and tomography is presented. The first studies of the source demonstrate its possibilities for practical applications to detect the microdefects in products made from heavy materials and to control gaps in joints of parts of composite structures of engineering facilities. The radiography method was used to investigate a compound object consisting of four vertically arranged steel bars between which surfaces were exposed gaps of 10 μm in width. The radiographic image of the object, obtained with a magnification of 2.4, illustrates the good sensitivity of detecting the gaps between adjacent bars, due to the small width of the linear focus of the bremsstrahlung source.

Non destructive testing and neutron radiography in 1994; Les controles non destructifs et la neutronographie en 1994

Energy Technology Data Exchange (ETDEWEB)

Bayon, G.

1994-12-31

Neutron radiography has been considered for a long time as a promising technique; however it plays a minor part in the world of non destructive testing today, due to the lack of suitable neutron sources and lack of new industrial applications. This paper reviews the present status of neutron sources, neutron radiography activities, especially in France (such as the neutron-capture-issued secondary radiation spectrometry), in nuclear, aerospace, aeronautical and metallurgical sectors, and the last applications of neutron dynamic imaging. 9 refs.

Neutron resonance radiography: Report of a workshop, Los Alamos, NM: July 27-29, 1987

International Nuclear Information System (INIS)

1988-07-01

Neutron resonance radiography is a new technique with great potential for non-destructive analysis and testing. This technique has been under research and development in a number of major research laboratories for some time. Unlike thermal neutron radiography, which is primarily oriented towards imaging hydrogen and a number of other highly neutron-absorptive materials without necessarily distinguishing between them, neutron resonance radiography has the capability of uniquely identifying many kinds of chemical elements and their individual isotopes. It also has the potential for temperature imaging in materials containing heavy elements and for certain dynamic features such as stroboscopic imaging. Although neutron resonance radiography has not yet been taken up in a systematic way for technological applications, significant development of ideas and instrumentation at the research level has blossomed. There have also been major developments in the availability of powerful pulsed-neutron sources. In light of these developments, the Los Alamos Neutron Scattering Center sponsored a workshop with the general aims of reviewing scientific and technical progress, discussing and highlighting future developments, and stimulating interest in technological exploitation of the methods. In addition to the techniques and instrumentation required for the field, the applications of neutron resonance radiography in some of the following industrial and manufacturing areas were discussed: nuclear fuel assay; nuclear safeguards in general; aerospace development (aeroengine blade temperature, stroboscopic techniques); diagnostics; non-nuclear industry (especially metallurgy); temperature imaging; use of mobile pulsed-neutron sources; and practical use of major pulsed-neutron facilities

Recognition of internal structure of unknown objects with simultaneous neutron and gamma radiography

International Nuclear Information System (INIS)

Moghadam, K.K.; Nasseri, M.M.

2004-01-01

Generally speaking in customary industrial and medical radiography, there is no tendency to reveal the nature of the samples. Ordinarily, the main objective of taking a radiograph is to show the position and dimension of unknown parts, inside the test object and to determine cracks, defects, etc. Whereas in radiography many important factors such as material cross-sections and build-up factors are also involved. In this paper, by using both neutron and gamma radiography techniques, some mathematical relations were successfully generated, in order to calculate the neutron and gamma total macroscopic cross-sections of some unknown elements in the presence of the other elements. For this work, some test pieces were defined and made of lead, silver, copper, Nickel, tin, graphite and polyethylene. The neutron radiography facility at Tehran Research Reactor (TRR) was used as mixed neutron and gamma radiography source (Proceedings of the Second World Conference on Neutron Radiography, Paris, France, pp. 25-32). On testing of a correction of the above-mentioned generated relations, a new technique of simultaneous neutron and gamma radiography was also investigated

Corrosion Surveillance In Pipe By Computed Radiography

International Nuclear Information System (INIS)

Nguyen The Man; Dao Duy Dung; Dang Thu Hong; Le Duc Thinh; Ha Hong Thu; Nguyen Trong Nghia

2014-01-01

Computed Radiography (CR) is a technique of digital industrial radiology which is developed to replace conventional radiography. With a CR system, the detection of the outer and inner wall surface of the pipe is done usually by edge detection and filter algorithms of the profile line at the position under investigation. Applying in industries, radiographic examination shall be performed in accordance with a written procedure. This paper summarizes collected knowledge and experimental results to establish a procedure for radiography applications in monitoring corrosion in small bore pipes. (author)

Specific radiography technique

International Nuclear Information System (INIS)

Abdul Nassir Ibrahim; Azali Muhammad; Ab. Razak Hamzah; Abd. Aziz Mohamed; Mohamad Pauzi Ismail

2008-01-01

Beside radiography testing using x-ray machine and gamma source, there are several technique that developed specifically to complete the testing that cannot be done with the two earlier. This technique was specific based on several factor, for the example, the advantages of neutron and electron using to show the image was unique compare to x-ray and gamma. Besides that, these special radiography techniques maybe differ in how to detect the radiation get through the object. These technique can used to inspect thin or specimen that contained radioactive material. There are several technique will discussed in this chapter such as neutron radiography, electron radiography, fluoroscopy and also autoradiography.

Radioisotopes in industry

International Nuclear Information System (INIS)

Popple, B.N.

1977-01-01

The author explains clearly what is radiography, enumerates four major factors in considering a practical source to use namely half-life, penetrating power, half value layer and specific activity and also the advantages and disadvantages in using isotopes. Common radioisotopes used in industrial radiography are iridium, cesium, cobalt and thulium. Main uses of the radioisotopes are for radiographic testing like welding castings, forgoings etc.; thickness, level or density measurement and tracing. (RTD)

Shielded radiography with a laser-driven MeV-energy X-ray source

Energy Technology Data Exchange (ETDEWEB)

Chen, Shouyuan; Golovin, Grigory [Department of Physics and Astronomy, University of Nebraska-Lincoln, Lincoln, NE 68588 (United States); Miller, Cameron [Department of Nuclear Engineering and Radiological Sciences, University of Michigan, Ann Arbor, MI 48109 (United States); Haden, Daniel; Banerjee, Sudeep; Zhang, Ping; Liu, Cheng; Zhang, Jun; Zhao, Baozhen [Department of Physics and Astronomy, University of Nebraska-Lincoln, Lincoln, NE 68588 (United States); Clarke, Shaun; Pozzi, Sara [Department of Nuclear Engineering and Radiological Sciences, University of Michigan, Ann Arbor, MI 48109 (United States); Umstadter, Donald, E-mail: donald.umstadter@unl.edu [Department of Physics and Astronomy, University of Nebraska-Lincoln, Lincoln, NE 68588 (United States)

2016-01-01

We report the results of experimental and numerical-simulation studies of shielded radiography using narrowband MeV-energy X-rays from a compact all-laser-driven inverse-Compton-scattering X-ray light source. This recently developed X-ray light source is based on a laser-wakefield accelerator with ultra-high-field gradient (GeV/cm). We demonstrate experimentally high-quality radiographic imaging (image contrast of 0.4 and signal-to-noise ratio of 2:1) of a target composed of 8-mm thick depleted uranium shielded by 80-mm thick steel, using a 6-MeV X-ray beam with a spread of 45% (FWHM) and 10{sup 7} photons in a single shot. The corresponding dose of the X-ray pulse measured in front of the target is ∼100 nGy/pulse. Simulations performed using the Monte-Carlo code MCNPX accurately reproduce the experimental results. These simulations also demonstrate that the narrow bandwidth of the Compton X-ray source operating at 6 and 9 MeV leads to a reduction of deposited dose as compared to broadband bremsstrahlung sources with the same end-point energy. The X-ray beam’s inherently low-divergence angle (∼mrad) is advantageous and effective for interrogation at standoff distance. These results demonstrate significant benefits of all-laser driven Compton X-rays for shielded radiography.

High energy neutron radiography

International Nuclear Information System (INIS)

Gavron, A.; Morley, K.; Morris, C.; Seestrom, S.; Ullmann, J.; Yates, G.; Zumbro, J.

1996-01-01

High-energy spallation neutron sources are now being considered in the US and elsewhere as a replacement for neutron beams produced by reactors. High-energy and high intensity neutron beams, produced by unmoderated spallation sources, open potential new vistas of neutron radiography. The authors discuss the basic advantages and disadvantages of high-energy neutron radiography, and consider some experimental results obtained at the Weapons Neutron Research (WNR) facility at Los Alamos

Safety Testing of Industrial Radiography Devices

International Nuclear Information System (INIS)

Trapp, D.J.

1999-01-01

The Nuclear Regulatory Commission contracted the Savannah River Technology Center to verify the relevancy of the 10 CFR Part 34 requirements for the normal use of portable gamma radiography systems and to propose recommendations for changes or modifications to the requirements

New X-ray testing methods of aerosol products for industrial radiography

Energy Technology Data Exchange (ETDEWEB)

Bozydar Knyziak, Adrian, E-mail: a.knyziak@gum.gov.pl; Rzodkiewicz, Witold, E-mail: w.rzodkiewicz@gum.gov.pl; Kaczorowska, Ewa, E-mail: e.kaczorowska@gum.gov.pl; Derlacinski, Michal, E-mail: m.derlacinski@gum.gov.pl

2017-02-01

An amount of product in e.g. an aerosol canister is not difficult to estimate by weighing a filled can and subtracting the tare of packaging. In this way, we can obtain the net weight of the ingredients present in the can. Although, this does not indicate the volumetric content. Therefore, in the paper, the fundamental (the weight method and given by FEICA) and new methods (given by authors) related to the determination of the volumetric content of canister filled with aeorosol products are presented. The new methods are based on direct digital radiography (DR) using X-ray radiation. For the needs of new methods, the X-ray CCD-DR imaging system was built and developed in our Laboratory in Department of Radiation and Vibration at the Central Office of Measures. For comparison purposes, with regard to the volumetric content, a lot of metal cans of capacities 140, 185, 450, 700 ml were inspected. In future, computed tomography (CT) for industrial radiography in our laboratory will be used. Currently, an algorithm for CT is being tested. It will give us possibility for very precise measurements to determine volumetric content of examined canisters.

Reconstructive dosimetry and radiation doses evaluation of members of the public due to radiological accident in industrial radiography; Dosimetria reconstrutiva e avaliacao de dose de individuos do publico devido a acidente radiologico em radiografia industrial

Energy Technology Data Exchange (ETDEWEB)

Lima, Camila Moreira Araujo de

2016-07-01

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 {sup 192}Ir 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)

Neutron radiography at the SCK/CEN

International Nuclear Information System (INIS)

Tourwe, H.

1977-01-01

Neutron radiography has become in recent years a very important method of nondestructive testing in industry and research. The earliest practical application of neutron radiography has probably been the inspection of highly radioactive material: originally irradiated reactor fuels. Applications then progressed to other nuclear and industrial inspection problems. Neutron radiography and the conventional X-ray or gamma techniques are complementary. Some of the most important application fields of neutron radiography are: the detection of light elements (H, Li, B,...) with a very high scattering of absorption cross section for thermal neutrons; the nondestructive control of fuel before and after irradiation; controls where a distinction has to be made between isotopes of the same element ( 235 U and 238 U, 10 B and 11 B,...) and between components of a similar atomic number (Fe and Zn); the control of materials with a high density; the study of corrosion in closed structures; the control of the homogeneity of foreign materials in alloys,.... (author)

Israeli Public Exposure As A Result Of Site Industrial Radiography: Paramenyl Findings

International Nuclear Information System (INIS)

Keren, M.; Rotenberg, L.

1999-01-01

In order to minimize accident possibilities due to Site Industrial Radiography [1], Radiation Safety Division (RSD) of The Ministry of The Environment ordered users of this technology to report their work program in advance. Thus, inspection may be executed by RSD during filming. This work presents results of sample inspections done by RSD during 1997. Accumulated exposure for the public was maximum 23 μ μSv, compared to maximum allowed dose of 300 μ Sv/a (1000 μ Sv/a[2] constrained by 0.3) allowed to the public

neutron radiography

International Nuclear Information System (INIS)

Barton, J.P.

1993-01-01

Neutron radiography (or radiology) is a diverse filed that uses neutrons of various energies, subthermal, thermal, epithermal or fast in either steady state or pulsed mode to examine objects for industrial, medical, or other purposes, both microscopic and macroscopic. The applications include engineering design, biological studies, nondestructive inspection and materials evaluation. In the past decade, over 100 different centers in some 30 countries have published reports of pioneering activities using reactors, accelerators and isotopic neutron sources. While film transparency and electronic video are most common imaging methods for static or in motion objects respectively, there are other important data gathering techniques, including track etch, digital gauging and computed tomography. A survey of the world-wide progress shows the field to be gaining steadily in its diversity, its sophistication and its importance. (author)

The use of portable shields in industrial radiography

International Nuclear Information System (INIS)

Oliveira e Silva, J.A. de.

1988-01-01

This paper shows techniques actually used to reduce radiations exposure taxes during examinations execution by gamma radiography in regions of high population density. A portable equipment of radiation shield for using in exams by gamma radiography in pipelines, that is an adjustable device in an object body that will be examined, joining a measured collimator and a shield geometrically arranged so that the radiation restrict to impress the radiographic film used in examination without reaching people, objects or self-movings injurious that are nearness. (C.M.) [pt

Simulations of Liners and Test Objects for a New Atlas Advanced Radiography Source

International Nuclear Information System (INIS)

Morgan, D. V.; Iversen, S.; Hilko, R. A.

2002-01-01

The Advanced Radiographic Source (ARS) will improve the data significantly due to its smaller source width. Because of the enhanced ARS output, larger source-to-object distances are a reality. The harder ARS source will allow radiography of thick high-Z targets. The five different spectral simulations resulted in similar imaging detector weighted transmission. This work used a limited set of test objects and imaging detectors. Other test objects and imaging detectors could possibly change the MVp-sensitivity result. The effect of material motion blur must be considered for the ARS due to the expected smaller X-ray source size. This study supports the original 1.5-MVp value

Effective source size as related to 252Cf neutron radiography

International Nuclear Information System (INIS)

Wada, Nobuo; Enomoto, Shigemasa; Tachikawa, Noboru; Nojiri, Toshiaki.

1977-01-01

The effective source size in 252 Cf thermal neutron radiography, relating to its geometrical unsharpness in image formation, is experimentally studied. A neutron radiographic system consists of a 160 μg 252 Cf neutron source, water moderator and divergent cadmium lined collimator. Thermal neutron image detection is performed with using a LiF scintillator and a high speed X-ray film to employ direct exposure method. The modulation transfer function, used for describing image quality, is derived from radiographic image corresponding to a cadmium plate with sharp edge. The modulation transfer function for the system is expressed by the product of the function for both geometrical and inherent unsharpness, and allows isolation of geometrical unsharpness as related to the effective size of the thermal neutron source. It is found to be 80 -- 90% of the collimator inlet diameter. (auth.)

Production of iridium-192 radiation sources: Indian Experience

International Nuclear Information System (INIS)

Sastry, K.V.S.; Kolhe, O.T.; Nagarja, P.S.; Paramr, Y.D.

2002-01-01

Board of Radiation and Isotope Technology (BRIT), a unit under the Department of Atomic Energy is fabricating and supplying Ir-192 industrial radiography sources for various models of radiography cameras for use in the industry for non-destructive testing. Basically these sources are fabricated by encapsulating the required quantity of the activity in stainless steel 316 L capsules using Tungsten Inert gas welding process and crimping/attaching to the respective pigtail assemblies of the radiography cameras. The inactive iridium pellets are irradiated in the DHRUVA reactor at a flux on 1.8 X 10 14 n/cm 2 /sec. The performance classification of these source encapsulation for various conditions of normal and accidental nature are tested by subjecting the prototype sources as per the standard laid down by the regulatory authority, Atomic Energy Regulatory Board, in India. The sources are fabricated as per the national and international standards. Activity of the sources varies from 37O GBq (10 Ci ) to 2.96 TBq (80 Ci ) source strength depending on the requirement of the user. The specific activity of the Ir-192 sources supplied is around 7.4 TBq/gm (200 Ci/gm ). Quality control /Assurance for the manufacture of the source begins from the procurement of the raw material and ends with the finished source. Ir- 192 in the form of -0.3 mm diameter (0.1 mm dia wire of Ir-25 % and Pt-75% sheathed in pure platinum of 0.1 mm thick) is being supplied for use in the treatment of cancer of cervix, tongue etc. by brachytherapy. This is supplied in lengths of 50 cm / 100 cm with 37 - 185 GBq/cm ( 1-5 mCi/cm) activity. Annually 925 TBq (25 kCi) of Ir-192 for industrial radiography and about 60 meters of wire for brachytherapy are being fabricated and supplied. Because of the quality of these sources BRIT not only caters to the Indian industry but also is able to export sources to the third world countries. (Author)

Evaluation of digital detector arrays systems for industrial radiography

International Nuclear Information System (INIS)

Silva, Aline S.S.; Oliveira, Davi F.; Gomes, Célio S.; Azeredo, Soraia R.; Lopes, Ricardo T.

2017-01-01

Digital Detector Arrays (DDA) or Flat Panel Detector (FPD) is a highly efficient technique that is used in nondestructive testing of internal features of an object. The evaluation of DDA systems for industrial radiography is important to ensure the image quality and to enables long-term stability of this system. This evaluation is specified by ASTM E2737 - 10, which describes the fundamental parameters of DDA systems to be measured. The tests require the usage of either the five-groove wedge or the duplex plate phantom with separate Image Quality Indicators (IQIs). The purpose of this work was evaluate the radiographic performance achieved using both techniques in two DDA systems manufactured by GEIT: DXR250P and DXR250V, which have thallium-doped cesium iodide (CsI:Tl) and terbium-doped gadolinium oxysulfide (Gd 2 O 2 S:Tb - GOS) scintillators, respectively. For this purpose, it was used an X-ray equipment as radiation source. The image quality parameters analyzed were Image Lag (IL), Offset Level (OL), Bad Pixel distribution, Burn In (BI), Spatial Resolution (SR), Material Thickness Range (MTR), Contrast Sensitivity (CS), Signal Level (SL) and Signal-to-Noise Ratio (SNR). As result of this study, has been observed that the use of the five-groove wedge phantom made the measurements to become easier to execute. Regarding the DDA system, the DXR250P presented more IL and BI, but produced images with better CS and SNR and needed a dose almost twice smaller than the DXR250V to achieve a similar SL. (author)

Evaluation of digital detector arrays systems for industrial radiography

Energy Technology Data Exchange (ETDEWEB)

Silva, Aline S.S.; Oliveira, Davi F.; Gomes, Célio S.; Azeredo, Soraia R.; Lopes, Ricardo T., E-mail: aline@lin.ufrj.br, E-mail: davi@lin.ufrj.br.br, E-mail: celio@lin.ufrj.br, E-mail: soraia@lin.ufrj.br, E-mail: ricardo@lin.ufrj.br, E-mail: davi.oliveira@uerj.br [Coordenacao de Pos-Graduacao e Pesquisa de Engenharia (COPPE/UFRJ), Rio de Janeiro, RJ (Brazil). Lab. de Instrumentação Nuclear

2017-07-01

Digital Detector Arrays (DDA) or Flat Panel Detector (FPD) is a highly efficient technique that is used in nondestructive testing of internal features of an object. The evaluation of DDA systems for industrial radiography is important to ensure the image quality and to enables long-term stability of this system. This evaluation is specified by ASTM E2737 - 10, which describes the fundamental parameters of DDA systems to be measured. The tests require the usage of either the five-groove wedge or the duplex plate phantom with separate Image Quality Indicators (IQIs). The purpose of this work was evaluate the radiographic performance achieved using both techniques in two DDA systems manufactured by GEIT: DXR250P and DXR250V, which have thallium-doped cesium iodide (CsI:Tl) and terbium-doped gadolinium oxysulfide (Gd{sub 2}O{sub 2}S:Tb - GOS) scintillators, respectively. For this purpose, it was used an X-ray equipment as radiation source. The image quality parameters analyzed were Image Lag (IL), Offset Level (OL), Bad Pixel distribution, Burn In (BI), Spatial Resolution (SR), Material Thickness Range (MTR), Contrast Sensitivity (CS), Signal Level (SL) and Signal-to-Noise Ratio (SNR). As result of this study, has been observed that the use of the five-groove wedge phantom made the measurements to become easier to execute. Regarding the DDA system, the DXR250P presented more IL and BI, but produced images with better CS and SNR and needed a dose almost twice smaller than the DXR250V to achieve a similar SL. (author)

Feasibility study of gamma-ray medical radiography

International Nuclear Information System (INIS)

Alyassin, Abdalmajeid M.; Maqsoud, Hamza A.; Mashat, Ahmad M.; Al-Mohr, Al-Sayed; Abdulwajid, Subhan

2013-01-01

This research explores the feasibility of using gamma-ray radiography in medical imaging. We will show that gamma-ray medical radiography has the potential to provide alternative diagnostic medical information to X-ray radiography. Approximately one Ci Am-241 radioactive source which emits mono-energetic 59.5 keV gamma rays was used. Several factors that influence the feasibility of this study were tested. They were the radiation source uniformity, image uniformity, and image quality parameters such as contrast, noise, and spatial resolution. In addition, several gamma-ray and X-ray images were acquired using humanoid phantoms. These images were recorded on computed radiography image receptors and displayed on a standard monitor. Visual assessments of these images were then conducted. The Am-241 radioactive source provided relatively uniform radiation exposure and images. Image noise and image contrast were mainly dependent on the exposure time and source size, whereas spatial resolution was dependent on source size and magnification factor. The gamma-ray humanoid phantom images were of lower quality than the X-ray images mainly due to the low radioactivity used and not enough exposure time. Nevertheless, the gamma-ray images displayed most of the main structures contained in the humanoid phantoms. Higher exposure rates and thus lower exposure times were estimated for different pure Am-241 source sizes that are hypothesized to provide high quality images similar to X-ray images. For instance, a 10 mm source size of pure Am-241 with 7 s exposure time should produce images similar in contrast and noise to X-ray images. This research paves the way for the production and usage of a highly radioactive Am-241 source with the potential to lead to the feasibility of acceptable quality medical gamma-ray radiography. - Highlights: ► Characterized the performance of gamma-ray radiography. ► Displayed medical images of humanoid phantoms using gamma radiography. ► Am-241

Occupational exposures in industrial application of radiation during 1999-2008

International Nuclear Information System (INIS)

Sanaye, S.S.; Baburajan, Sujatha; Pawar, S.G.; Nalawade, S.K.; Sapra, B.K.

2012-01-01

Application of radiation in industry, medicine and research sector has increase significantly over the years. In industry main applications are industrial radiography, industrial fluoroscopy, radiation processing, luminizing, nucleonic gauges. Since the strength of the source used is generally high compared to other applications as well as the operating conditions prevailing during the exposure, radiological protection plays important role in this sector. Analysis of dose data, available with National Occupational Dose Registry of RPAD, Bhabha Atomic Research Centre, provides some insight into trends in occupational exposures received by industrial radiation workers. This helps in providing information on adequateness of radiation protection practices followed in the industry. This paper presents the trends in occupational exposure received by radiation workers in the industry during past 10 years (1999 to 2008). It is observed that there is a gradual increase in the occupational radiation workers during the period. The number of persons monitored as well as exposed is highest in industrial radiography compared to other sub-categories. Major contribution to collective dose is also from industrial radiography. The highest annual average as well as exposed average doses are contributed by industrial radiography. The monitored persons receiving dose d 5 mSv is 96.9% industry

Radiography of steel castings by radioisotopes

International Nuclear Information System (INIS)

Agrawal, D.K.

1977-01-01

The salient features of isotope radiography techniques in the inspections of alloy castings are described. Some of the typical radiographic tests conducted in the Bharat Heavy Electricals Ltd., Bhopal and the problems encountered are described in detail. Specific examples are cited to enlighten the benefits of isotope radiography in heavy industries. (author)

Potential exposures in mobile industrial radiography

International Nuclear Information System (INIS)

Tauhata, L.; Leocadio, J.C.; Crispim, V.R.

2000-01-01

The radiation protection conditions of the mobile or open industrial radiography facilities were analyzed in the period from 1992 to 1996 to estimate the value of the potential exposure risk, the mean annual dose and the dose distribution function of the workers. To estimate the potential exposure the concepts described in ICRP 64 and Safety Series 104 were used. The annual mean value of abnormal events occurred in the operations of to remove and to retract the radioactive source of exposure device recorded in data bank of National Commission of Nuclear Energy (CNEN), in a period of 5 years, were used to obtain the risk value. To evaluate the worker exposures, data obtained by accompaniment the radiographic testing in 5 installations, representative of all radiographic facilities in Brazil and the data bank of CNEN were used. To obtain the statistical dose distribution data from individual monitoring of the workers of these installations were used, data from additional individual monitoring and data bank of CNEN. The absorbed mean dose value in the period from 1992 to 1996 maintained about 0.2 mSv/year like as in the period from 1990 to 1994, with a maximum value of 0.55 mSv/year in 1988. The statistical distribution in a period from January to December 1996, behavior likes as long-normal type. The estimated risk value for potential exposure was 4x10 -6 per year, in the period from 1992 to 96. Using the data bank of CNEN, in a period from 1976 to 1992, the estimate value was 6.6x10 -6 per year, using the same methodology. The comparison of the failed operation probability value of operator/device/local system, in a period from 1976 to 1992 and in 1996, shows an increasing of 0.5x10 -11 to 1.1x10 -11 per year, due mainly to the radiographic device and accessories become oldest, in spite of maintenance care. However, due to the radiation procedure improvements, the potential risk value reduced about 40%, that is from 6.6x10 6 to 4x10 -6 per year. (author)

Apparatus for gamma radiography

International Nuclear Information System (INIS)

1983-06-01

The aim of the present standard is to fix the rules for the construction of gamma radiography instrumentation without prejudice to the present regulations. These apparatus have to be fitted with only sealed sources conformable to the experimental standard M 61-002. The present standard agrees with the international standard ISO 3999 of 1977 dealing with the same subject. Nevertheless, it is different on the three main following points: it does not accept the same limits of absorbed dose rates in the air calculated on the external surface of projectors; it precribes tightness, bending, crushing and tensile tests for some components of the gamma radiography it prescribes tests of endurance and resistance to breaking for the locking systems of the gamma radiography apparatus. The present standard also specifies the following points: symbols and indications to put on projectors and on the source-holder; identification of the source contained in the projector; and, accompanying documents. The regulation references are given in annexe [fr

Gamma radiography and its technological application; Gammagraphie et techniques annexes

Energy Technology Data Exchange (ETDEWEB)

Courtois, G [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

1962-07-01

After the presentation of gamma radiography and X-ray radiography, the author compare both techniques showing, in particular, the greater utility of gamma radiography in industrial diagnostic and more particularly on works site diagnostic. Problem of using radiography and safety consideration will be studied. Figures shows two radiography equipment which have been designed for gamma radiography respecting the safety regulations required by the Radioisotope Inter-ministerial Commission. In the second part, different techniques and uses of gamma radiography are briefly described : xerography, neutron radiography, fluoroscopy and imaging amplifier, tomography, betatrons and linear accelerators. Cost analysis will discussed in conclusion. (M.P.)

Demonstration of the self-magnetic-pinch diode as an X-ray source for flash core-punch radiography

International Nuclear Information System (INIS)

Cordova, Steve Ray; Rovang, Dean Curtis; Portillo, Salvador; Oliver, Bryan Velten; Bruner, Nichelle Lee; Ziska, Derek Raymond

2007-01-01

Minimization of the radiographic spot size and maximization of the radiation dose is a continuing long-range goal for development of electron beam driven X-ray radiography sources. In collaboration with members of the Atomic Weapons Establishment(AWE), Aldermaston UK, the Advanced Radiographic Technologies Dept. 1645 is conducting research on the development of X-ray sources for flash core-punch radiography. The Hydrodynamics Dept. at AWE has defined a near term radiographic source requirement for scaled core-punch experiments to be 250 rads(at)m with a 2.75 mm source spot-size. As part of this collaborative effort, Dept. 1645 is investigating the potential of the Self-Magnetic-Pinched (SMP) diode as a source for core-punch radiography. Recent experiments conducted on the RITS-6 accelerator [1,2] demonstrated the potential of the SMP diode by meeting and exceeding the near term radiographic requirements established by AWE. During the demonstration experiments, RITS-6 was configured with a low-impedance (40 (Omega)) Magnetically Insulated Transmission Line (MITL), which provided a 75-ns, 180-kA, 7.5-MeV forward going electrical pulse to the diode. The use of a low-impedance MITL enabled greater power coupling to the SMP diode and thus allowed for increased radiation output. In addition to reconfiguring the driver (accelerator), geometric changes to the diode were also performed which allowed for an increase in dose production without sacrificing the time integrated spot characteristics. The combination of changes to both the pulsed power driver and the diode significantly increased the source x-ray intensity

Use of cost benefit analysis in the field of industrial radiography

International Nuclear Information System (INIS)

Croft, J.R.; Webb, G.A.M.; Tattersall, P.; Sutherland, A.; Spence, E.

1988-01-01

Over the past decade NRPB has had a program of work on the development of cost benefit analysis (CBA) techniques in the optimisation of radiological protection. A provisional framework for including suggestions for assigning a value to unit collective dose was published for consultation in 1981/82 and after various interim statements this process culminated in formal advice in 1986. As part of this work, and as part of a project for the Commission of the European Communities (CEC) the NRPB has carried out a number of case studies to demonstrate the practical implementation of ALARA or optimisation of protection using CBA. These techniques, used in conjunction with ALARA audits, are now in general use in the NRPB's Radiation Protection Advisor Service. They have been used for a variety of medical and industrial situations, but mainly in industrial radiography as this is the part of the non-nuclear sector where occupational exposure problems predominate. Three cases are presented as representative examples

Decree No85-968 of 27 August 1986 amending Article R.233-83 of the Labour Code and defining the health and safety conditions to be met by gamma industrial radiography equipment

International Nuclear Information System (INIS)

1986-01-01

This Decree, amending Article R 233-83 of the Labour Code, applies to gamma-ray industrial radiography equipment whether mobile or fixed. It contains specific technical conditions concerning the equipment, in particular, safety devices located at the entry and exit points of the source's shield. The equipment must carry a notice mentioning''Radioactive''prepared by the constructor or the importer of the source, which explains the conditions for handling, setting-up, use and maintenance of the source, including the frequency of revisions. The Decree entered into force on 1 June 1986. (NEA) [fr

Industrial radiography. Gamma radiography

International Nuclear Information System (INIS)

Menetrier, J.

1975-01-01

Informations are given on gamma radiodefectology regulations, entire references and main dispositions applicable to each state of the European Economic Community. The content includes previous arrangements for source acquisition, holding and use of the sources, transport, accidents, civil liability of the source holder, person insurance against radiation hazards and contamination, property insurance, penal liability of the source holder

Recent developments in radiography

International Nuclear Information System (INIS)

Berger, Harold

1982-01-01

Advances in radiography are reviewed and eighty-one references are cited to provide additional information. The review includes information on x-ray sources in terms of output, portability and imaging geometry and detectors in terms of films and screens, electrostatic methods, real-time techniques and solid state devices. Inspection methods utilizing radiations other than x-rays, neutrons and charged particles, expand the inspection problems suitable for radiography. Techniques such as tomography, digital radiography and image enhancement are described. Tomography, in particular, provides excellent capability to characterize materials and discontinuities

Double beam neutron radiography facility

International Nuclear Information System (INIS)

Domanus, J.C.

1977-09-01

The DR1 reactor at Risoe is used as a neutron source for neutron radiography. In the double-beam neutron radiography facility a neutron flux of an intensity of 1.4 and 1.8 x 10 6 n. cm -2 . s -1 reaches the object to be radiographed. The transport and exposure container used for neutron radiography of irradiated nuclear fuel rods is described, and the exposure technique and procedure are reviewed. The mode by which single neutron radiographs are assembled and assessed is described. This report will be published in the ''Neutron Radiography Newsletter''. (author)

Neutron radiography of fuel pins

International Nuclear Information System (INIS)

Jackson, C.N. Jr.; Powers, H.G.; Burgess, C.A.

1975-01-01

Neutron radiography performed with a reactor source has been shown to be a superior radiographic method for the examination of unirradiated mixed oxide fuel pins at the Hanford Engineering Development Laboratory. Approximately 1,700 fuel pins were contained in a sample that demonstrated the capability of the method for detecting laminations, structural flaws, fissile density variation, hydrogenous inclusions and voids in assembled fuel pins. The nature, extent, and importance of the detected conditions are substantiated by gamma autoradiography and by destructive analysis employing alpha autoradiography, electron microprobe and visual inspection. Also, a series of radiographs illustrate the response of neutron radiography as compared to low voltage and high voltage x-ray and gamma source Iridium 192 radiography. (U.S.)

Process waste assessment for the Radiography Laboratory

International Nuclear Information System (INIS)

Phillips, N.M.

1994-07-01

This Process Waste Assessment was conducted to evaluate the Radiography Laboratory, located in Building 923. It documents the processes, identifies the hazardous chemical waste streams generated by these processes, recommends possible ways to minimize waste, and serves as a reference for future assessments of this facility. The Radiography Laboratory provides film radiography or radioscopy (electronic imaging) of weapon and nonweapon components. The Radiography Laboratory has six x-ray machines and one gamma ray source. It also has several other sealed beta- and gamma-ray isotope sources of low microcurie (μCi) activity. The photochemical processes generate most of the Radiography Laboratory's routinely generated hazardous waste, and most of that is generated by the DuPont film processor. Because the DuPont film processor generates the most photochemical waste, it was selected for an estimated material balance

Quality assurance test of a real time radiography system

International Nuclear Information System (INIS)

Yadav, R.K.; Rama, R.; Sharma, A.; Kannan, R.

2005-01-01

Any radiation generating equipment can be used and marketed in India only after obtaining specific type approval certificate from the Competent Authority i.e. Chairman, Atomic Energy Regulatory Board (AERB), Mumbai. Recently AERB has enforced a directive that the Industrial X-ray machines should also be permitted to use only after getting NOC or type approval. Type approval is granted based upon the satisfactory QA test report of the radiation generating equipment. X-ray machines with Real Time Radiography (RTR) facility are used in industrial radiography for faster inspection of equipment's and products online. A standard test protocol was developed for QA tests of a real time radiography system. This will be helpful for evaluation of an industrial X-ray machine. Also above procedure can be used to check a RTR system each day or a system-qualification can be done when the image quality diminishes as recommended by American Society of Testing Material (ASTM). Various tests carried out on a constant potential 450 kV, 10 mA industrial X-ray machine having real time radiography facility to monitor the products online, is described in this paper. (author)

3D reconstruction, a new challenge in industrial radiography

International Nuclear Information System (INIS)

Lavayssiere, B.; Fleuet, E.; Georgel, B.

1995-01-01

In a NDT context, industrial radiography enables the detection of defects through their projection on a film. EDF has studied the benefit that may be brought in terms of localisation and orientation of the defects by the mean of 3D reconstruction using a very limited number of radiographs. The reconstruction issue consists of solving an integral equation of the first kind ; in a noisy context, the reconstruction belongs to the so-called ill-posed class of problem. Appropriate solutions may only be found with the help of regularization technique, by the introduction of a priori knowledge concerning the unknown solution and also by the use of a statistical modelization of the physical process which produces radiographs. Another approach simplifies the problem and reconstructs the skeleton of a defect only. All these methods coming from applied mathematical sciences enable a more precise diagnosis in non-destructive testing of thick inhomogeneous material. (authors). 4 refs., 4 figs

Information extraction from muon radiography data

International Nuclear Information System (INIS)

Borozdin, K.N.; Asaki, T.J.; Chartrand, R.; Hengartner, N.W.; Hogan, G.E.; Morris, C.L.; Priedhorsky, W.C.; Schirato, R.C.; Schultz, L.J.; Sottile, M.J.; Vixie, K.R.; Wohlberg, B.E.; Blanpied, G.

2004-01-01

Scattering muon radiography was proposed recently as a technique of detection and 3-d imaging for dense high-Z objects. High-energy cosmic ray muons are deflected in matter in the process of multiple Coulomb scattering. By measuring the deflection angles we are able to reconstruct the configuration of high-Z material in the object. We discuss the methods for information extraction from muon radiography data. Tomographic methods widely used in medical images have been applied to a specific muon radiography information source. Alternative simple technique based on the counting of high-scattered muons in the voxels seems to be efficient in many simulated scenes. SVM-based classifiers and clustering algorithms may allow detection of compact high-Z object without full image reconstruction. The efficiency of muon radiography can be increased using additional informational sources, such as momentum estimation, stopping power measurement, and detection of muonic atom emission.

Preliminary results from the application of risk matrix method for safety assessment in industrial radiography; Resultados preliminares de la aplicacion del metodo de matrices de riesgo para evaluaciones de seguridad en radiografia industrial

Energy Technology Data Exchange (ETDEWEB)

Lopez G, A.; Cruz, D. [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Barragan 779, Col. Narvarte, 03020 Ciudad de Mexico (Mexico); Truppa, W. [Autoridad Reguladora Nuclear, Buenos Aires (Argentina); Aravena, M. [Comision Chilena de Energia Nuclear, Santiago (Chile); Tamayo, B., E-mail: alopezg@cnsns.gob.mx [Consejo de Seguridad Nuclear, Madrid (Spain)

2015-09-15

Although the uses of ionizing radiation in industry are subject to procedures that provide a high level of safety, experience has shown that equipment failure, human errors, or the combination of both that can trigger accidental exposures may occur. Traditionally, the radiation safety checks whether these industrial practices (industrial radiography, industrial irradiators, among others) are sufficiently safe to prevent similar accidental exposures already occurred, so that becomes dependent on the published information and not always answers questions like: What other events can occur, or what other risks are present? Taking into account the results achieved by the Foro Iberoamericano de Organismos Reguladores Radiologicos y Nucleares, its leading position in the use of techniques of risk analysis in radioactive facilities and the need to develop a proactive approach to the prevention of accidents arising from the use of ionizing radiations in the industry, it intends to apply the risk analysis technique known as Risk Matrix to a hypothetical reference entity for the region in which industrial radiography is performed. In this paper the results of the first stage of this study are shown, that is the identification of initiating events (IE) and barriers that help mitigate the consequences of such IE, so that can appreciate the applicability of this method to industrial radiography services, to reduce the risk to acceptable levels. The fundamental advantage associated with the application of this methodology is that can be applied by the professionals working in the service and identifies specific weaknesses that from the point of view of safety there, so they can be prioritized resources depending on risk reduction. (Author)

Examination of welds by digital radiography

International Nuclear Information System (INIS)

Ekinci, S.

2004-01-01

Industrial radiography is the oldest and most reliable non-destructive test method in the examination and two dimensional evaluation of weld defects. Digital radiographic methods provide more sensitive, faster and more reliable evaluation of defect images. One of the most important factors influencing the contrast and consequently the image quality is the noise on the film caused by scattered radiation. The digital image processing technique can eliminate the noise and improve the image quality. Digital radiography also enables three dimensional evaluation of weld defects. This work describes the use of digital radiography in the evaluation of defects in welds of different configurations by using a laser film digitizing system and an appropriate software programme. Advantages and limitations of the digital technique and conventional film radiography were discussed. (author)

Examination of welds by digital radiography

International Nuclear Information System (INIS)

Ekinci, S.

2004-01-01

Full text: Industrial radiography is the oldest and most reliable non-destructive test method in the examination and two dimensional evaluation of weld defects. Digital radiographic methods provide more sensitive, faster and more reliable evaluation of defect images. One of the most important factors influencing the contrast and consequently the image quality is the noise on the film caused by scattered radiation. The digital image processing technique can eliminate the noise and improve the image quality. Digital radiography also enables three dimensional evaluation of weld defects. This work describes the use of digital radiography in the evaluation of defects in welds of different configurations by using a laser film digitizing system and an appropriate software programme. Advantages and limitations of the digital technique and conventional film radiography were discussed

Application of neutron radiography to the nondestructive testing of fuel elements before and after irradiation

International Nuclear Information System (INIS)

Barbalat, R.; Bayon, G.; Laporte, A.

1983-12-01

The neutron radiography installations of Saclay using collimated neutron sources from reactors for non-destructive testing of nuclear fuels and components of the nuclear industry are described. The first installation in a pool for experimental devices before, during and after irradiation near the core allowing imaging of highly radioactive materials. The second, a dry installation, is used for monitoring active fuel elements. The last is used for inactive materials coming from industry [fr

Axial Tomography from Digitized Real Time Radiography

Science.gov (United States)

Zolnay, A. S.; McDonald, W. M.; Doupont, P. A.; McKinney, R. L.; Lee, M. M.

1985-01-18

Axial tomography from digitized real time radiographs provides a useful tool for industrial radiography and tomography. The components of this system are: x-ray source, image intensifier, video camera, video line extractor and digitizer, data storage and reconstruction computers. With this system it is possible to view a two dimensional x-ray image in real time at each angle of rotation and select the tomography plane of interest by choosing which video line to digitize. The digitization of a video line requires less than a second making data acquisition relatively short. Further improvements on this system are planned and initial results are reported.

Scheme for radiography/tomography with a low-brilliance neutron source at the CPHS

International Nuclear Information System (INIS)

Huang Zhifeng; Xiao Yongshun; Zhang Ran; Li Yuanji; Han Xiaoxue; Shao Beibei; Wang Xuewu; Wei Jie; Loong, C.-K.

2011-01-01

A cold neutron radiography/tomography instrument was designed and will soon undergo construction at the Compact Pulsed Hadron Source (CPHS) of Tsinghua University, China. In this paper, we report the physical design of the instrument and propose a scheme to implement several techniques at a later phase to enhance the utilization of the flux on larger samples. This includes code-aperture, grating-based imaging, prompt gamma-ray analysis and 3D emission CT.

NDE of ceramic insulator blanks by radiography

International Nuclear Information System (INIS)

Sarvanan, S.; Venkatraman, B.; Jayakumar, T.; Baldev Raj

1996-01-01

The production of ceramic insulators in electrical industry involves a number of steps, one of which is the green blank. The defects such as voids and crack can be present in the extruded green blank. One of the best non-destructive evaluation (NDE) technique radiography. This paper deals with the development of methodology based on theoretical modeling for the examination of ceramics by high sensitivity radiography. (author)

Development of gamma exposure chart (Selenium-75) for Industrial Radiography Application

International Nuclear Information System (INIS)

Sapizah Rahim; Shaharudin Sayuti; Noorhazleena Azaman

2011-01-01

Radiographic exposure can be determined by either trial exposure, reference to previous data or using exposure chart. Without previous data, exposure chart is the easiest and economic way to achieve correct exposure. It will minimize re-shoot and time. This paper presents the development of gamma exposure chart for Selenium-75 source. Film radiography method has been chosen for this development using steel step wedge blocks. Agfa Structurix D7 films have been used during the exposure and the optical density of the films was measured by using X-Rite densitometer. Method of development of the chart is explained. The chart is tested on pipe and welded plate test sample and the results are discussed. (author)

Application of (n, f)-radiography for assessment of environmental impact by uranium due to industrial activity

International Nuclear Information System (INIS)

Bertman, E.B.; Vasidov, A.; Tsipin, V.Z.; Tillaev, T.S.

2001-01-01

Neutron induced (n, f)-radiography has been used for assessment of radioactive impact on biota by industrial wastes and exhalation. The objects analyzed were tree leaves which can serve the natural seasonal microelements collectors. Sampling was made in the urban area with two main industrial plants - on the processing of atomic raw material and production of mineral fertilizer. The samples were analyzed by neutron activation analysis (NAA) and neutron induced (n, f)-radiography. The latter technique was used for the study of uranium distribution in a leaf surface. A procedure of the technique was that a detector foil (LEXAN) in a tied contact with a sample surface was subject to thermal neutron exposure in our WWR-SM nuclear reactor. Fission fragments from the 235U(n, f) reaction form radiation damages - tracks - in the surface layer of the detector. Due to close contact of the detector to the sample surface, location of tracks is consistent to location of the determined element. This makes it possible to get a picture of surface distribution of the element and, thus, to get an idea on genesis of pollution with this element. There are two principal ways for intake of pollutant elements in plants, namely, through the root system from the soil, and through the aerosol, dust and/or rain deposition on leaves. Presence of dense track spots like clusters or stars in the produced radiographs asserts their genesis was due to industrial disposal and exhalation. The average uranium concentrations in the leaves cover the range of 0.026 to 0.83 ppm. Based on the experimental data, uranium mapping of the explored territory has been made. Epicenter of the highest uranium level field was spatially consistent to location of the industrial plants, and, therefore, most probably, was generated by their activity

Revisited the mathematical derivation wall thickness measurement of pipe for radiography

Energy Technology Data Exchange (ETDEWEB)

Hamzah, A.R.; Amir, S.M.M. [Non Destructive Testing(NDT) Group, Industrial Technology Div., Malaysian Nuclear Agency, Selangor (Malaysia)

2007-07-01

Wall thickness measurement of pipe is very important of the structural integrity of the industrial plant. However, the radiography method has an advantage because the ability of penetrating the insulated pipe. This will have economic benefit for industry. Moreover, the era of digital radiography has more advantages because the speed of radiographic work, less exposure time and no chemical used for film development. Either the conventional radiography or digital radiology, the wall thickness measurement is using the tangential radiography technique (TRT). In case, of a large diameter, pipe (more than inches) the determination maximum penetration wall thickness must be taken into the consideration. This paper is revisited the mathematical derivation of the determination of wall thickness measurement based on tangential radiography technique (TRT). The mathematical approach used in this derivation is the Pythagoras theorem and geometrical principles. In order to derive the maximum penetration wall thickness a similar approach is used. (authors)

Radioactive sources production in the Boris Kidric Institute of nuclear sciences

International Nuclear Information System (INIS)

Radosavljevic, B.; Nemoda, Dj.; Memedovic, T.; Bircanin, LJ.

1978-01-01

Since 1960, in the Laboratory for radioisotopes production of the Institute isotopes were produced for industrial, medical and research purposes. From the beginning, this activity was developed in two directions: 1. sealed sources, for industrial radiography, teletherapy Cobalt, later for lightning arresters, level meters, densitometers etc., 2. radioactive sources that need chemical treatment for different applications in industry and research. This paper lists the types of radioactive sources and methods for production [sr

Multidimensional analysis in industrial radiography

International Nuclear Information System (INIS)

Lavayssiere, B.; Georgel, B.

1992-01-01

EDF uses non-destructive testing by X or gamma-ray radiography for routine nozzle inspection in nuclear power plants. The images obtained are examined by radiographic specialists in order to detect, identify and quantify any defects, but the quality of the radiograms and the small size of the defects make their work extremely difficult. It is for these reasons that EDF developed ENTRAIGUES, a digital package for the processing and aid in interpretation of images generated by radiographical inspections, aimed at: -digitizing the radiographic films to be appraised, - facilitating analysis of the digitized radiograms. Defect orientation is estimated by 3D reconstruction of the component being inspected, based on a limited number of its projections. (authors). 11 figs., 6 refs

Industrial Applications of radioisotopes and radiation technology and Agency's role

International Nuclear Information System (INIS)

Ramamoorthy, N.; Haji-Saeid, M.

2004-01-01

Applications of radioisotopes and radiation technology are contributing significantly in many areas of science and technology, industry and environment, towards sustainable development, improving the quality of life and cleaner and safer national industries. There are three major classes impacting industrial scale operations, namely, (a) radiation processing/treatment, (b) radiotracer and sealed source techniques to monitor industrial processes/columns/vessels and (c) industrial gamma radiography and tomography. Radiation processing applying gamma sources and electron accelerators for material treatment/modification is an established technology. There are over 160 gamma industrial irradiators and 1300 industrial electron accelerators in operation worldwide. Development of new materials, especially for health care and environment protection, and advanced products (for electronics, solar energy systems, biotechnology etc) are the main objectives of R and D activity in radiation processing technology. The International Atomic Energy Agency (IAEA, Agency) is involved in supporting both the development and transfer of radiation technology. Thanks to Agency's efforts, advanced radiation processing centres have been established in many Member States (MS), e.g. Malaysia, Egypt, Iran, Poland, Brazil, Hungary. Hydrogel dressing for wounds, radiation vulcanised latex, degraded natural polymer are examples of useful product outcomes. Demonstration of effective treatment of flue gas in pilot plant as well as industrial scale and industrial wastewater in pilot plant scale has shown promise for tackling industrial emissions/effluents using electron beam machines. Industrial radiotracer and gamma sealed source techniques are largely used for analyzing industrial process systems. Initially used as trouble-shooting measures, they play a vital role in process parameter optimization, improved productivity, on-line monitoring and could lead to even pre-commissioning benchmarking. Gamma

Industrial Applications of radioisotopes and radiation technology and Agency's role

International Nuclear Information System (INIS)

Ramamoorthy, N.; Haji-Saeid, M.

2004-01-01

Full text: Applications of radioisotopes and radiation technology are contributing significantly in many areas of science and technology, industry and environment, towards sustainable development, improving the quality of life and cleaner and safer national industries. There are three major classes impacting industrial scale operations, namely, (a) radiation processing/treatment, (b) radiotracer and sealed source techniques to monitor industrial processes/columns/vessels and (c) industrial gamma radiography and tomography. Radiation processing applying gamma sources and electron accelerators for material treatment/modification is an established technology. There are over 160 gamma industrial irradiators and 1300 industrial electron accelerators in operation worldwide. Development of new materials, especially for health care and environment protection, and advanced products (for electronics, solar energy systems, biotechnology etc) are the main objectives of R and D activity in radiation processing technology. The International Atomic Energy Agency (IAEA, Agency) is involved in supporting both the development and transfer of radiation technology. Thanks to Agency's efforts, advanced radiation processing centres have been established in many Member States (MS), e.g. Malaysia, Egypt, Iran, Poland, Brazil, Hungary. Hydrogel dressing for wounds, radiation vulcanised latex, degraded natural polymer are examples of useful product outcomes. Demonstration of effective treatment of flue gas in pilot plant as well as industrial scale and industrial wastewater in pilot plant scale has shown promise for tackling industrial emissions/effluents using electron beam machines. Industrial radiotracer and gamma sealed source techniques are largely used for analyzing industrial process systems. Initially used as trouble-shooting measures, they play a vital role in process parameter optimization, improved productivity, on-line monitoring and could lead to even pre

Digital radiography: description and user's guide

International Nuclear Information System (INIS)

Berthel, A.; Bonin, Th.; Cadilhon, S.; Thiery, Ch.; Chatellier, L.; Kaftandjian, V.; Honorat, Ph.; Torrent, J.; Le Brun, A.; Maglaive, J.C.; Moreau, Ph.; Pettier, J.L.; Rebuffel, V.; Roenelle, P.; Roussilhe, J.; Staat, St.; Tahon, M.

2007-01-01

The presented document arises from the work of the group 'Digital Radiography and sensors' of COFREND. It is a collective work of synthesis aimed to analyze the quality parameters of digital images influencing the answer and the diagnosis brought to a given industrial problem. Five families of digital sensors have been studied: 1. Image Intensifier coupled with CCD devices - 2. scintillators coupled with a CCD device- 3. Flat Panels with indirect conversion - 4. Flat Panels with direct electric conversion - 5. Photostimulable Storage Phosphor Screens). In particular, concerning a complete imaging chain, it deals with the notions of magnification, blur (unsharpness) (geometrical, kinetic or internal to the very sensor), noises, scattered radiation, spatial resolution, which is different from the one of analog detectors such as films, Contrast to Noise Ratio (CNR), sensitivity using IQIs, dynamic range, detection quantum efficiency, persistence and temporal resolution. This document is not a standard; it must be understood as a user's guide, and it approaches some essentials corrections to bring to a sensor in order to optimize his efficiency without losing information during the pre-processing phase in the radiographic acquisition. It also introduces some image processing tools commonly used. It can be used as a source document to the future elaboration of a standardisation document. It augurs not at all of the choice of a digital sensor with regard to the traditional radiographic film, but gives bases of reflection to a radio user for a sensible transfer from the classic radiography to the digital radiography. (authors)

Radioprotection of industrial radiography

International Nuclear Information System (INIS)

Abela, G.; Bonaventure, P.; Jupin, L.; Truchi, F.

2006-01-01

The EDF Nuclear Power Division (N.P.D.) conducts a substantial number of industrial g-ray inspections: about 40.000 inspections are conducted annually on the nuclear fleet by contractors as H.O.R.U.S. Company. Point sources of Iridium 192 are generally used. In normal configurations, the activity of these sources can go up to 4.4 T.Bq (120 Ci), inducing - at a range of 1 meter - such a high dose equivalent rate that the value of 20 mSv is reached in a little more than 2 minutes. To date, no exceeding of the regulatory limit has been observed within EDF, but during the observation of events, a practice that has been in effect for many years, 'low-level events', such as unplanned exposures lower than the regulatory limits, were noted. N.P.D. management and contractors thus decided to take particular actions in the field. An analysis of unplanned exposures was carried out. This analysis related to 1: The 'human factor' analysis showed that the activity, which can seem 'simple' due to its seemingly basic constituent parts, taken in isolation, therefore appears easy to accomplish. In fact, completion of each point requires very extensive technical training, a complex planning file has to be compiled as there are many interfaces with other players, is linked to other activities that have to be carried out prior to the g-ray inspection. It requires preparation of the areas, with measures taken to prohibit access, and requires adaptation to physical conditions (temperature, lighting, noise, dose rate) and sometimes very difficult access conditions. The operators 'error' and lack of attention or vigilance cannot thus be considered by a preventer as being a satisfactory cause of incidents or accidents, within the scope of an ongoing improvement initiative: Vigilance means work. 2: Analysis of material causes did not highlight causes related to the equipment used, but camera ergonomics could be improved. Changes to EDF rules focused on: Compulsory and systematic use of

Radiography of X-ray in coral reefs

International Nuclear Information System (INIS)

Djoli Soembogo

2016-01-01

The application of X-ray radiography has been developed and it is already widely used in metal materials such as metal steel and carbon steel. This radiography using a source of radiation from X-ray machines. This research attempts to use the application of digital radiography X-ray source and use scanner Epson V700 positive films media for digitization results of conventional radiographic films on coral reefs. It has been testing radiography using Fuji film 100 to get the contrast medium, the sensitivity of the medium and image quality is good, Single Wall Single Image method , and using the media scanner films positive and X-ray sources, observation parameter are density radiographic film and the defect shape. Radiography uses Fuji film 100 to obtain a good contrast medium, good medium sensitivity and good quality image. Radiography of X-ray on coral reefs aims to find defects or discontinuities coral reefs such as porosity which would interfere with the determination of the age of the coral reefs. X-ray exposure time is 1 seconds for a thickness of 5.45 mm and 5.60 mm coral reefs by using a high voltage X-ray machine Rigaku of 130 kV. The result of the positive film scanner in the form of digital radiography that allows for the transfer of digital data or digital computerized data storage. The test results of radiographic on coral reefs with Single Wall Single Image method obtained radiographic film density parameter for Fuji film 100 on coral reefs No. 2 are 2.55; 2.53; 2.59 and on coral reefs No. 4 are 2.62; 2.65; 2.66, unsharpness geometric of radiographic results obtained 0.022 mm and 0.023 mm, sensitivity radiography are 1.648% and 1.604%. No defect found of Porosity that is significant. Status is acceptable for Fuji film 100, because the density of the film is in conformity with the standards referred to. Status of coral reefs No. 2 and No. 4 can be accepted, because it has conformed with the standards referred. (author)

Cold neutron radiography using low power accelerator

International Nuclear Information System (INIS)

Kiyanagi, Yoshiaki; Iwasa, Hirokatu

1993-01-01

A cold neutron source which can be adopted at a low power accelerator was studied. Time-of-flight radiography using the cold neutron source was performed. It is suggested that time-of-flight cold neutron radiography has possibility to distinguish the materials more clearly than the traditional film method since large contrast differences can be obtained by using digital data of the neutron intensity at different energies from thermal to cold region. Material will be identified at the same time by this method. (author)

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

International Nuclear Information System (INIS)

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

2004-01-01

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

Production of sealed sources

International Nuclear Information System (INIS)

Bandi, L.N.

2016-01-01

Radioisotope production has been an ongoing activity in India since the sixties. Radioisotopes find wide-ranging applications in various fields, including industry, research, agriculture and medicine. Board of Radiation and Isotope Technology, an industrial unit of Department of Atomic Energy is involved in fabrication and supply of wide variety of sealed sources. The main radioisotopes fabricated and supplied by BRIT are Cobalt-60, Iridium-192. These isotopes are employed in industrial and laboratory irradiators, teletherapy machines, radiography exposure devices, nucleonic gauges. The source fabrication facilities of BRIT are located at Rajasthan Atomic Power Project Cobalt-60 Facility (RAPPCOF), Kota, Radiological Laboratories Group (RLG) and High Intensity Radiation Utilization Project (HIRUP) at Trombay

Ambulating radiography

International Nuclear Information System (INIS)

Magnusson, K.

1989-01-01

Strong gamme or X-ray sources are utilized for non-destructive testing of i.e. bridges. The activities involve certain risks of accident that might lead to serious injuries caused by radiation. The National Institute of Radiation Protection has during the laste decade greatly yhe inspection rate in this area. It has today made controls of most enterprieses running ambulating radiography. (O.S.)

Search for adequate quality standards for neutron radiography of nuclear fuel

International Nuclear Information System (INIS)

Domanus, J.C.

1983-01-01

Unlike in other fields of industrial radiography, where standard methods and procedures are used to control the quality of the radiographic image, no such standard exists for neutron radiography of nuclear fuel. To fill that gap it was felt that standardization work ought to be started in that field, too. Accordingly in 1979 an Euratom Neutron Radiography Working Group was constituted, which initiated standardization work in the field of neutron radiography of nuclear fuel. Finding adequate standards for image quality of neutron radiographs and checking the accuracy of dimension measurements from them were given first priority. (Auth.)

Atomic Energy Control Regulations: interpretation of revisions relating to industrial radiography

International Nuclear Information System (INIS)

1983-09-01

The purpose of this document is to provide assistance to those affected by section 18 to 18.23 of the Canadian Atomic Energy Control Regulations. Words, phrases, and concepts that are specific to these Regulations are explained herein. However, the corresponding sections of the Regulations should be examined to obtain the exact wording. Although sections 18 to 18.23 of the Canadian Atomic Energy Control Regulations apply to both neutron and gamma radiography, this guide has been written for only the latter. Persons engaged in neutron radiography should consult the Atomic Energy Control Board (AECB)

Low energy 7Li(p,n)7Be neutron source (CANUTRON)

International Nuclear Information System (INIS)

Lone, M.A.; Ross, A.M.; Fraser, J.S.; Schriber, S.O.; Kushneriuk, S.A.; Selander, W.N.

1982-04-01

Characteristics of a neutron source based on the 7 Li(p,n) reaction at 2.5 MeV are investigated. It is shosn that with a 10-50 mA beam current this reaction provides a useful source for neutron radiography and other industrial applications

Industrial radiography on radiographic paper

International Nuclear Information System (INIS)

Domanus, J.C.

1977-11-01

An investigation was performed to compare the quality of radiographic paper with that of X-ray film, after a review had been made of the rather scarce literature on the subject. The equipment used throughout the investigation is described, and characteristic curves for Agfa-Gevaert and Kodak papers exposed with different intensifying screens in the low and intermediate voltage range are reproduced. The relative speed, contrast and exposure latitude were computed from these curves. The quality of the radiographic image was checked on U/Al blocks and plates, Al and Fe blocks, and fiber-reinforced composites. Exposure charts for Al and Fe were made for various paper and screen combinations. Both the sharpness of the radiographic image as well as the influence of processing on speed and contrast were checked. Examples are given of the practical application of the paper for radiography of castings, weldings, solderings, assemblies, etc. (author)

Quality assurance procedure for an industrial radiography linear accelerator

International Nuclear Information System (INIS)

Vishwakarma, R.R.; Kannan, R.; Yadav, R.K.

2001-01-01

Any radiation generating equipment can be marketed and used in India, only after obtaining specific type approval from the Competent Authority i.e. Chairman, Atomic Energy Regulatory Board (AERB). Generally linear accelerators are allowed to be used in the country based on the type approval issued by the regulatory authority of the country of its origin. So type approval of imported linear accelerators do not involve many parameters to be tested in our country. However for an indigenous accelerator, test procedures are to be defined and the same are to be followed during type approval process. No such protocol is available for linear accelerators used in industrial radiography. Recently some Indian manufacturers have started manufacturing and supplying such accelerators. A need for developing an indigenous protocol for type approval/NOC of such accelerators has arisen and the same has been developed. Various requirements for such protocol are discussed in this paper. Measurements have been performed on one of the 4 MV indigenous unit. Results of such measurements are also presented. Need for a regular periodic quality assurance program is necessary for imported as well as indigenous accelerators. A program for such quality assurance is also listed in the paper. (author)

Industrial ion sources broadbeam gridless ion source technology

CERN Document Server

Zhurin, Viacheslav V

2012-01-01

Due to the large number of uses of ion sources in academia and industry, those who utilize these sources need up to date and coherent information to keep themselves abreast of developments and options, and to chose ideal solutions for quality and cost-effectiveness. This book, written by an author with a strong industrial background and excellent standing, is the comprehensive guide users and developers of ion sources have been waiting for. Providing a thorough refresher on the physics involved, this resource systematically covers the source types, components, and the operational parameters.

Stereoscopic radiographic images with gamma source encoding

International Nuclear Information System (INIS)

Strocovsky, S.G.; Otero, D

2012-01-01

Conventional radiography with X-ray tube has several drawbacks, as the compromise between the size of the focal spot and the fluence. The finite dimensions of the focal spot impose a limit to the spatial resolution. Gamma radiography uses gamma-ray sources which surpass in size, portability and simplicity to X-ray tubes. However, its low intrinsic fluence forces to use extended sources that also degrade the spatial resolution. In this work, we show the principles of a new radiographic technique that overcomes the limitations associated with the finite dimensions of X-ray sources, and that offers additional benefits to conventional techniques. The new technique called coding source imaging (CSI), is based on the use of extended sources, edge-encoding of radiation and differential detection. The mathematical principles and the method of images reconstruction with the new proposed technique are explained in the present work. Analytical calculations were made to determine the maximum spatial resolution and the variables on which it depends. The CSI technique was tested by means of Monte Carlo simulations with sets of spherical objects. We show that CSI has stereoscopic capabilities and it can resolve objects smaller than the source size. The CSI decoding algorithm reconstructs simultaneously four different projections from the same object, while conventional radiography produces only one projection per acquisition. Projections are located in separate image fields on the detector plane. Our results show it is possible to apply an extremely simple radiographic technique with extended sources, and get 3D information of the attenuation coefficient distribution for simple geometry objects in a single acquisition. The results are promising enough to evaluate the possibility of future research with more complex objects typical of medical diagnostic radiography and industrial gamma radiography (author)

Digital radiography

International Nuclear Information System (INIS)

Coulomb, M.; Dal Soglio, S.; Pittet-Barbier, L.; Ranchoup, Y.; Thony, F.; Ferretti, G.; Robert, F.

1992-01-01

Digital projection radiography may replace conventional radiography some day, provided it can meet several requirements: equal or better diagnostic effectiveness of the screen-film systems; reasonable image cost; real improvement in the productivity of the Departments of Imaging. All digital radiographic systems include an X-ray source, an image acquisition and formatting sub-system, a display and manipulation sub-system, and archiving subsystem and a laser editing system, preferably shared by other sources of digital images. Three digitization processes are available: digitization of the radiographic film, digital fluorography and phospholuminescent detectors with memory. The advantages of digital fluoroscopy are appealing: real-time image acquisition, suppression of cassettes; but its disadvantages are far from negligible: it cannot be applied to bedside radiography, the field of examination is limited, and the wide-field spatial resolution is poor. Phospholuminescent detectors with memory have great advantages: they can be used for bedside radiographs and on all the common radiographic systems; spatial resolution is satisfactory; its current disadvantages are considerable. These two systems, have common properties making up the entire philosophy of digital radiology and specific features that must guide our choice according to the application. Digital fluorography is best applied in pediatric radiology. However, evaluation works have showed that it was applicable with sufficient quality to many indications of general radiology in which a fluoroscopic control and fast acquisition of the images are essential; the time gained on the examination may be considerable, as well as the savings on film. Detectors with memory are required for bedside radiographs, in osteoarticular and thoracic radiology, in all cases of traumatic emergency and in the resuscitation and intensive care departments

An improved fast neutron radiography quantitative measurement method

International Nuclear Information System (INIS)

Matsubayashi, Masahito; Hibiki, Takashi; Mishima, Kaichiro; Yoshii, Koji; Okamoto, Koji

2004-01-01

The validity of a fast neutron radiography quantification method, the Σ-scaling method, which was originally proposed for thermal neutron radiography was examined with Monte Carlo calculations and experiments conducted at the YAYOI fast neutron source reactor. Water and copper were selected as comparative samples for a thermal neutron radiography case and a dense object, respectively. Although different characteristics on effective macroscopic cross-sections were implied by the simulation, the Σ-scaled experimental results with the fission neutron spectrum cross-sections were well fitted to the measurements for both the water and copper samples. This indicates that the Σ-scaling method could be successfully adopted for quantitative measurements in fast neutron radiography

Occupational exposures in industrial application of radiation during 1999-2008

International Nuclear Information System (INIS)

Sanaye, Suresh Shantaram; Baburajan, Sujatha; Pawar, Suresh Ganpat; Nalawade, Shailesh Krishna; Sapra, Balvinder Kaur

2012-01-01

Radiation sources are used in various industrial applications like industrial radiograph, industrial irradiation, industrial fluoroscopy, nucleonic gauges, well logging etc., Gamma, beta X-ray as well as neutron sources are used for various applications. Number of radiation workers in this field has increased over the years. Due to operating conditions prevailing during the exposure as well as the strength of the sources used in some of the applications, radiation protection plays an important role in this field. Analysis of doses received by radiation workers in industry provides information on trends of doses as well as adequateness of radiation protection practices followed in this sector. In India, National Occupational Dose Registry System (NODRS) of Radiological Physics and Advisory Division (RPAD), Bhabha Atomic Research Centre (BARC) maintains personnel dose information of monitored radiation workers in the country. Analysis of occupational dose data of industrial radiation workers for last 10 years, i.e., 1999-2008 has been presented in this paper. It is observed that even though there is an increase in monitored radiation workers, percentage of persons receiving radiation exposure has come down during this period. There is also a decrease in the average annual dose as well as the collective dose. Further analysis of sub-categories shows that industrial radiography operations are the main contributor for collective dose (about 77%) followed by well logging and industrial X-ray operations (about 8% each). Thus, in addition to industrial radiography attention is also to be given to operations in these areas. (author)

System for uncollimated digital radiography

Science.gov (United States)

Wang, Han; Hall, James M.; McCarrick, James F.; Tang, Vincent

2015-08-11

The inversion algorithm based on the maximum entropy method (MEM) removes unwanted effects in high energy imaging resulting from an uncollimated source interacting with a finitely thick scintillator. The algorithm takes as input the image from the thick scintillator (TS) and the radiography setup geometry. The algorithm then outputs a restored image which appears as if taken with an infinitesimally thin scintillator (ITS). Inversion is accomplished by numerically generating a probabilistic model relating the ITS image to the TS image and then inverting this model on the TS image through MEM. This reconstruction technique can reduce the exposure time or the required source intensity without undesirable object blurring on the image by allowing the use of both thicker scintillators with higher efficiencies and closer source-to-detector distances to maximize incident radiation flux. The technique is applicable in radiographic applications including fast neutron, high-energy gamma and x-ray radiography using thick scintillators.

Preparation of very small point sources for high resolution radiography

International Nuclear Information System (INIS)

Case, F.N.

1976-01-01

The need for very small point sources of high specific activity 192 Ir, 169 Yb, 170 Tm, and 60 Co in non-destructive testing has motivated the development of techniques for the fabrication of these sources. To prepare 192 Ir point sources for use in examination of tube sheet welds in LMFBR heat exchangers, 191 Ir enriched to greater than 90 percent was melted in a helium blanketed arc to form spheres as small as 0.38 mm in diameter. Methods were developed to form the roughly spherical shaped arc product into nearly symmetrical spheres that could be used for high resolution radiography. Similar methods were used for spherical shaped sources of 169 Yb and 170 Tm. The oxides were arc melted to form rough spheres followed by grinding to precise dimensions, neutron irradiation of the spheres at a flux of 2 to 3 x 10 15 nv, and use of enriched 168 Yb to provide the maximum specific activity. Cobalt-60 with a specific activity of greater than 1100 Ci/g was prepared by processing 59 Co that had been neutron irradiated to nearly complete burnup of the 59 Co target to produce 60 Co, 61 Ni, and 62 Ni. Ion exchange methods were used to separate the cobalt from the nickel. The cobalt was reduced to metal by plating either onto aluminum foil which was dissolved away from the cobalt plate, or by plating onto mercury to prepare amalgam that could be easily formed into a pellet of cobalt with exclusion of the mercury. Both methods are discussed

Safety regulations of radiation sources in industry in the Philippines

Energy Technology Data Exchange (ETDEWEB)

Borras, A M [Licensing and Evaluation Section, Nuclear Regulations Licensing and Safeguards Division, Philippine Nuclear Research Institute, Diliman, Quezon City (Philippines)

1992-12-31

The Philippine Nuclear Research Institute (PNRI) by virtue of Republic Act 2067, as amended, Republic Act 5207 and Executive Order 128 (1987), was mandated to advance and regulate the safe and peaceful applications of nuclear science and technology in the Philippines. The PNRI was formerly the Philippine Atomic Energy Commission established in 1958. This report aims to share the experiences of the PNRI on licensing and regulating the safe use of radioactive materials in industry, particularly in industrial gamma radiography, nuclear gauges and radioactive tracers. It enumerates the licensing and enforcement procedures. Some common problems encountered in the licensing and enforcement activities and comments of future plans to resolve the problems were also discussed. (Author).

Safety regulations of radiation sources in industry in the Philippines

International Nuclear Information System (INIS)

Borras, A.M.

1991-01-01

The Philippine Nuclear Research Institute (PNRI) by virtue of Republic Act 2067, as amended, Republic Act 5207 and Executive Order 128 (1987), was mandated to advance and regulate the safe and peaceful applications of nuclear science and technology in the Philippines. The PNRI was formerly the Philippine Atomic Energy Commission established in 1958. This report aims to share the experiences of the PNRI on licensing and regulating the safe use of radioactive materials in industry, particularly in industrial gamma radiography, nuclear gauges and radioactive tracers. It enumerates the licensing and enforcement procedures. Some common problems encountered in the licensing and enforcement activities and comments of future plans to resolve the problems were also discussed. (Author)

Fast neutron (14.5 MeV) radiography: a comparative study

International Nuclear Information System (INIS)

Klann, R.T.

1996-01-01

Fast neutron (14.5 MeV) radiography is a type of non-destructive analysis tool that offers its own benefits and drawbacks. Because cross-sections vary with energy, a different range of materials can be examined with fast neutrons than can be studied with thermal neutrons, epithermal neutrons, or x-rays. This paper details these differences through a comparative study of fast neutron radiography to the other types of radiography available. The most obvious difference among the different types of radiography is in the penetrability of the sources. Fast neutrons can probe much deeper and can therefore obtain details of the internals of thick objects. Good images have been obtained through as much as 15 cm of steel, 10 cm of water, and 15 cm of borated polyethylene. In addition, some objects were identifiable through as much as 25 cm of water or 30 cm of borated polyethylene. The most notable benefit of fast neutron radiography is in the types of materials that can be tested. Fast neutron radiography can view through materials that simply cannot be viewed by X rays, thermal neutrons, or epithermal neutrons due to the high cross-sections or linear attenuation coefficients involved. Cadmium was totally transparent to the fast neutron source. Fast neutron radiography is not without drawbacks. The most pronounced drawback has been in the quality of radiograph produced. The image resolution is only about 0.8 mm for a 1.25 cm thick object, whereas, other forms of radiography have much better resolution

A Glance on the Safety Culture in Industrial Gamma Radiography in the Philippines: Regulatory Body Perspective

International Nuclear Information System (INIS)

Borras, A.M.

2016-01-01

The current version of the Code of PNRI Regulations (CPR) Part 11 was published in the Official Gazette on 2010. It is just a year ahead of the publication of the IAEA Specific Safety Guide No. 11. In view of these, radiation safety culture in the practice of industrial gamma radiography was not yet fully introduced in the said national regulations in the country. However, it should not be a reflection that the radiation workers in the country specifically in the said field of practice do not exercise positive safety culture. The Nuclear Regulatory Division (NRD)—regulatory arm, although not yet separated from the Philippine Nuclear Research Institute (PNRI0) as mandated by law — the promotional organization, has a well established and systemic regulatory infrastructure. It is attested by several studies and reports, among others. This study aims to assess the status of the existing safety culture in the conduct of industrial gamma radiography in the country through personnel perception survey of the radiation workers, i.e., managers, radiation safety officers, radiographers and radiographer’s assistants, based on the IAEA five characteristics of safety culture stipulated in the IAEA Safety Guide No. GS-G-3.5, “The Management System for Nuclear Installations”. It is assessed by the NRD of the PNRI. Also, the study determines the existence of safety culture as to the perspective of NRD through observations on the conduct of radiographic operations and walk-through of the facility while using the three-level Schein Model, i.e., “artefacts”, “espoused values” and “basic assumptions” and document reviews, among others

Industrial applications of radiations

International Nuclear Information System (INIS)

Gallien, C.L.

1988-01-01

Radiation processing refers to the use of ionizing radiation to initiate chemical or biological changes in various materials as a substitute for conventional thermal or chemical processes. The method was inroduced in the industrial field 30 years ago and is now being widely used for numerous applications, among which industrial radiography, polymer modification, sterilization or decontamination, and food preservation. Both electron beam accelerators and gamma sources can be used, depending mainly of the amount of radiation and the penetration required. Radiation processing presents an increasing economical importance; in 1986 the market volume of ionized products ranged 3 billion $ [fr

Non-destructive evaluation utilizing imaging plates for field radiography applications

International Nuclear Information System (INIS)

White, Brian S.

2016-01-01

The oil and gas industry has utilized film radiography for the evaluation of pipeline welds for many years. The world has evolved, and today people are easily sharing digital images as part of the information revolution. Computed radiography is ready to replace film radiography for portable outdoor use applications. Computed radiography technology adoption has been contingent upon achieving acceptable image quality and getting enough imaging plate use cycles to be profitable. Image quality is dependent upon shot conditions, imaging plate type, reader settings, and scatter control. Likewise, the number of achievable use cycles is dependent upon the imaging plate design for durability and the user's operating environment. This presentation reviews the basic principles of storage phosphor imaging plates. Usage criteria and guidelines for optimum image quality and maximized overall use cycles will be discussed for various imaging plate types. A comparison of film and computed radiography imaging plate technology will be presented.

Dynamic neutron radiography instrumentation and applications in Central Europe

International Nuclear Information System (INIS)

Balasko, M.

1996-01-01

Characteristic features of simultaneous dynamic neutron and gamma radiography installations built in the last ten years at the Budapest/Hungary and at the Seibersdorf/Austria research reactors are surveyed. For image detection scintillation detectors and a low-light level television camera with video output are used, thereby providing the possibility for visualizing medium speed movements inside the investigated object. The radiography stations have been used for inspecting industrial products, with the aim of research and development. (orig.)

Digital radiography: description and user's guide

Energy Technology Data Exchange (ETDEWEB)

Berthel, A. [Cryospace, 78 - Les Mureaux (France); Bonin, Th. [CEA Valduc, 21 - Is-sur-Tille (France); Cadilhon, S.; Thiery, Ch. [CEA Bruyeres-le-Chatel, 91 (France); Chatellier, L. [Electricite de France (EDF-RD), Recherche et Developpement, 78 - Chatou (France); Kaftandjian, V. [Lyon Univ., INSA Lab. Controle Non Destructif par Rayonnements Ionisants (CNDRI), 69 (France); Honorat, Ph.; Torrent, J. [SNECMA, 75 - Paris (France); Le Brun, A. [Electricite de France, 78 - Chatou (France); Maglaive, J.C. [Euromev, 78 - Buc (France); Moreau, Ph. [General Electric Industrial Inspection Technologies, 69 - Limonest (France); Pettier, J.L. [CEA Cadarach, Dir. de l' Energie Nucleaire, 13 - Saint Paul lez Durance (France); Rebuffel, V. [CEA Grenoble, Lab. d' Electronique et de Technologie de l' Informatique (LETI), 38 (France); Roenelle, P. [Centre d' Etudes Techniques de l' Equipement, 69 - Bron Lyon (France); Roussilhe, J. [Carestream Health France SA, 71 - Chalon/Saone (France); Staat, St.; Tahon, M. [Cegelec, 91 - Bretigny sur Orge (France)

2007-07-01

The presented document arises from the work of the group 'Digital Radiography and sensors' of COFREND. It is a collective work of synthesis aimed to analyze the quality parameters of digital images influencing the answer and the diagnosis brought to a given industrial problem. Five families of digital sensors have been studied: 1. Image Intensifier coupled with CCD devices - 2. scintillators coupled with a CCD device- 3. Flat Panels with indirect conversion - 4. Flat Panels with direct electric conversion - 5. Photostimulable Storage Phosphor Screens). In particular, concerning a complete imaging chain, it deals with the notions of magnification, blur (unsharpness) (geometrical, kinetic or internal to the very sensor), noises, scattered radiation, spatial resolution, which is different from the one of analog detectors such as films, Contrast to Noise Ratio (CNR), sensitivity using IQIs, dynamic range, detection quantum efficiency, persistence and temporal resolution. This document is not a standard; it must be understood as a user's guide, and it approaches some essentials corrections to bring to a sensor in order to optimize his efficiency without losing information during the pre-processing phase in the radiographic acquisition. It also introduces some image processing tools commonly used. It can be used as a source document to the future elaboration of a standardisation document. It augurs not at all of the choice of a digital sensor with regard to the traditional radiographic film, but gives bases of reflection to a radio user for a sensible transfer from the classic radiography to the digital radiography. (authors)

The industrial radiography service in Brazil concerning to the radiation protection aspect

International Nuclear Information System (INIS)

Martins, M.M.

1994-01-01

A study about the industrial radiography situation in Brazil, concerning to the radiation protection aspects is shown. With this purpose it was made an inventory, with utilization of the file of facilities officially registered in industrial application from Brazilian Nuclear Energy Commission (CNEN). It was evaluated the quantity of accelerators), radiation monitors and radiation workers (health physics, operator). As quality and performance indicators of radiation protection the mean doses and the collective doses were used, and their variation from 1987 to 1990. As deficiency signals of radiological protection programs and procedures were utilized the 175 abnormal event occurred (radiological accident and emergency situation) from 1976 to 1992, after an analysis of their causes. The results showed that, for around 2000 monitored workers, the mean dose equivalent was between 0.83 to 2.70 mSv, and the collective dose, between 1.54 and 6.18 Sv.man, from 1987 to 1990. In this period, it was verified a tendency for reduction of means dose and collective dose values. It indicates a possible improvement of radiation protection services or an influence of economical situation of the country. From 175 abnormal events analysed, 456 persons were exposed, with 7.2% of them receiving doses above 50 mSv. These results were compared with those from others countries, such as United Kingdom and united States. (author). 76 refs, 16 figs, 24 tabs

Recovery from Iridium-192 flakes of a radioactive source for industrial use after a radiation incident

International Nuclear Information System (INIS)

Cruz, W.H.; Zapata, L.A.

2013-01-01

The Iridium-192 ( 192 Ir) is the most used and ideal for industrial radiography applications, especially in petrochemical plants and pipelines and provides better contrast sensitivity for thick (25.4 mm). This source has constructive sealed double encapsulation, the internal capsule containing stainless steel to radioactive material in the form of flakes and welded with TIG process. The radiological incident happened at a gas station fuel sales in circumstances in which there was a homogeneity test welds a tank, the flakes or Ir-192 fell off his ponytail and left scattered over an area of 2 m 2 , some fell flat areas and other land so collected in lead shielding and metal container and ground source. Full recovery of the leaflets was performed at the Division of radioactive waste management (GRRA) gaining a total of 22 flakes with no radiation risk to staff performance and installation and the conclusion was reached that the misapplicaion of TIG welding was the main cause the incident. (author)

A Survey of Industrial Involvement in Open Source

OpenAIRE

Røsdal, Andreas

2006-01-01

This thesis presents the results of an explorative survey of industrial involvement in open source. The survey is performed in collaboration with participants from the European ITEA project, COSI (Co-development using inner & Open source in Software Intensive products). The survey was performed to explore aspects of industrial involvement in open source, as industrial management of open source project, industrial use of open source components, related development, and communication processes,...

Radiography

Science.gov (United States)

Gardner, C. G.

1973-01-01

Radiography is discussed as a method for nondestructive evaluation of internal flaws of solids. Gamma ray and X-ray equipment are described along with radiographic film, radiograph interpretation, and neutron radiography.

Assessment of risk of potential exposures on facilities industries

International Nuclear Information System (INIS)

Leocadio, Joao Carlos

2007-03-01

This work develops a model to evaluate potential exposures on open facilities of industrial radiography in Brazil. This model will decisively contribute to optimize operational, radiological protection and safety procedures, to prevent radiation accidents and to reduce human errors in industrial radiography. The probabilistic safety assessment (PSA) methodology was very useful to assess potential exposures. The open facilities of industrial radiography were identified as the scenario to be analyzed in what concerns the evaluation of potential exposures, due to their high accidents indices. The results of the assessment of potential exposures confirm that the industrial radiography in Brazil is a high-risk practice as classified by the IAEA. The risk of potential exposure was estimated to be 40,5 x 10 -2 per year in Brazil, having as main consequences injuries to the workers' hands and arms. In the world scene, the consequences are worst, leading to fatalities of people, thus emphasizing the high risk of industrial radiography. (author)

Application of nomograms to calculate radiography parameters

International Nuclear Information System (INIS)

Voronin, S.A.; Orlov, K.P.; Petukhov, V.I.; Khomchenkov, Yu.F.; Meshalkin, I.A.; Grachev, A.V.; Akopov, V.'S.; Majorov, A.N.

1979-01-01

The method of calculation of radiography parameters with the help of nomograms usable for practical application under laboratory and industrial conditions, is proposed. Nomograms are developed for determining the following parameters: relative sensitivity, general non-definition of image, permissible difference of blackening density between the centre and edge of the picture (ΔD), picture contrast, focus distance, item thickness, radiation-physical parameter, dose build up factor, groove dimension and error. An experimental test has been carried out for evaluating the results, obtained with nomograms. Steel items from 25 to 79 mm thick have been subjected to testing 191 Ir has been used as a source. Comparison of calculation and experimental results has shown the discrepancy in sensitivity values, caused by ΔDsub(min) apriori index and the error, inherent in graphical plotting on a nomogram

Radiography – How do students understand the concept of radiography?

International Nuclear Information System (INIS)

Lundgren, S.M.; Lundén, M.; Andersson, B.T.

2015-01-01

Background: Radiography as a concept has mainly been associated with the functional role of the radiographer. The concept has been studied from a theoretical point of view. However, there is a lack of a theoretical foundation and research on the actual substance of the term radiography used in education. It is therefore important to undertake an investigation in order to determine how students after three years education understand the subject of radiography. Aim: The aim of this study was to analyse how students in the Swedish radiographers' degree program understand the concept of radiography. Method: A concept analysis was made according to the hybrid model, which combines theoretical, fieldwork and analytical phases. A summative content analysis was used to identify the number and content of statements. The empirical data were collected from questionnaires answered by radiography students at four universities in Sweden. Findings: All radiography students' exemplified radiography with statements related to the practical level although some of them also identified radiography at an abstract level, as a subject within a discipline. The attribute ‘An interdisciplinary area of knowledge’ emerged, which is an attribute on the abstract level. The practical level was described by four attributes: Mastering Medical Imaging’, ‘To accomplish images for diagnosis and interventions’, ‘Creating a caring environment’ and ‘Enabling fruitful encounters’. Conclusion: The hybrid model used was a versatile model of concept development. The results of this study have increased the understanding of what characterizes the concept of radiography in a Swedish context. - Highlights: • This concept analysis of radiography was undertaken according to a hybrid model. • In radiography humanistic aspects are emphasized, a shift from the technological perspective. • The attributes demonstrate the essence and interdisciplinary nature of radiography. • This

Radiological protection in the industrial area

International Nuclear Information System (INIS)

Fraga, H.

2008-12-01

Radiation protection (RP) in industrial applications is composed of four major themes that are recruiting and training personnel, equipment and instrumentation, materials used and also the acquisition of new technologies to improve their own RP. To carry out the recruitment of staff and train them to serve as occupationally exposed personnel in the industry continues with the Mexican Official Standard NOM-031-NUCL-1999, R equirements for qualification and training of personnel occupationally exposed to radiation ionizing , what will be done regarding the physical fitness of personnel by NOM-026-NUCL-1999, M edical surveillance of personnel occupationally exposed to ionizing radiation . The principle of optimization of the RP, or ALARA principle (keeping the risk as low as reasonably achievable), is assumed to be the safety philosophy in the field of industrial applications of ionizing radiation. Practically all the elements that make up the equipment, instrumentation and materials used in industrial radiography and other industrial applications, has an orientation towards the protection, along with procedures that operate. For example, in industrial radiography the technician always has several instruments for radiation detection and measurement, some with visible and audible alarms. The equipment characteristics and transport (containers) are regulated by the standards NOM-025/1- 2000 and NOM-025/2-2996, which contains requirements for radiological safety in design and operation, respectively, for both as containers for some of its parts and accessories. As part of the technological innovation with benefits to the RP itself and eventually target practice today are venturing into the radiography digital, which involves the exposure of a plate image phosphorus-based with the later download to a computer. In combination with the use of sources of X-rays, there is a real contribution to reducing the dose, since the later are nowadays equipped with programmable

Assessment of cold neutron radiography capability

International Nuclear Information System (INIS)

McDonald, T.E. Jr.; Roberts, J.A.

1998-01-01

This is the final report of a one-year, Laboratory Directed Research and Development (LDRD) project at Los Alamos National Laboratory (LANL). The authors goals were to demonstrate and assess cold neutron radiography techniques at the Los Alamos Neutron Science Center (LANSCE), Manual Lujan Neutron Scattering Center (Lujan Center), and to investigate potential applications of the capability. The authors have obtained images using film and an amorphous silicon detector. In addition, a new technique they have developed allows neutron radiographs to be made using only a narrow range of neutron energies. Employing this approach and the Bragg cut-off phenomena in certain materials, they have demonstrated material discrimination in radiography. They also demonstrated the imaging of cracks in a sample of a fire-set case that was supplied by Sandia National Laboratory, and they investigated whether the capability could be used to determine the extent of coking in jet engine nozzles. The LANSCE neutron radiography capability appears to have applications in the DOE stockpile maintenance and science-based stockpile stewardship (SBSS) programs, and in industry

Optimization of a rod pinch diode radiography source at 2.3 MV

International Nuclear Information System (INIS)

Menge, P.R.; Johnson, D.L.; Maenchen, J.E.; Rovang, D.C.; Oliver, B.V.; Rose, D.V.; Welch, D.R.

2003-01-01

Rod pinch diodes have shown considerable capability as high-brightness flash x-ray sources for penetrating dynamic radiography. The rod pinch diode uses a small diameter (0.4-2 mm) anode rod extended through a cathode aperture. When properly configured, the electron beam born off of the aperture edge can self-insulate and pinch onto the tip of the rod creating an intense, small x-ray source. Sandia's SABRE accelerator (2.3 MV, 40 Ω, 70 ns) has been utilized to optimize the source experimentally by maximizing the figure of merit (dose/spot diameter2) and minimizing the diode impedance droop. Many diode parameters have been examined including rod diameter, rod length, rod material, cathode aperture diameter, cathode thickness, power flow gap, vacuum quality, and severity of rod-cathode misalignment. The configuration producing the greatest figure of merit uses a 0.5 mm diameter gold rod, a 6 mm rod extension beyond the cathode aperture (diameter=8 mm), and a 10 cm power flow gap to produce up to 3.5 rad (filtered dose) at 1 m from a 0.85 mm x-ray on-axis spot (1.02 mm at 3 deg. off axis). The resultant survey of parameter space has elucidated several physics issues that are discussed

Basic research of neutron radiography using cold neutron beam

International Nuclear Information System (INIS)

Oda, Masahiro; Tamaki, Masayoshi; Tasaka, Kanji

1995-01-01

As the result of demanding high quality images, now the nuclear reactors which can supply stably intense neutron beam have become the most general neutron source for radiography. For the purpose, mostly thermal neutrons have been used, but it is indispensable to use other neutrons than thermal neutrons for advancing neutron radiography technology and expanding the application fields. The radiography using cold neutrons is most behind in the development because the suitable neutron source was not available in Japan. The neutron sources for exclusively obtaining intense cold neutron beam were installed in the Kyoto University reactor in 1986 and in the JRR-3M of Japan Atomic Energy Research Institute in 1991. Basically as neutron energy lowers, the cross section of substances increases. In certain crystalline substances, the Bragg cutoff arises. The removal of scattered neutrons, the measurement of parallelism of beam and the relation of the thickness of objects with the transmissivity of cold neutrons are described. The imaging by TV method and the cold neutron CT in the CNRF and the simplified neutron CT by film method are reported. (K.I.)

Ion sources for industrial use

International Nuclear Information System (INIS)

Sakudo, Noriyuki

1994-01-01

Industrial applications of ion beams began in the 1970's with their application in fabrication of semiconductor devices. Since then, various improvements have been carried out for source lifetimes, current levels and diversification of ion species. Nowadays, ion beams are expected to be used for surface modification of materials as well as semiconductor fabrication. In this report, some of the typical ion sources are reviewed from the viewpoint of future industrial use. (author)

Recent advances in fast neutron radiography for cargo inspection

International Nuclear Information System (INIS)

Sowerby, B.D.; Tickner, J.R.

2007-01-01

Fast neutron radiography techniques are attractive for screening cargo for contraband such as narcotics and explosives. Neutrons have the required penetration, they interact with matter in a manner complementary to X-rays and they can be used to determine elemental composition. Compared to neutron interrogation techniques that measure secondary radiation (neutron or gamma-rays), neutron radiography systems are much more efficient and rapid and they are much more amenable to imaging. However, for neutron techniques to be successfully applied to cargo screening, they must demonstrate significant advantages over well-established X-ray techniques. This paper reviews recent developments and applications of fast neutron radiography for cargo inspection. These developments include a fast neutron and gamma-ray radiography system that utilizes a 14 MeV neutron generator as well as fast neutron resonance radiography systems that use variable energy quasi-monoenergetic neutrons and pulsed broad energy neutron beams. These systems will be discussed and compared with particular emphasis on user requirements, sources, detector systems, imaging ability and performance

Proceedings of 7th short conference on neutron radiography

International Nuclear Information System (INIS)

Hiraoka, Eiichi; Katsurayama, Kousuke; Tsujimoto, Tadashi

1986-10-01

The first short period conference on neutron radiography was held in 1970, and now the 7th meeting was held. The works to develop neutron radiography in Japan are as active as those in western countries, and the research is in progress by using neutrons from reactors, radioisotopes and accelerators in order to achieve the technology of high standard. In this conference, 26 papers and six comments were presented, and the themes covered the equipment for radiography, the practical application, and the related research. The second World Conference on Neutron Radiography will be held in Paris in June, 1986, and the further promotion of the spread of neutron radiography can be expected. The proceedings of the conference is published with the hope that joint effort and information exchange are further enhanced in coming years to develop the neutron radiography in Japan. The neutron radiography using the Kinki University reactor, the Rikkyo Triga-2 reactor, the Musashi reactor, the Kyoto research reactor, a 3MV Van de Graaff accelerator in Toyota, a subcompact cyclotron in Sumitomo, a baby cyclotron-dual collimator in National Space Development Agency and so on, Cf-252 based thermal neutron radiography, CT with Sb-124/Be neutrons, pulse power neutron source, imaging converters, neutron radiographic image processing, computed tomography using neutron television systems and others are reported. (Kako, I.)

Digital radiography

International Nuclear Information System (INIS)

Zani, M.L.

2002-01-01

X-ray radiography is a very common technique used to check the homogeneity of a material or the inside of a mechanical part. Generally the radiation that goes through the material to check, produced an image on a sensitized film. This method requires time because the film needs to be developed, digital radiography has no longer this inconvenient. In digital radiography the film is replaced by digital data and can be processed as any computer file. This new technique is promising but its main inconvenient is that today its resolution is not so good as that of film radiography. (A.C.)

Apparatus for proton radiography

International Nuclear Information System (INIS)

Martin, R.L.

1976-01-01

An apparatus for effecting diagnostic proton radiography of patients in hospitals comprises a source of negative hydrogen ions, a synchrotron for accelerating the negative hydrogen ions to a predetermined energy, a plurality of stations for stripping extraction of a radiography beam of protons, means for sweeping the extracted beam to cover a target, and means for measuring the residual range, residual energy, or percentage transmission of protons that pass through the target. The combination of information identifying the position of the beam with information about particles traversing the subject and the back absorber is performed with the aid of a computer to provide a proton radiograph of the subject. In an alternate embodiment of the invention, a back absorber comprises a plurality of scintillators which are coupled to detectors. 10 claims, 7 drawing figures

Industrial Radiography Manual.

Science.gov (United States)

Richardson, Harry D.

This text was developed for use by students in an 80-hour course for industrial radiographers. Chapter headings are: (1) The Structure of Matter, (2) Radiation and Radiation Machines, (3) Nuclear Reactions and Radioisotopes, (4) Interaction of Radiation with Matter, (5) Radiation Detection and Measurement, (6) The Nature and Consequences of…

Non destructive testing of industrial pieces by radiography: quantitative characterization and 3 D reconstruction by the way of a limited number of images

International Nuclear Information System (INIS)

Retraint, F.

1998-01-01

The non destructive testing of industrial pieces is evaluated on the basis of numerical radiographies.The context of the study is the online control of the fuel rods production. A direct model of a numerical radiography formation is proposed and detailed for an acquisition system consisting of a CCD video connected to a converter screen by an optical system. As this approach does not allow the determination of the measured matter thickness from the X-ray photograph, an approximate model based on realistic approximations of the industrial non destructive testing, has been developed. For the specific cases it is possible to inverse the model and to reach the quantitative information present in the x-ray photograph, in other words, the map of the X-rays measured matter thickness. It becomes then possible to access to the quantitative parameters of the possible defects present in the measured specimen, such as the surface and the bulk. To reach the 3 D information on the defects a 3 D reconstruction method, from 3 X-rays photographs, is proposed.The inverse problem is solved by the non convex energy minimization. (A.L.B.)

Evidence-based radiography

International Nuclear Information System (INIS)

Hafslund, Bjorg; Clare, Judith; Graverholt, Birgitte; Wammen Nortvedt, Monica

2008-01-01

Evidence-based practice (EBP) offers the integration of the best research evidence with clinical knowledge and expertise and patient values. EBP is a well known term in health care. This paper discusses the implementation of EBP into radiography and introduces the term evidence-based radiography. Evidence-based radiography is radiography informed and based on the combination of clinical expertise and the best available research-based evidence, patient preferences and resources available. In Norway, EBP in radiography is being debated and radiographers are discussing the challenges of implementing EBP in both academic and clinical practice. This discussion paper explains why EBP needs to be a basis for a radiography curriculum and a part of radiographers' practice. We argue that Norwegian radiographers must increase participation in research and developing practice within their specific radiographic domain

Electronic device for automatic control of exposure in radiography

International Nuclear Information System (INIS)

Pendharkar, A.S.; Jayakumar, T.K.

1977-01-01

An electronic instrument for calculating and controlling exposure in radiography practice using radioisotopes is described. When using this equipment, only factor to be known is the dose required by the film for a given density and the thickness of material inspected. It eliminates all the problems arising out of various parameters such as source decay etc in the conventional procedure for calculating exposure time. Principle of operation, the electronic circuitry adopted and the functional aspects of the system are described in detail. Exposure doses for different industrial films have been related to the instrumental readouts. The system reproducibility and reliability have been evaluated. The advantages and limitations of the present system and the future development to overcome the problems are indicated. (author)

Engineering applications of microfocal radiography. Chapter 2

International Nuclear Information System (INIS)

Sharpe, R.S.; Parish, R.W.

1980-01-01

The engineering applications of microfocal radiography are reviewed in detail. After describing the terminology used, the types of application are identified where the advantages of the reduced focal spot size are utilised e.g. finer detail, dynamic radiography of temporally changing events, lower background in the film and superior depth of focus. The quality of the images obtained with microfocal techniques is also discussed in detail. Finally various types of microfocal equipment which are commercially available are described and explicit examples of the areas of application are given, e.g. non-destructive testing in the nuclear industry, microporosity in aero-engine gas turbine blades and inspection of miniaturised electronic components such as integrated circuits. (U.K.)

Reconstructive dosimetry of radiological accidents - study of a brazilian case of industrial gamma radiography

International Nuclear Information System (INIS)

Silva, Francisco Cesar Augusto da; Hunt, John G.; Ramalho, Adriana; Pinto, Livia M.F. Amalfi

2002-01-01

On May 2000, an industrial gamma radiography operator, during a maintenance work of a 60 Co irradiator, has suffered a radiological accident with severe consequences to the left hand. The experts of the High Doses Analysis Group (GADE/IRD/CNEN) initiated the reconstructive dosimetry for the radiation dose estimation, in order to determine the real dose received by the operator, and to help the medical evaluation for prescribing the medical procedures for treatment of the involved victim. This paper presents the reconstructive dosimetry performed through the determination of the radiation doses of the operator, based on theoretical, experimental and computational methods. For the computer methods, a program for the calculation of external doses were used, based on the Monte Carlo method, and a human body simulator composed by voxels. The values of effective and equivalent doses are also presented which has caused severe lesions on the operator hand

Californium Multiplier. Part I. Design for neutron radiography

International Nuclear Information System (INIS)

Crosbie, K.L.; Preskitt, C.A.; John, J.; Hastings, J.D.

1982-01-01

The Californium Multiplier (CFX) is a subcritical assembly of enriched uranium surrounding a californium-252 neutron source. The function of the CFX is to multiply the neutrons emitted by the source to a number sufficient for neutron radiography. The CFX is designed to provide a collimated beam of thermal neutrons from which the gamma radiation is filtered, and the scattered neutrons are reduced to make it suitable for high resolution radiography. The entire system has inherent safety features, which provide for system and personnel safety, and it operates at moderate cost. In Part I, the CFX and the theory of its operation are described in detail. Part II covers the performance of the Mound Facility CFX

Review of neutron radiographic applications in industrial and biological systems

International Nuclear Information System (INIS)

Ashraf, M.M.; Khan, A.R.

1992-10-01

Neutron radiography is a non-destructive testing technique and is being used worldwide for the design and the development of reactor fuels for research and power reactors. It is also being used for non-destructive examination of nuclear industrial products. In addition to its explosives and other industrial sectors. In addition to its applications in industrial sectors, the technique is widely used for research and development activities in biological systems. A review of technical applications of neutron radiography in different fields particularly in nuclear fuel management, aerospace industry, explosives and biology is presented. The methodology of neutron radiography is also discussed in detail along with the advantages of the technique. In addition, the potential of the neutron radiography facility at PINSTECH has been described. (author)

Use of industrial isotopes in the construction of an integrated steel plant

International Nuclear Information System (INIS)

Narasimha Rao, Y.V.; Prasad, G.C.

1977-01-01

The applications of radioisotopes by industrial radiography methods in the control of quality of welding of steel structures and equipment during the construction of a steel plant are highlighted. Some of the main units that are controlled in a steel plant by the radiography methods are boilers, pressure vessels, blast furnace shells and stoves, L.D. convertors, technological pipelines etc. After briefly describing the different radioisotopes (sources) and the accessories required for radiography work, the different techniques adopted for determining the defects in the welded joints are mentioned. A mention is also made of the different types of image quality indicators (penetrameters) and their relative advantages. The norms for control and acceptance of the defects for different structures are also covered. Finally, the safety requirements that are to be followed during radiography work at the site of erection, where different agencies of construction work simultaneously are dealt with. (author)

A study on evaluation of public dose for hypothetical exposure from industrial sources in major Indian cities

International Nuclear Information System (INIS)

Chandrasekaran, S.; Sivasubramanian, K.; Venkatraman, B.

2016-01-01

With expanding industrial establishments in India, the requirements for quality Assurance (QA) have become stringent at every stages of process including selection of raw material, manufacturing process and packing and transport. Radiography, a non-destructive method is widely employed for QA testing. Inadvertent handling or loss of these sources may result in exposure of public/workers to higher levels of ionizing radiation. A well planned emergency preparedness is essential to manage any such untoward incidents. Dose estimation to members of public involved is the major challenge as the time available is very short and eases of availability/labs surrounding the location. This paper determines the dose up to 30m distance as prescribed in AERB safety guidelines and using the population data of four major metropolitan cities in India, public dose is also estimated

Development and application of test apparatus for classification of sealed source

International Nuclear Information System (INIS)

Kim, Dong Hak; Seo, Ki Seog; Bang, Kyoung Sik; Lee, Ju Chan; Son, Kwang Je

2007-01-01

Sealed sources have to conducted the tests be done according to the classification requirements for their typical usages in accordance with the relevant domestic notice standard and ISO 2919. After each test, the source shall be examined visually for loss of integrity and pass an appropriate leakage test. Tests to class a sealed source are temperature, external pressure, impact, vibration and puncture test. The environmental test conditions for tests with class numbers are arranged in increasing order of severity. In this study, the apparatus of tests, except the vibration test, were developed and applied to three kinds of sealed source. The conditions of the tests to class a sealed source were stated and the difference between the domestic notice standard and ISO 2919 were considered. And apparatus of the tests were made. Using developed apparatus we conducted the test for 192 Ir brachytherapy sealed source and two kinds of sealed source for industrial radiography. 192 Ir brachytherapy sealed source is classified by temperature class 5, external pressure class 3, impact class 2 and vibration and puncture class 1. Two kinds of sealed source for industrial radiography are classified by temperature class 4, external pressure class 2, impact and puncture class 5 and vibration class 1. After the tests, Liquid nitrogen bubble test and vacuum bubble test were done to evaluate the safety of the sealed sources

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

International Nuclear Information System (INIS)

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

2001-01-01

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

Experiments on muon radiography with emulsion track detectors

International Nuclear Information System (INIS)

Aleksandrov, Andrey; Bagulya, Alexander; Baklagin, Sergei; Chernyavsky, Mikhail; Galkin, Vladimir; Grachev, Victor; Konovalova, Nina; Managadze, Alexander; Polukhina, Natalya; Roganova, Tatiana; Starkov, Nikolai; Shchedrina, Tatiana; Tioukov, Valeri; Vladymirov, Mykhailo; Zemskova, Svetlana

2016-01-01

Muon radiography is a method of study the internal structure of large natural and industrial objects based on sensing an object with a flux of cosmic muons with their subsequent registration and analysis of the pattern of their dispersion, or conplete (or partial) absorption. The Lebedev Physical Institute of the Russian Academy of Sciences and the Skobeltsyn Institute of Nuclear Physics of Moscow State University have started a series of muon radiography experiments with nuclear emulsion detectors. As a result, the optimal conditions for experiment arrangement have been determined, algorithms of data processing have been worked out, and peculiarities of the method have been ultimately investigated

Neutron radiography devices and their own applications

International Nuclear Information System (INIS)

Farny, G.

1975-04-01

Three kinds of neutron radiography devices were developed by the Saclay Reactor Department: underwater facilities for active rig or loop examination; extracted beam without γ for industrial applications; a special unit for the examination of spent fuels several meters long from power plants. These devices are described and their applications and performances discussed [fr

Opportunities for TRIGA reactors in neutron radiography

International Nuclear Information System (INIS)

Barton, John P.

1978-01-01

In this country the two most recent installations of TRIGA reactors have both been for neutron radiography, one at HEDL and the other at ANL. Meanwhile, a major portion of the commercial neutron radiography is performed on a TRIGA fueled reactor at Aerotest. Each of these installations has different primary objectives and some comparative observations can be drawn. Another interesting comparison is between the TRIGA reactors for neutron radiography and other small reactors that are being installed for this purpose such as the MIRENE slow pulse reactors in France, a U-233 fueled reactor for neutron radiography in India and the L88 solution reactor in Denmark. At Monsanto Laboratory, in Ohio, a subcritical reactor based on MTR-type fuel has recently been purchased for neutron radiography. Such systems, when driven by a Van de Graaff neutron source, will be compared with the standard TRIGA reactor. Future demands on TRIGA or competitive systems for neutron radiography are likely to include the pulsing capability of the reactor, and also the extraction of cold neutron beams and resonance energy beams. Experiments recently performed on the Oregon State TRIGA Reactor provide information in each of these categories. A point of particular current concern is a comparison made between the resonance energy beam intensity extracted from the edge of the TRIGA core and from a slot which penetrated to the center of the TREAT reactor. These results indicate that by using such slots on a TRIGA, resonance energy intensities could be extracted that are much higher than previously predicted. (author)

A study of television imaging system for fast neutron radiography

International Nuclear Information System (INIS)

Yoshii, Koji

1992-01-01

The neutron radiography with fast neutron beam is a very useful imaging technique for thicker objects, especially those composed of hydrogen-rich materials which are sometimes difficult to image by thermal neutron radiography. The fast neutron radiography has not been studied so much as the thermal neutron radiography. The fast neutron radiography has been studied at the fast neutron source reactor 'Yayoi' of the University of Tokyo built in Tokai-mura. The average neutron energy of the Yayoi is about 1 MeV, and the peak neutron flux at the core center is 0.8 x 10 12 at the maximum operating power of 2 kW. In the experiment on fast neutron radiography, a CR39 nuclear track detector has been used successfully. But in the Yayoi radiography procedure, about 24 hours were required for obtaining an imaging result. To get a prompt imaging result and a real-time imaging result, it is necessary to develop a fast neutron television system, and in this paper, a new fast neutron TV system is proposed. The main difference is the converter material sensitive to fast neutrons. The study on the fast neutron TV system was carried out by using the Baby Cyclotron of Japan Steel Works, and the good images were realized. (K.I.)

Time-grated energy-selected cold neutron radiography

International Nuclear Information System (INIS)

McDonald, T.E. Jr.; Brun, T.O.; Claytor, T.N.; Farnum, E.H.; Greene, G.L.; Morris, C.

1998-01-01

A technique is under development at the Los Alamos Neutron Science Center (LANSCE), Manuel Lujan Jr. Neutron Scattering Center (Lujan Center) for producing neutron radiography using only a narrow energy range of cold neutrons. The technique, referred to as Time-Gated Energy-Selected (TGES) neutron radiography, employs the pulsed neutron source at the Lujan Center with time of flight to obtain a neutron pulse having an energy distribution that is a function of the arrival time at the imager. The radiograph is formed on a short persistence scintillator and a gated, intensified, cooled CCD camera is employed to record the images, which are produced at the specific neutron energy range determined by the camera gate. The technique has been used to achieve a degree of material discrimination in radiographic images. For some materials, such as beryllium and carbon, at energies above the Bragg cutoff the neutron scattering cross section is relatively high while at energies below the Bragg cutoff the scattering cross section drops significantly. This difference in scattering characteristics can be recorded in the TGES radiography and, because the Bragg cutoff occurs at different energy levels for various materials, the approach can be used to differentiate among these materials. This paper outlines the TGES radiography technique and shows an example of radiography using the approach

SOURCES OF FINANCING INDUSTRIAL COMPLEX ENTERPRISES

Directory of Open Access Journals (Sweden)

Anzhela Zakhitovna Namitulina

2016-01-01

Full Text Available Subject article is relevant because It is devoted to description of sources of financing of defense enterprises and peculiarities of selection of sources of financing enterprises of the military-industrial complex. In the first part of the article provides an overview of the financial resources and types of funding organizations and enterprises. Description of modern methods of creating a climate for innovation, supporting innovative ideas, and domestic entrepreneurship. The second part of the article describes the direction, the form of financing for companies, taking into account the peculiarities of the development and operation of defense enterprises. The first phase of the study was to identify the main sources of financing for companies in difficult socio-economic conditions of the potential customer of defense products. The second phase of the study was to determine the ranking factors the use of different sources of funding and its impact on the development of enterprises. The presented research topic is particularly relevant in connection with an increase in the role of sources of financing development of the industry for the growth of innovation activity of enterprises. The urgency of acquiring those aspects of economic relations that with the financing of new projects enterprises of the defense-industrial complex, the financing of the state defense order. In today's economic environment has the need to address financial security of the defense-industrial complex, to attract new sources of funding, development of bank lending in the defense sector and the participation of banks in the financing of projects of the enterprises of the military-industrial complex. The processes of market transformation of enterprises of the military-industrial complex (MIC have acquired a special significance in relation to defining the role of these enterprises in the country and providing security to the complexity of their adaptation to market

Digital luminescent radiography: A substitute for conventional chest radiography?

International Nuclear Information System (INIS)

Neufang, K.F.R.; Krug, B.; Lorenz, R.; Steinbrich, W.

1990-01-01

The image quality of digital luminescent radiography (DLR) is sufficient for routine biplane chest radiography and for follow-up studies of heart size, pulmonary congestion, coin lesions, infiltrations, atelectasis, pleural effusions, and mediastinal and hilar lymph node enlargement. Chest radiography in the intensive care unit may in most cases be performed using the DLR technique. there is no need for repeat shots because of incorrect exposure, and the position of catheters, tubes, pacemakers, drains and artificial heart valves, the mediastinum, and the retrocardiac areas of the left lung are more confidently assessed on the edge-enhanced DLR films than on conventional films. Nevertheless, DLR is somewhat inferior to conventional film-screen radiography of the chest as it can demonstrate or rule out subtle pulmonary interstitial disease less confidently. There is no reduction of radiation exposure of the chest in DLR compared with modern film-screen systems. As a consequence, DLR is presently not in a position to replace traditional film-screen radiography of the chest completely. (orig.) [de

An Industrial Radipgraphy Exposure Device Based on Measurement of Transmitted Gamma-Ray Intensity

International Nuclear Information System (INIS)

Polee, C.; Chankow, N.; Srisatit, S.; Thong-Aram, D.

2014-01-01

In film radiography, underexposure and overexposure may happen particularly when lacking knowledge of specimen material and hollowness. This paper describes a method and a device for determining exposure in industrial gamma-ray radiography based on quick measurement of transmitted gamma-ray intensity with a D3372 Hamamatsu small GM tube. Application software is developed for Android mobile phone to remotely control the device and to display the counting data via Bluetooth. Prior to placing film, the device is placed behind the specimen to be radiographed to determine the exposure time from the transmitted intensity which is independent on source activity, source-to-film distance, specimen thickness and kind of material. The developed technique and device make radiographic process economic, convenient and more reliable.

Charged Particle Radiography

International Nuclear Information System (INIS)

Morris, Chris

2004-01-01

The Coulomb multiple scattering of charged particles as they pass through material allows them to be used as a radiographic probe. This forms the basis for a new kind of radiography that is finding application where conventional x-ray radiography is limited by flux or backgrounds. Charged-particle radiography is providing a versatile new probe that has advantages over conventional x-ray radiography for some unique application. Proton radiography has been used to make quantitative motion pictures of high explosive driven experiments and proves to be of great value for radiographing experiments that mock up nuclear weapon primaries for stockpile certification. By taking advantage of magnetic lens to magnify images and by using the very bright beams that can be made with electrons, charged-particle radiography may be useful for studying the fine spatial detail and very fast motion in laser driven implosion experiments at the National Ignition Facility. Finally, radiographs can be made using cosmic-ray muons for searching vehicles and cargo containers for surreptitious cargo of high z materials such as uranium or plutonium.

Entraigues, a system dedicated to industrial radiography interpretation

International Nuclear Information System (INIS)

Fleuet, E.; Lavayssiere, B.

1995-01-01

Some inspections including radiography are periodically done among the components of a nuclear power plant in order to check their integrity. Today the operator is in charge of acquiring data, of analysing and of quantifying the produced X-ray films. EDF has built a digital system called ENTRAIGUES which aims to help the processing and the interpretation of radiographic images. The hardware of ENTRAIGUES is composed of a digitizer, a dedicated image processor and a PC. The software has been designed to facilitate the analysis of X-ray images. With the inclusion of compression algorithms and automatic image procedures ENTRAIGUES has become a complete tool dedicated to digitization, processing and archiving of nuclear power plant radiographs. (authors). 2 refs

Radiography shielding

Energy Technology Data Exchange (ETDEWEB)

Redmayne, I.

1985-11-27

Apparatus for the inspection of a pipe weld by radiography comprises a radiation source contained in a housing having a first collimator for defining the exit beam and a second collimator mountable on the pipe in the region of the weld to define with the first collimator a predetermined volume enclosing the radiation beam passing through the second collimator when the housing is in a predetermined position relative to the second collimator. The arrangement is such that if the housing is slightly displaced from the predetermined position the radiation beam still falls within the predetermined volume.

Radiography shielding

International Nuclear Information System (INIS)

Redmayne, I.

1985-01-01

Apparatus for the inspection of a pipe weld by radiography comprises a radiation source contained in a housing having a first collimator for defining the exit beam and a second collimator mountable on the pipe in the region of the weld to define with the first collimator a predetermined volume enclosing the radiation beam passing through the second collimator when the housing is in a predetermined position relative to the second collimator. The arrangement is such that if the housing is slightly displaced from the predetermined position the radiation beam still falls within the predetermined volume. (author)

Radiation exposure management over a decade in sealed sources fabrication

International Nuclear Information System (INIS)

Chougule, Nitin V.; Swaminathan, N.; Singh, P.; Sreenivas, V.; Bairwa, S.M.; Rath, D.P.; Patil, B.N.; Sastry, K.V.S.

2008-01-01

Radioactive sealed sources find innumerable applications in medical and industrial applications. 60 Co teletherapy sources are used for the treatment of cancer. In brachytherapy; 137 Cs and 192 Ir are used. Industrial sources using 60 Co, 137 Cs find applications in nucleonic gauges, tracer studies etc. 60 Co and 192 Ir sources are used in radiography also. In addition, 60 Co is widely used in irradiator facilities. Board of Isotopes and Radiation Technology (BRIT) has committed in supply of these sealed sources to various hospitals and industrial institutions in India. Annually, PetaBq (PBq) level of above mentioned isotopes are handled remotely in hot cells, RLG, BARC. This paper brings out a detailed account on the radiological surveillance provided during the fabrication of these sources implementing ALARA. The decrease in collective dose per activity handled is the outcome of improved operation practices which were carried out at various stages of source fabrication. (author)

Defective pixel map creation based on wavelet analysis in digital radiography detectors

International Nuclear Information System (INIS)

Park, Chun Joo; Lee, Hyoung Koo; Song, William Y.; Achterkirchen, Thorsten Graeve; Kim, Ho Kyung

2011-01-01

The application of digital radiography detectors has attracted increasing attention in both medicine and industry. Since the imaging detectors are fabricated by semiconductor manufacturing process over large areas, defective pixels in the detectors are unavoidable. Moreover, the radiation damage due to the routine use of the detectors progressively increases the density of defective pixels. In this study, we present a method of identifying defective pixels in digital radiography detectors based on wavelet analysis. Artifacts generated due to wavelet transformations have been prevented by an additional local threshold method. The proposed method was applied to a sample digital radiography and the result was promising. The proposed method uses a single pair of dark and white images and does not require them to be corrected in gain-and-offset properties. This method will be helpful for the reliable use of digital radiography detectors through the working lifetime.

Muon radiography for exploration of Mars geology

Directory of Open Access Journals (Sweden)

S. Kedar

2013-06-01

Full Text Available Muon radiography is a technique that uses naturally occurring showers of muons (penetrating particles generated by cosmic rays to image the interior of large-scale geological structures in much the same way as standard X-ray radiography is used to image the interior of smaller objects. Recent developments and application of the technique to terrestrial volcanoes have demonstrated that a low-power, passive muon detector can peer deep into geological structures up to several kilometers in size, and provide crisp density profile images of their interior at ten meter scale resolution. Preliminary estimates of muon production on Mars indicate that the near horizontal Martian muon flux, which could be used for muon radiography, is as strong or stronger than that on Earth, making the technique suitable for exploration of numerous high priority geological targets on Mars. The high spatial resolution of muon radiography also makes the technique particularly suited for the discovery and delineation of Martian caverns, the most likely planetary environment for biological activity. As a passive imaging technique, muon radiography uses the perpetually present background cosmic ray radiation as the energy source for probing the interior of structures from the surface of the planet. The passive nature of the measurements provides an opportunity for a low power and low data rate instrument for planetary exploration that could operate as a scientifically valuable primary or secondary instrument in a variety of settings, with minimal impact on the mission's other instruments and operation.

Startup data for the Stationary Neutron Radiography Reactor (SNRS)

International Nuclear Information System (INIS)

Heidel, C.C.; Richards, W.J.

1990-01-01

Moisture and corrosion in the F-lll aluminum honeycomb structure is a significant maintenance problem for these 1960 vintage aircraft. Corrosion and moisture are not readily detectable with conventional nondestructive testing techniques such as X-ray. However, by using neutron radiography, high quality images of the corrosion and moisture within the panels can be obtained. The SNRS-1 TRIGA was developed to provide the high intensity neutron source needed to support systems that enable neutron radiography to be performed on these aircraft parts

Protection from potential exposures: application to selected radiation sources

International Nuclear Information System (INIS)

1997-09-01

This ICRP Report begins with the general principles of radiation protection in the case of potential exposures, followed by special issues in application and compliance with regulatory aims. The rest of the report uses event trees or fault trees to derive the logical structure of six scenarios of potential exposure, i.e. two irradiators, a large research accelerator, an accelerator for industrial isotope production, an industrial radiography device using a mobile source of radiation, and finally a medical gamma radiotherapy device. (UK)

Bone X-Ray (Radiography)

Medline Plus

Full Text Available ... Resources Professions Site Index A-Z X-ray (Radiography) - Bone Bone x-ray uses a very small ... X-ray (Radiography)? What is Bone X-ray (Radiography)? An x-ray (radiograph) is a noninvasive medical ...

Bone X-Ray (Radiography)

Medline Plus

Full Text Available ... Professions Site Index A-Z X-ray (Radiography) - Bone Bone x-ray uses a very small dose ... limitations of Bone X-ray (Radiography)? What is Bone X-ray (Radiography)? An x-ray (radiograph) is ...

Bone X-Ray (Radiography)

Science.gov (United States)

... News Physician Resources Professions Site Index A-Z X-ray (Radiography) - Bone Bone x-ray uses a very small ... of Bone X-ray (Radiography)? What is Bone X-ray (Radiography)? An x-ray (radiograph) is a noninvasive ...

Regulatory considerations and quality assurance of depleted uranium based radiography cameras

International Nuclear Information System (INIS)

Sapkal, Jyotsna A.; Yadav, R.K.B.; Amrota, C.T.; Singh, Pratap; GopaIakrishanan, R.H.; Patil, B.N.; Mane, Nilesh

2016-01-01

Radiography cameras with shielding material as Depleted Uranium (DU) are used for containment of Iridium ( 192 Ir) source. DU shielding surrounds the titanium made 'S' tube through which the encapsulated 192 Ir source along with the pigtail travels. As per guidelines, it is required to check periodically the shielding integrity of DU shielding periodically by monitoring for alpha transferable contamination inside the 'S' tube. This paper describes in brief the method followed for collection of samples from inside the 'S' tube . The samples were analysed for transferable contamination due to gross alpha using alpha scintillation (ALSCIN) counter. The gross alpha contamination in the 'S' tube was found to be less than the recommended USNRC value for discarding the radiography camera. IAEA recommendations related to transferable contamination and AERB guidelines on the quality assurance (QA) requirements of radiography camera were studied

Digital radiography

International Nuclear Information System (INIS)

Kusano, Shoichi

1993-01-01

Firstly, from an historic point of view, fundamental concepts on digital imaging were reviewed to provide a foundation for discussion of digital radiography. Secondly, this review summarized the results of ongoing research in computed radiography that replaces the conventional film-screen system with a photo-stimulable phosphor plate; and thirdly, image quality, radiation protection, and image processing techniques were discussed with emphasis on picture archiving and communication system environment as our final goal. Finally, future expansion of digital radiography was described based on the present utilization of computed tomography at the National Defense Medical College Hospital. (author) 60 refs

Radiography - A conceptual approach

Energy Technology Data Exchange (ETDEWEB)

Ahonen, Sanna-Mari [Department of Nursing Science and Health Administration, University of Oulu, P.O. Box 5000, FIN-90014 (Finland)], E-mail: sanna-mari.ahonen@oulu.fi

2008-11-15

Aim: The purpose of this article is to describe interdisciplinary comparison of the attributes of the concept of radiography in health sciences, physics and technology on the grounds of concept analysis. Background: The concept of radiography is widely used in health sciences, physics and technology. However, the content of the concept may vary. In order to clarify the concept of radiography, the concept must be systematically examined and defined in linguistic form. Method: The concept of radiography was analysed by using the evolutionary method of concept analysis. The data were collected through discretionary sampling and consisted of literature and Internet pages. Qualitative content analysis was employed for analysing the data. Findings: As a result of concept analysis, the concept of radiography in health sciences was determined as expertise of radiographers in the use of radiation, which is dual, dynamic, social and situation-related in nature, and typically based on versatile synthesis. Regarding the attributes identified, the concept of radiography has both similarities and differences between health sciences, physics and technology. Conclusions: The concept of radiography was found to be more abstract, wider, more complex and more radiographer-centred in health sciences than in other disciplines. The content of the concept of radiography seems to vary according to the discipline.

Radiography - A conceptual approach

International Nuclear Information System (INIS)

Ahonen, Sanna-Mari

2008-01-01

Aim: The purpose of this article is to describe interdisciplinary comparison of the attributes of the concept of radiography in health sciences, physics and technology on the grounds of concept analysis. Background: The concept of radiography is widely used in health sciences, physics and technology. However, the content of the concept may vary. In order to clarify the concept of radiography, the concept must be systematically examined and defined in linguistic form. Method: The concept of radiography was analysed by using the evolutionary method of concept analysis. The data were collected through discretionary sampling and consisted of literature and Internet pages. Qualitative content analysis was employed for analysing the data. Findings: As a result of concept analysis, the concept of radiography in health sciences was determined as expertise of radiographers in the use of radiation, which is dual, dynamic, social and situation-related in nature, and typically based on versatile synthesis. Regarding the attributes identified, the concept of radiography has both similarities and differences between health sciences, physics and technology. Conclusions: The concept of radiography was found to be more abstract, wider, more complex and more radiographer-centred in health sciences than in other disciplines. The content of the concept of radiography seems to vary according to the discipline

Dose in conventional radiography

International Nuclear Information System (INIS)

Acuna D, E.; Padilla R, Z. P.; Escareno J, E.; Vega C, H. R.

2011-10-01

It has been pointed out that medical exposures are the most significant sources of exposure to ionizing radiation for the general population. Inside the medical exposures the most important is the X-ray use for diagnosis, which is by far the largest contribution to the average dose received by the population. From all studies performed in radiology the chest radiography is the most abundant. In an X-ray machine, voltage and current are combined to obtain a good image and a reduce dose, however due to the workload in a radiology service individual dose is not monitored. In order to evaluate the dose due to chest radiography in this work a plate phantom was built according to the ISO recommendations using methylmethacrylate walls and water. The phantom was used in the Imaging department of the Zacatecas General Hospital as a radiology patient asking for a chest study; using thermoluminescent dosimeters, TLD 100 the kerma at the surface entrance was determined. (Author)

Neutron radiography and other NDE tests of main rotor helicopter blades

International Nuclear Information System (INIS)

Beer, F.C. de; Coetzer, M.; Fendeis, D.; Silva, A. da Costa E

2004-01-01

A few nondestructive examination (NDE) techniques are extensively being used worldwide to investigate aircraft structures for all types of defects. The detection of corrosion and delaminations, which are believed to be the major initiators of defects leading to aircraft structural failures, are addressed by various NDE techniques. In a combined investigation by means of visual inspection, X-ray radiography and shearography on helicopter main rotor blades, neutron radiography (NRad) at SAFARI-1 research reactor operated by Necsa, was performed to introduce this form of NDE testing to the South African aviation industry to be evaluated for applicability. The results of the shearography, visual inspection and NRad techniques are compared in this paper. The main features and advantages of neutron radiography, within the framework of these investigations, will be highlighted

Bone X-Ray (Radiography)

Medline Plus

Full Text Available ... News Physician Resources Professions Site Index A-Z X-ray (Radiography) - Bone Bone x-ray uses a very ... of Bone X-ray (Radiography)? What is Bone X-ray (Radiography)? An x-ray (radiograph) is a noninvasive ...

Bone X-Ray (Radiography)

Medline Plus

Full Text Available ... News Physician Resources Professions Site Index A-Z X-ray (Radiography) - Bone Bone x-ray uses a very small ... of Bone X-ray (Radiography)? What is Bone X-ray (Radiography)? An x-ray (radiograph) is a noninvasive ...

Neutron radiography applications in I.T.U. TRIGA Mark-II reactor

International Nuclear Information System (INIS)

Tugrul, A. B.

2002-01-01

Neutron radiography is an important radiographic technique which is supplied different and advanced information according to the X or gamma ray radiography. However, it has a trouble for supplying the convenient neutron sources. Tangential beam tube of Istanbul Technical University (ITU) TRIGA Mark-II Training and Research Reactor has been arranged for using neutron radiography. The neutron radiography set defined as detailed for the application of the technique. Two different techniques for neutron radiography are defined as namely, transfer method and direct method. For the transfer method dysprosium and indium screens are used in the study. But, dysprosium generally was preferred in many studies in the point of view nuclear safety. Gadolinium was used for direct method. Two techniques are compared and explained the preferring of the transfer technique. Firstly, reference composition is prepared for seeing the differences between neutron and X-ray or gamma radiography. In addition of it, some radiograph samples are given neutron and X-ray radiography which shows the different image characters. Lastly, some examples are given from archaeometric studies. One of them the brass plates of Great Mosque door in Cizre. After the neutron radiography application, organic dye traces are noticed. Other study is on a sword that belong to Urartu period at the first millennium B.C. It is seen that some wooden part on it. Some different artefacts are examined with neutron radiography from the Ikiztepe excavation site, then some animal post parts are recognized on them. One of them is sword and sheath which are corroded together. After the neutron radiography application, it can be noticed that there are a cloth between the sword and its sheath. By using neutron radiography, many interesting and detailed results are observed in ITU TRIGA Mark-II Training and Research Reactor. Some of them shouldn't be recognised by using any other technique

Digital radiography in NDT applications

International Nuclear Information System (INIS)

Deprins, E.

2004-01-01

A lot of film radiography could be replaced by today's technologies in the field of digital radiography. Only few of these applications have indeed replaced film. The choice to go digital depends on cost, quality requirement, workflow and throughput. Digital images offer a lot of advantages in terms of image manipulation and workflow. But despite the many advantages, a lot of considerations are needed before someone can decide to convert his organization from conventional to digital radiography. This paper gives an overview of all different modalities that can be used in digital radiography with today's technologies, together with the experiences of the pioneers of digital radiography. Film Scanning, Computed Radiography and Digital Radiography by using of different kinds of flat panel detectors all have their specific application fields and customers. What is the status of the technology today, which advantages brings digital radiography, and which are the limitations radiographers have to consider when replacing film by digital systems. (author)

International Neutron Radiography Newsletter

DEFF Research Database (Denmark)

Domanus, Joseph Czeslaw

1986-01-01

At the First World Conference on Neutron Radiography i t was decided to continue the "Neutron Radiography Newsletter", published previously by J.P. Barton, as the "International Neutron Radiography Newsletter" (INRNL), with J.C. Doraanus as editor. The British Journal of Non-Destructive Testing...

Using a tungsten rollbar to characterize the source spot of a megavoltage bremsstrahlung linac

International Nuclear Information System (INIS)

Schach von Wittenau, A.E.; Logan, C.M.; Rikard, R.

2002-01-01

In photon teletherapy, the size and functional form of the photon source spot affect both the sharpness of the penumbra of treatment fields and the sharpness of portal images. Photon source spot parameters are also used in photon teletherapy dose calculation codes. A simple method for characterizing the source spot would complement the existing, more involved methods that have been described in the medical physics literature. Such a method, using a rollbar made of tungsten or other high-Z metal, is used in industrial radiography. We describe the use of a tungsten rollbar for characterizing the source spot edge spread function (and thereby the source spot size and shape) of a megavoltage bremsstrahlung photon source. We use Monte Carlo simulations to quantify anticipated experimental artifacts of the method, assuming typical spot sizes for circ-function, Gaussian, and Bennett line shapes. We illustrate the use of the rollbar method by characterizing the source spot of a typical 9 MV linac used for industrial radiography. The source spot is analyzed using two approaches: (a) fitting the rollbar image with analytic functions and (b) using Abel inversion to obtain the cylindrically symmetric spot profile consistent with the measured rollbar image. Monte Carlo simulations, based on a 6 MV photon teletherapy accelerator, suggest that aspects of the method are applicable to medical bremsstrahlung sources

Qualitative discussion of quantitative radiography

International Nuclear Information System (INIS)

Berger, H.; Motz, J.W.

1975-01-01

Since radiography yields an image that can be easily related to the tested object, it is superior to many nondestructive testing techniques in revealing the size, shape, and location of certain types of discontinuities. The discussion is limited to a description of the radiographic process, examination of some of the quantitative aspects of radiography, and an outline of some of the new ideas emerging in radiography. The advantages of monoenergetic x-ray radiography and neutron radiography are noted

A study of quantitative radiography for moisture content distributions in plant

International Nuclear Information System (INIS)

Kawabata, Y.; Hino, M.; Horie, T.

2003-01-01

Vacuum pre-cooling in cut flower or perishable vegetables industry are used for protecting from the deterioration of the perishables during transportation. Some improvements of the pre-cooling way, however, are required for a bruise in plant on the way of handling. Neutron radiography is suitable to detect and observe the bruise in plant, especially, moisture content distributions in leaves, flowers and stalks. Neutron spectrum in irradiation neutron beams is required for obtaining quantitative moisture contents in plant. The neutron spectrum measurements for determination of effective cross-section of water are carried out at CN-3 experimental hole of Kyoto University Reactor (KUR) by time of flight method. Moisture content distributions in leaves of chrysanthemum, before and after the vacuum pre-cooling are measured by cold neutron radiography at the experimental hole. The local decreases of moisture contents caused by a bruise on the surface of the leaves are measured quantitatively by the cold neutron radiography. The quantitative changes of the moisture content in the leaves are able to read out from the cold neutron radiography image. (M. Suetake)

Dosimetry of industrial sources

International Nuclear Information System (INIS)

Vega C, H.R.; Rodriguez J, R.; Manzanares A, E.; Hernandez V, R.; Ramirez G, J.; Rivera M, T.

2007-01-01

The gamma rays are produced during the disintegration of the atomic nuclei, its high energy allows them to cross thick materials. The capacity to attenuate a photons beam allows to determine the density, in line, of industrial interest materials as the mining. By means of two active dosemeters and a TLDs group (passive dosimetry) the dose rates of two sources of Cs-137 used for determining in line the density of mining materials were determined. With the dosemeters the dose levels in diverse points inside the grave that it harbors the sources and by means of calculations the isodoses curves were determined. In the phase of calculations was supposed that both sources were punctual and the isodose curves were calculated for two situations: naked sources and in their Pb packings. The dosimetry was carried out around two sources of 137 Cs. The measured values allowed to develop a calculation procedure to obtain the isodoses curves in the grave where the sources are installed. (Author)

Laser-driven x-ray and neutron source development for industrial applications of plasma accelerators

Science.gov (United States)

Brenner, C. M.; Mirfayzi, S. R.; Rusby, D. R.; Armstrong, C.; Alejo, A.; Wilson, L. A.; Clarke, R.; Ahmed, H.; Butler, N. M. H.; Haddock, D.; Higginson, A.; McClymont, A.; Murphy, C.; Notley, M.; Oliver, P.; Allott, R.; Hernandez-Gomez, C.; Kar, S.; McKenna, P.; Neely, D.

2016-01-01

Pulsed beams of energetic x-rays and neutrons from intense laser interactions with solid foils are promising for applications where bright, small emission area sources, capable of multi-modal delivery are ideal. Possible end users of laser-driven multi-modal sources are those requiring advanced non-destructive inspection techniques in industry sectors of high value commerce such as aerospace, nuclear and advanced manufacturing. We report on experimental work that demonstrates multi-modal operation of high power laser-solid interactions for neutron and x-ray beam generation. Measurements and Monte Carlo radiation transport simulations show that neutron yield is increased by a factor ~2 when a 1 mm copper foil is placed behind a 2 mm lithium foil, compared to using a 2 cm block of lithium only. We explore x-ray generation with a 10 picosecond drive pulse in order to tailor the spectral content for radiography with medium density alloy metals. The impact of using  >1 ps pulse duration on laser-accelerated electron beam generation and transport is discussed alongside the optimisation of subsequent bremsstrahlung emission in thin, high atomic number target foils. X-ray spectra are deconvolved from spectrometer measurements and simulation data generated using the GEANT4 Monte Carlo code. We also demonstrate the unique capability of laser-driven x-rays in being able to deliver single pulse high spatial resolution projection imaging of thick metallic objects. Active detector radiographic imaging of industrially relevant sample objects with a 10 ps drive pulse is presented for the first time, demonstrating that features of 200 μm size are resolved when projected at high magnification.

Laser-driven x-ray and neutron source development for industrial applications of plasma accelerators

International Nuclear Information System (INIS)

Brenner, C M; Rusby, D R; Armstrong, C; Wilson, L A; Clarke, R; Haddock, D; McClymont, A; Notley, M; Oliver, P; Allott, R; Hernandez-Gomez, C; Neely, D; Mirfayzi, S R; Alejo, A; Ahmed, H; Kar, S; Butler, N M H; Higginson, A; McKenna, P; Murphy, C

2016-01-01

Pulsed beams of energetic x-rays and neutrons from intense laser interactions with solid foils are promising for applications where bright, small emission area sources, capable of multi-modal delivery are ideal. Possible end users of laser-driven multi-modal sources are those requiring advanced non-destructive inspection techniques in industry sectors of high value commerce such as aerospace, nuclear and advanced manufacturing. We report on experimental work that demonstrates multi-modal operation of high power laser-solid interactions for neutron and x-ray beam generation. Measurements and Monte Carlo radiation transport simulations show that neutron yield is increased by a factor ∼2 when a 1 mm copper foil is placed behind a 2 mm lithium foil, compared to using a 2 cm block of lithium only. We explore x-ray generation with a 10 picosecond drive pulse in order to tailor the spectral content for radiography with medium density alloy metals. The impact of using  >1 ps pulse duration on laser-accelerated electron beam generation and transport is discussed alongside the optimisation of subsequent bremsstrahlung emission in thin, high atomic number target foils. X-ray spectra are deconvolved from spectrometer measurements and simulation data generated using the GEANT4 Monte Carlo code. We also demonstrate the unique capability of laser-driven x-rays in being able to deliver single pulse high spatial resolution projection imaging of thick metallic objects. Active detector radiographic imaging of industrially relevant sample objects with a 10 ps drive pulse is presented for the first time, demonstrating that features of 200 μm size are resolved when projected at high magnification. (paper)

Radiography student perceptions of clinical stressors.

Science.gov (United States)

Mason, Starla L

2006-01-01

Technological change and the increasingly rapid pace of life in the United States and globally have contributed to increased levels of stress and burnout experienced by workers and their families. Although studies are available on the levels of workplace stress and burnout affecting radiographers, little to no research has been conducted to assess the stressors encountered by radiography students in the clinical environment. This study was designed to pinpoint the primary sources of stress for radiography students and to determine the most effective measures to alleviate the stress that students experience in the clinical environment. It also sought to identify the clinical activities and practices that enhance learning. A convenience sample of radiography students attending an Association of Collegiate Educators in Radiologic Technology meeting was surveyed. Students were asked to rank their greatest stressors in the clinical environment, the most desired qualities in a clinical instructor and clinical environment, and the clinical practices and activities that best enhance their learning. Descriptive statistics were used to report the results. Data were collected for 82 first-year and second-year students. Students identified 7 primary clinical stressors: fear of making a mistake/repeat, feeling unprepared/inexperienced, intimidation by staff and by instructors, difficult/critical patients, hurtful criticism, too much supervision and negative responses to questions/requests for help. Students indicated that more frequent feedback, availability of the clinical instructor and other staff, assurance that mistakes happen and the opportunity to make mistakes were clinical practices that eased stress. The majority of students cited hands-on learning and repetition as the clinical activities that most reinforced their learning. Summary Radiography students in this survey experience some of the same clinical stressors as radiographers and other allied health workers

Radiography geometry principle

International Nuclear Information System (INIS)

Abdul Nassir Ibrahim; Azali Muhammad; Ab. Razak Hamzah; Abd. Aziz Mohamed; Mohamad Pauzi Ismail

2008-01-01

If one object placed in the field under the sun, we can see the shadow of that object in two dimensional where that object was placed. Nevertheless, the sun cannot penetrate deeply so that it will produce the shadow with same object. This principal also same as radiography, however, with ionizing radiation, it can penetrate through the object so that the image that produced not only the shadow of the object but also what are inside the object. So this can give advantages for the radiographer to make inspection what are inside this object. The images that produce depend with the shape, density, thickness and distance between the object, film and source. The reader also will introduce with some term such as Distance source to film, distance source to object, and distance object to film also some basic on DIN standard and API 1104 Standard.

Wind Turbine Blade Nondestructive Testing with a Transportable Radiography System

Directory of Open Access Journals (Sweden)

J. G. Fantidis

2011-01-01

Full Text Available Wind turbines are becoming widely used as they are an environmentally friendly way for energy production without emissions; however, they are exposed to a corrosive environment. In addition, as wind turbines typically are the tallest structures in the surrounding area of a wind farm, it is expected that they will attract direct lightning strikes several times during their operating life. The purpose of this paper is to show that the radiography with a transportable unit is a solution to find defects in the wind turbine blade and reduce the cost of inspection. A transportable neutron radiography system, incorporating an Sb–Be source, has been simulated using the MCNPX code. The simulated system has a wide range of radiography parameters.

An overview of digital radiography

International Nuclear Information System (INIS)

Aweligiba, S. A.

2013-04-01

The medical application of radiography has gained wider study since diagnostic radiology plays a very important role in modern medicine for fast diagnosis and therapy. Digital radiography is a relatively new technology that promises greater accuracy, lesser dose and better manipulation of patient radiology images in hospitals. In this study, a general discussion on digital radiography has been presented. The presentation focuses on the optimisation of doses to patients in the medical application of digital radiography, quality control and quality assurance. A brief presentation on performance indicators in digital radiography has also been presented. The advantages of digital radiography over the conventional film/screen system have been elaborated and its limitations are also outlined. (author)

Industrial Radiography Instructor's Guide.

Science.gov (United States)

Richardson, Harry D.

The curriculum guide was developed for teacher use in an 80-hour course for industrial radiographers. The units include: (1) The Structure of Matter and Radiation, (2) Nuclear Reactions and Radioisotopes, (3) The Nature and Consequences of Radiation Exposure, (4) Radiation Attenuation, (5) Absorption of Radiation, (6) Radiation Detection and…

Proton nuclear scattering radiography

International Nuclear Information System (INIS)

Duchazeaubeneix, J.C.; Faivre, J.C.; Garreta, D.

1982-10-01

Nuclear scattering of protons allows to radiograph objects with specific properties: direct 3- dimensional radiography, different information as compared to X-ray technique, hydrogen radiography. Furthermore, it is a well adapted method to gating techniques allowing the radiography of fast periodic moving systems. Results obtained on different objects (light and heavy materials) are shown and discussed. The dose delivery is compatible with clinical use, but at the moment, the irradiation time is too long between 1 and 4 hours. Perspectives to make the radiography faster and to get a practical method are discussed

The neutron radiography facility at Tehran Research Reactor (TRR)

International Nuclear Information System (INIS)

Ali Pazirandeh

2009-01-01

Full text: Non-destructive testing in many fields of industry including detection of explosives, at the airports, testing for micro-cracks on airplane wings and turbine blades cracks is badly needed. Thermal neutron beam is one of preferable method to detect the micro-cracks, reveals the internal structure of components and explosives. The purpose of this paper is to present the neutron radiography facility at Tehran Research Reactor (TRR), Science and Technology Research Institute, and in particular to emphasize the industrial applications in wood industry, automobile engine inspection, minerals composition identification, turbine blade cracks detection. (author)

X-ray digital industrial radiography (DIR) for local liquid velocity (VLL) measurement in trickle bed reactors (TBRs): Validation of the technique

Science.gov (United States)

Mohd Salleh, Khairul Anuar; Rahman, Mohd Fitri Abdul; Lee, Hyoung Koo; Al Dahhan, Muthanna H.

2014-06-01

Local liquid velocity measurements in Trickle Bed Reactors (TBRs) are one of the essential components in its hydrodynamic studies. These measurements are used to effectively determine a reactor's operating condition. This study was conducted to validate a newly developed technique that combines Digital Industrial Radiography (DIR) with Particle Tracking Velocimetry (PTV) to measure the Local Liquid Velocity (VLL) inside TBRs. Three millimeter-sized Expanded Polystyrene (EPS) beads were used as packing material. Three validation procedures were designed to test the newly developed technique. All procedures and statistical approaches provided strong evidence that the technique can be used to measure the VLL within TBRs.

Efficacy of daily bedside chest radiography as visualized by digital luminescence radiography

International Nuclear Information System (INIS)

Kirchner, J.; Stueckle, C.A.; Schilling, E.M.; Peters, J.

2001-01-01

To determine the diagnostic impact of daily bedside chest radiography in comparison with digital luminescence technique (DLR; storage phosphor radiography) and conventional film screen radiography, a prospective randomized study was completed in 210 mechanically ventilated patients with a total of 420 analysed radiographs. The patients were allocated to two groups: 150 patients underwent DLR, and 60 patients underwent conventional film screen radiography. Radiological analysis was performed consensually and therapeutic efficacy was assessed by the clinicians. There was no statistical significant difference between the frequency of abnormal findings seen on DLR and conventional film screen radiography. In total, 448 abnormal findings were present in 249 of 300 DLR and 97 of 120 conventional film screen radiographs. The most common findings were signs of overhydration (41 %), pleural effusion (31%), partial collapse of the lung (11%) and pneumothorax (2%). One hundred and twenty-three of 448 (27%) of these abnormal findings were thought to have a considerable impact on patient management. The high rate of abnormal findings with significant impact on patient management suggests that the use of daily bedside chest radiography may be reasonable. Copyright (2001) Blackwell Science Pty Ltd

Wall Thickness Measurement Of Insulated Pipe By Tangential Radiography Technique Using Ir 192

International Nuclear Information System (INIS)

Soedarjo

2000-01-01

Insulation pipe wall thickness by tangential radiography technique has been carried out using 41 Curie Iridium 192 source has activity for two carbon steel pipes. The outer diameter of the first pipe is 90 mm, wall thickness is 75.0 mm, source film film distance is 609.5 mm, source tangential point of insulation is 489.5 mm and exposure time 3 minute and 25 second. From the calculation, the first pipe thickness is found to be 12.54 mm and for the second pipe is 8.42 mm. The thickness is due to inaccuracy in reading the pipe thickness on radiography film and the geometry distortion radiation path

Comparison of the quality of the chest film between digital radiography and conventional high kV radiography

International Nuclear Information System (INIS)

Zeng Qingsi; Cen Renli; Chen Ling; He Jianxun; Lin Hanfei

2003-01-01

Objective: To evaluate the quality and usefulness of direct digital radiography system in roentgenogram of chest in clinical practice. Methods: 1000 cases of chest roentgenograms with digital radiography and high kV conventional radiography were selected for analysis by 3 senior radiologists. Results: 1. With digital radiography system, the quality of chest film was assessed as grade A in 50.6%, grade B in 38.5%, grade C in 10.9%, and no waste film. 2. With conventional high kV radiography, the quality of chest film was assessed as grade A in 41.1%, grade B in 44.1%, grade C in 13.3%, and waste film in 1.5%. The direct digital radiography was statistically superior to the conventional high kV radiography. 3. The fine structure of the lungs could be revealed in 100.0% of chest roentgenogram with direct digital radiograph system, which was significantly higher than that acquired with the conventional high KV radiography (78.6%, P < 0.001). Conclusion: Direct digital radiography could provide the chest film with better quality than that with the conventional high kV radiography. The direct digital radiography system is easy to operate, fast in capturing imaging and could provide post-processing techniques, which will facilitate the accurate diagnosis of chest radiography

Characteristics of sets of diffusion photographic materials for rapid X-ray radiography

International Nuclear Information System (INIS)

Gusev, E.A.; Neduv, A.M.; Korolev, A.I.; Mirzoyan, I.N.; Chelnokov, V.B.

1989-01-01

Peculiarities of application in X-ray radiography of roentgenographic films, roentgenographic paper, xeroroentgenographic plates and sets of diffusion photographic materials are considered. It is shown that the use of diffusion photographic materials for X-ray radiography permits to reduce the process labour consumption and to considerably reduce the time for the obtaining of a dry positive image and also to reduce the consumption of silver, but the image will preserve high information content. Selts of diffusion photographic materials are developed, which contain bromoiodosilver negative material with silver spraying of 2-3 g/m 3 and transparent positive material on Dacron basis. Prospects of application of sets of diffusion photographic materials in the practice of rapid X-ray radiography to solve the problems of industrial X-ray defectoscopy are panted out

Radiation safety for site radiography

International Nuclear Information System (INIS)

1986-01-01

This guidance is an update of the 1975 Code of Practice for Site Radiography and is for the use of employers and their radiographers who carry out site work. The subject is discussed under the following headings: Administrative organization, Personnel requirements, Equipment (x-ray and gamma-ray equipment, security, pipeline crawler equipment and safety equipment) Work methods and monitoring, Carriage of sources, Contingency plans, Legal considerations. (U.K.)

Quality control of aluminium casting: X ray radiography or tomography?

International Nuclear Information System (INIS)

Munier, B.; Tamziti, J.; Grignard, A.; Peix, G.; Kaftandjian, V.

2007-01-01

Full text of publication follows: X ray radiography has been for years a well known method commonly used for controlling parts either on line or off line. The purpose is to detect internal defects or to achieve reverse engineering on the parts. More recently two-dimensional or three-dimensional Computed Tomography has been introduced and provides key advantages over standard X ray radiography, such as dimensional measurement of complex objects with hidden structures and 3D defect localisation. However, from the user point of view, despite the clear advantages of tomography, the time consuming drawback is predominant, and thus, it is worth assessing the added value of tomography with respect to several radioscopic images. It is clear that there is no unique response to that question. If unacceptable defects are already detected in one radioscopic image, then the sample can be rejected and 3D tomography is useless. On another hand, 3D tomography cannot be replaced if internal structures such as holes must be measured with accuracy. The paper will present a comparison between radiography and tomography for controlling parts in the aluminium casting industry. Advantages and drawbacks of both methods will be reviewed. Performance features in both cases will be assessed in this specific industrial case by estimating the defect detection efficiency and image quality parameters. (authors)

Non destructive testing of industrial pieces by radiography: quantitative characterization and 3 D reconstruction by the way of a limited number of images; Controle non destructif de pieces industrielles par radiographie: caracterisation quantitative et reconstruction 3D a partir d`un nombre limite de vues

Energy Technology Data Exchange (ETDEWEB)

Retraint, F

1999-12-31

The non destructive testing of industrial pieces is evaluated on the basis of numerical radiographies.The context of the study is the online control of the fuel rods production. A direct model of a numerical radiography formation is proposed and detailed for an acquisition system consisting of a CCD video connected to a converter screen by an optical system. As this approach does not allow the determination of the measured matter thickness from the X-ray photograph, an approximate model based on realistic approximations of the industrial non destructive testing, has been developed. For the specific cases it is possible to inverse the model and to reach the quantitative information present in the x-ray photograph, in other words, the map of the X-rays measured matter thickness. It becomes then possible to access to the quantitative parameters of the possible defects present in the measured specimen, such as the surface and the bulk. To reach the 3 D information on the defects a 3 D reconstruction method, from 3 X-rays photographs, is proposed.The inverse problem is solved by the non convex energy minimization. (A.L.B.) 109 refs.

Non destructive testing of industrial pieces by radiography: quantitative characterization and 3 D reconstruction by the way of a limited number of images; Controle non destructif de pieces industrielles par radiographie: caracterisation quantitative et reconstruction 3D a partir d`un nombre limite de vues

Energy Technology Data Exchange (ETDEWEB)

Retraint, F

1998-12-31

The non destructive testing of industrial pieces is evaluated on the basis of numerical radiographies.The context of the study is the online control of the fuel rods production. A direct model of a numerical radiography formation is proposed and detailed for an acquisition system consisting of a CCD video connected to a converter screen by an optical system. As this approach does not allow the determination of the measured matter thickness from the X-ray photograph, an approximate model based on realistic approximations of the industrial non destructive testing, has been developed. For the specific cases it is possible to inverse the model and to reach the quantitative information present in the x-ray photograph, in other words, the map of the X-rays measured matter thickness. It becomes then possible to access to the quantitative parameters of the possible defects present in the measured specimen, such as the surface and the bulk. To reach the 3 D information on the defects a 3 D reconstruction method, from 3 X-rays photographs, is proposed.The inverse problem is solved by the non convex energy minimization. (A.L.B.) 109 refs.

Magnifying lens for 800 MeV proton radiography

International Nuclear Information System (INIS)

Merrill, F. E.; Campos, E.; Espinoza, C.; Hogan, G.; Hollander, B.; Lopez, J.; Mariam, F. G.; Morley, D.; Morris, C. L.; Murray, M.; Saunders, A.; Schwartz, C.; Thompson, T. N.

2011-01-01

This article describes the design and performance of a magnifying magnetic-lens system designed, built, and commissioned at the Los Alamos National Laboratory (LANL) for 800 MeV flash proton radiography. The technique of flash proton radiography has been developed at LANL to study material properties under dynamic loading conditions through the analysis of time sequences of proton radiographs. The requirements of this growing experimental program have resulted in the need for improvements in spatial radiographic resolution. To meet these needs, a new magnetic lens system, consisting of four permanent magnet quadrupoles, has been developed. This new lens system was designed to reduce the second order chromatic aberrations, the dominant source of image blur in 800 MeV proton radiography, as well as magnifying the image to reduce the blur contribution from the detector and camera systems. The recently commissioned lens system performed as designed, providing nearly a factor of three improvement in radiographic resolution.

Status of flash radiography in the USA today and future possibilities

International Nuclear Information System (INIS)

Bryant, L.E. Jr.

1978-01-01

A listing of presently employed flash x-ray generators is given including low-energy, commercially available systems and high-energy very specialized installations in government laboratories. These flash x-ray sources are compared as to radiographic characteristics. Imaging techniques and materials are surveyed and compared as to their advantages and limitations. A variety of applications of flash radiography are cited including explosive, ballistic, diffraction, crash injury, and fuel injection. Probable near term advances in special techniques are mentioned in cine radiography and film image enhancement. Possible future developments are speculated upon such as flash radiographic applications of computerized axial tomography. The recent recognition of flash radiography at professional society conferences is reviewed

Inspection of CF188 composite flight control surfaces with neutron radiography

International Nuclear Information System (INIS)

Lewis, W.J.; Bennett, L.G.I.; Mullin, S.K.

1996-01-01

At the Royal Military College of Canada's SLOWPOKE-2 Facility, a neutron radiography facility has been designed and installed using a small (20kWth), pool-type research reactor called the SLOWPOKE-2 (Safe Low Power c(K)ritical Experiment) as the neutron source. Since then, the research has continued along two fronts: developing applications and improving the quality of the neutron beam. The most interesting applications investigated to date has been the inspection of various metal ceramic composites and the inspection of the composite flight control surfaces of some of the CF188 Hornet aircraft. As part of the determination of the integrity of the aircraft, it was decided to inspect an aircraft with the highest flight house using both X- and neutron radiography. The neutron radiography and, to a lesser extent, X-radiography inspections completed at McClellan AFB revealed 93 anomalies. After returning to Canada, the component with the greatest structural significance, namely the right hand rudder from the vertical stabilizer, was removed from the aircraft and put through a rigorous program of numerous NDT inspections, including X-radiography (film and real-time), eddy current, ultrasonics (through transmission and pitch-catch), infrared thermography, and neutron radiography. Therefore, of all the techniques investigated, only through transmission ultrasonics and neutron radiography were able to identify large areas of hydration. However, only neutron radiography could identify the small areas of moisture and hydration. Given the structural significance of the flight control surfaces in modern fighter aircraft, even the smallest amounts of hydration could potentially lead to catastrophic results

Proton nuclear scattering radiography

International Nuclear Information System (INIS)

Saudinos, J.

1982-04-01

Nuclear scattering of protons allows to radiograph objects with specific properties: 3-dimensional radiography, different information as compared to X-ray technique, hydrogen radiography. Furthermore the nuclear scattering radiography (NSR) is a well adapted method to gating techniques allowing the radiography of fast periodic moving objects. Results obtained on phantoms, formalin fixed head and moving object are shown and discussed. The dose delivery is compatible with clinical use, but at the moment, the irradiation time is too long between 1 and 4 hours. Perspectives to make the radiograph faster and to get a practical method are discussed

Regulatory control of radiation sources in the Philippines

International Nuclear Information System (INIS)

Daroy, Rosita R.

1995-01-01

This paper is concerned with the radiation protection and safety infrastructure providing emphasis on the regulation and control of radiation sources in the Philippines. It deals with the experiences of the Philippine Nuclear Research Institute, as a regulatory body, in the regulation and control of radioactive materials in radiotherapy, nuclear medicine, industrial radiography, industrial gauges, industrial irradiators, and well logging. This paper includes an inventory of the sources and types of devices/equipment used by licensed users of radioactive materials in the Philippines as a contribution to the data base being prepared by the IAEA. The problems encountered by the regulatory body in the licensing and enforcement process, as well as the lessons learned from incidents involving radioactive materials are discussed. Plans for improving compliance to the regulations and enhancing the effectiveness of PNRI's regulatory functions are presented. (author)

Development of protocols for corrosion and deposits evaluation in pipes by radiography

International Nuclear Information System (INIS)

2005-04-01

The International Atomic Energy Agency is promoting industrial applications of non-destructive testing (NDT) technology, which includes radiography testing (RT) and related methods, to assure safety and reliability of operation of nuclear, petrochemical and other industrial facilities. In many industries such as petroleum, power stations, refineries, petrochemical and chemical plants, desalination pipelines and urban gas installations, the reliability and safety of equipment can be substantially influenced by degradation processes such as corrosion, erosion, deposits and blocking of pipes, which can seriously affect the security and consistency. One of the most important parameters in a piping or pipeline to be monitored and measured is the wall thickness. Among NDT methods, radiography has the advantage in that in the process of an inspection it eliminates the need for the costly removal of the pipe insulation and also the added benefit that it can be carried out in high temperature environments. The Coordinated Research Project (CRP) on Validation of Protocols for Corrosion and Deposits Determination in Small Diameter Pipes by Radiography (CORDEP) was implemented from 1997 to 2000 with the participation of 11 NDT laboratories from Algeria, China, Costa Rica, France, India, Republic of Korea, Malaysia, Sri Lanka, Syrian Arab Republic, Tunisia and Turkey. The CRP tested and validated radiographic measurement of corrosion and deposits in straight and bent pipes made of carbon or stainless steels corroded/eroded on the outer or inner surfaces with or without insulation. Each participating laboratory produced three test specimens of straight and bent pipes containing natural as well as simulated corrosion defects. Typical diameters of these pipes were up to 168 mm. Radiography using X ray machines and radioisotopes of Iridium-192 and Cobalt-60 in conjunction with radiographic film using single and double wall penetrations for total inspection was performed. Selected

The stationary neutron radiography system

International Nuclear Information System (INIS)

Weeks, A.A.; Newell, D.L.; Heidel, C.C.

1990-01-01

To provide the high intensity neutron beam and support systems necessary for radiography, the Stationary Neutron Radiography System was constructed at McClellan Air Force Base. The Stationary Neutron Radiography System utilizes a one megawatt TRIGA reactor contained in an Aluminium tank surrounded by eight foot thick concrete walls. There are four neutron beam tubes at inclined angles from the reactor core to separate radiography bays. In three of the bays, robotic systems manipulate aircraft components in the neutron beam, while real-time imaging systems provide images concurrent with the irradiation. Film radiography of smaller components is performed in the remaining bay

X-ray absorption radiography for high pressure shock wave studies

Science.gov (United States)

Antonelli, L.; Atzeni, S.; Batani, D.; Baton, S. D.; Brambrink, E.; Forestier-Colleoni, P.; Koenig, M.; Le Bel, E.; Maheut, Y.; Nguyen-Bui, T.; Richetta, M.; Rousseaux, C.; Ribeyre, X.; Schiavi, A.; Trela, J.

2018-01-01

The study of laser compressed matter, both warm dense matter (WDM) and hot dense matter (HDM), is relevant to several research areas, including materials science, astrophysics, inertial confinement fusion. X-ray absorption radiography is a unique tool to diagnose compressed WDM and HDM. The application of radiography to shock-wave studies is presented and discussed. In addition to the standard Abel inversion to recover a density map from a transmission map, a procedure has been developed to generate synthetic radiographs using density maps produced by the hydrodynamics code DUED. This procedure takes into account both source-target geometry and source size (which plays a non negligible role in the interpretation of the data), and allows to reproduce transmission data with a good degree of accuracy.

Progress and status of neutron radiography and gauging in Europe

International Nuclear Information System (INIS)

Balasko, Marton

1996-01-01

European neutron radiography (NR) stations, applications and main trends of progress are surveyed. NR laboratories installed at research reactors operating in eight countries. DIANE transportable neutron source has been constructed within the framework of EURECA project. High resolution film techniques and video imaging are used in various applications. In several cases NR is combined with other non-destructive methods. The European Neutron Radiography Working Group organizes annual meetings and international projects (COST, INCO Copernicus) to promote personal contacts and scientific cooperation in this field. (author)

Optimization of digital radiography techniques for specific application

International Nuclear Information System (INIS)

Harara, W.

2010-12-01

A low cost digital radiography system (DRS) for testing weld joints and castings in laboratory was assembled. The DRS is composed from X-ray source, scintillator, first surface mirror with Aluminum coating, charged coupled device (CCD) camera and lens. The DRS was used to test flawed carbon steel welded plates with thicknesses up to 12 mm. The comparison between the digital radiographs of the plates weldments and the radiographs of the same plates weldments using medium speed film type had shown that, the detection capability of the weld flaws are nearly identical for the two radiography techniques, while the sensitivity achieved in digital radiography of the plates weldments was one IQI wire less than the sensitivity achieved by conventional radiography of the same plates weldments according to EN 462-1. Further, the DRS was also successfully used to test (100 x 100 x 100) mm Aluminum casting with artificial flaws of varied dimensions and orientations. The resulted digital radiographs of the casting show that, all the flaws had been detected and their dimensions can be measured accurately, this confirm that, The proposed DRS can be used to detect and measure the flaws in the Aluminum and others light metals castings accurately. (author)

Evaluation of the map accuracy thickness defects by computer analysis of the radiography images

International Nuclear Information System (INIS)

Wawszczak, J.; Wocial, A.

2000-01-01

Analysis of the sensitivity map radiography for the local profiles of the surface steel plate with artificial of the thickness defects were presented of the paper. Errors of these method estimation and they sources were presented also. Usefulness of this mapping radiography during field investigations for paper and film carriers were discussed and concluded. (author)

Chest X-Ray (Chest Radiography)

Science.gov (United States)

... Resources Professions Site Index A-Z X-ray (Radiography) - Chest Chest x-ray uses a very small dose ... Radiography? What is a Chest X-ray (Chest Radiography)? The chest x-ray is the most commonly performed diagnostic ...

Medical radiography and information societies: Challenges and opportunities

International Nuclear Information System (INIS)

Kalra, H.P.S.

2006-01-01

This paper presents the perspective from a less developed country for broadening the horizon of medical imaging as an integral part of medical records and biomedical information. From the industrial to the information society, the number as well as the diversity of stakeholders in the medical records and medical information has grown. this call for a fresh outlook on medical radiography and medical imaging

Experimental study of self magnetic pinch diode as flash radiography source at 4 megavolt

International Nuclear Information System (INIS)

Etchessahar, Bertrand; Bicrel, Béatrice; Cassany, Bruno; Desanlis, Thierry; Voisin, Luc; Maisonny, Rémi; Toury, Martial; Hourdin, Laurent; Cartier, Frédéric; Cartier, Stéphanie; D'Almeida, Thierry; Delbos, Christophe; Garrigues, Alain; Plouhinec, Damien; Ritter, Sandra; Sol, David; Zucchini, Frédéric; Caron, Michel

2013-01-01

The Self Magnetic Pinch (SMP) diode is a potential high-brightness X-ray source for high voltage generators (2–10 MV) that has shown good reliability for flash radiography applications [D. D. Hinchelwood et al., “High power self-pinch diode experiments for radiographic applications” IEEE Trans. Plasma Sci. 35(3), 565–572 (2007)]. We have studied this diode at about 4 MV, driven by the ASTERIX generator operated at the CEA/GRAMAT [G. Raboisson et al., “ASTERIX, a high intensity X-ray generator,” in Proceedings of the 7th IEEE Pulsed Power Conference (1989), pp. 567–570]. This generator, made up of a capacitor bank and a Blumlein line, was initially designed to test the behavior of electronic devices under irradiation. In our experiments, the vacuum diode is modified in order to set up flash radiographic diodes. A previous set of radiographic experiments was carried out on ASTERIX with a Negative Polarity Rod Pinch (NPRP) diode [B. Etchessahar et al., “Study and optimization of negative polarity rod pinch diode as flash radiography source at 4.5 MV,” Phys. Plasmas 19(9), 093104 (2012)]. The SMP diode which is examined in the present study provides an alternative operating point on the same generator and a different radiographic performance: 142 ± 11 rad at 1 m dose (Al) for a 3.46 ± 0.42 mm spot size (1.4× FWHM of the LSF). This performance is obtained in a reproducible and robust nominal configuration. However, several parametric variations were also tested, such as cathode diameter and anode/cathode gap. They showed that an even better performance is accessible after optimization, in particular, a smaller spot size (<3 mm). Numbers of electrical, optical, and X-ray diagnostics have been implemented in order to gain more insight in the diode physics and to optimize it further. For the first time in France, visible and laser imaging of the SMP diode has been realized, from a radial point of view, thus, providing key information on the electrode

A system for fast neutron radiography

International Nuclear Information System (INIS)

Klann, R.T.

1996-01-01

A system has been designed and a neutron generator installed to perform fast neutron radiography. With this sytem, objects as small as a coin or as large as a waste drum can be radiographed. The neutron source is an MF Physics A-711 neutron generator which produces 3x10 10 neutrons/second with an average energy of 14.5 MeV. The radiography system uses x-ray scintillation screens and film in commercially available cassettes. The cassettes have been modified to include a thin sheet of plastic to convert neutrons to protons through elastic scattering from hydrogen and other low Z materials in the plastic. For film densities from 1.8 to 3.0, exposures range from 1.9x10 7 to 3.8x10 8 n/cm 2 depending on the type of screen and film

Locating industrial VOC sources with aircraft observations

International Nuclear Information System (INIS)

Toscano, P.; Gioli, B.; Dugheri, S.; Salvini, A.; Matese, A.; Bonacchi, A.; Zaldei, A.; Cupelli, V.; Miglietta, F.

2011-01-01

Observation and characterization of environmental pollution, focussing on Volatile Organic Compounds (VOCs), in a high-risk industrial area, are particularly important in order to provide indications on a safe level of exposure, indicate eventual priorities and advise on policy interventions. The aim of this study is to use the Solid Phase Micro Extraction (SPME) method to measure VOCs, directly coupled with atmospheric measurements taken on a small aircraft environmental platform, to evaluate and locate the presence of VOC emission sources in the Marghera industrial area. Lab analysis of collected SPME fibres and subsequent analysis of mass spectrum and chromatograms in Scan Mode allowed the detection of a wide range of VOCs. The combination of this information during the monitoring campaign allowed a model (Gaussian Plume) to be implemented that estimates the localization of emission sources on the ground. - Highlights: → Flight plan aimed at sampling industrial area at various altitudes and locations. → SPME sampling strategy was based on plume detection by means of CO 2 . → Concentrations obtained were lower than the limit values or below the detection limit. → Scan mode highlighted presence of γ-butyrolactone (GBL) compound. → Gaussian dispersion modelling was used to estimate GBL source location and strength. - An integrated strategy based on atmospheric aircraft observations and dispersion modelling was developed, aimed at estimating spatial location and strength of VOC point source emissions in industrial areas.

JRR-3 neutron radiography facility

International Nuclear Information System (INIS)

Matsubayashi, M.; Tsuruno, A.

1992-01-01

JRR-3 neutron radiography facility consists of thermal neutron radiography facility (TNRF) and cold neutron radiography facility (CNRF). TNRF is installed in JRR-3 reactor building. CNRF is installed in the experimental beam hall adjacent to the reactor building. (author)

Improvements in or relating to radiography

International Nuclear Information System (INIS)

Logan, A.B.; Marsh, R.G.; Fleming, I.A.

1980-01-01

Tomographic apparatus for use in biomedical radiography is described in detail. The radiation source and detectors are capable of rotating around the axis of the body under investigation to measure the absorption coefficients of a particular slice. Additionally, the detectors and source are capable of lateral motion across the body slice. Detailed suggestions of the number and optimum angular size of the detectors are given as well as the various angular steps of rotation of the source and detectors. Rotations in excess of 180 0 may be performed since the direction of travel of the X-radiation is not significant for constructing the absorption picture. (UK)

A light, superconducting H- cyclotron for medical diagnostics and neutron radiography

International Nuclear Information System (INIS)

Finlan, M.F.; Kruip, M.; Wilson, M.N.

1987-01-01

Oxford Instruments, working in close collaboration with Amersham International are developing a compact, lightweight, low radiation field superconducting cyclotron. The combination of superconductivity, H - acceleration and no internal yoke as such makes this possible. It is intended for use as a generator of short half lived isotopes for use in hospitals for PET and other imaging procedures, for use in industrial PET imaging, and as a neutron generator for neutron radiography. With a weight of 2000 kg, it is transportable and comparitively easy to handle and is capable in the 17 MeV version of generating 1.8 10 13 neutrons/second for neutron radiography. (author)

X-ray digital industrial radiography (DIR) for local liquid velocity (VLL) measurement in trickle bed reactors (TBRs): Validation of the technique

International Nuclear Information System (INIS)

Mohd Salleh, Khairul Anuar; Lee, Hyoung Koo; Rahman, Mohd Fitri Abdul; Al Dahhan, Muthanna H.

2014-01-01

Local liquid velocity measurements in Trickle Bed Reactors (TBRs) are one of the essential components in its hydrodynamic studies. These measurements are used to effectively determine a reactor's operating condition. This study was conducted to validate a newly developed technique that combines Digital Industrial Radiography (DIR) with Particle Tracking Velocimetry (PTV) to measure the Local Liquid Velocity (V LL ) inside TBRs. Three millimeter-sized Expanded Polystyrene (EPS) beads were used as packing material. Three validation procedures were designed to test the newly developed technique. All procedures and statistical approaches provided strong evidence that the technique can be used to measure the V LL within TBRs

Student Incivility in Radiography Education.

Science.gov (United States)

Clark, Kevin R

2017-07-01

To examine student incivility in radiography classrooms by exploring the prevalence of uncivil behaviors along with the classroom management strategies educators use to manage and prevent classroom disruptions. A survey was designed to collect data on the severity and frequency of uncivil student behaviors, classroom management strategies used to address minor and major behavioral issues, and techniques to prevent student incivility. The participants were educators in radiography programs accredited by the Joint Review Committee on Education in Radiologic Technology. Findings indicated that severe uncivil student behaviors in radiography classrooms do not occur as often as behaviors classified as less severe. Radiography educators in this study used a variety of strategies and techniques to manage and prevent student incivility; however, radiography educators who received formal training in classroom management reported fewer incidents of student incivility than those who had not received formal training. The participants in this study took a proactive approach to addressing severe behavioral issues in the classroom. Many radiography educators transition from the clinical environment to the classroom setting with little to no formal training in classroom management. Radiography educators are encouraged to attend formal training sessions to learn how to manage the higher education classroom effectively. Student incivility is present in radiography classrooms. This study provides a foundation for future research on incivility. ©2017 American Society of Radiologic Technologists.

Neutron radiography

International Nuclear Information System (INIS)

Alaa eldin, M.T.

2011-01-01

The digital processing of the neutron radiography images gives the possibility for data quantification. In this case an exact relation between the measured neutron attenuation and the real macroscopic attenuation coefficient for every point of the sample is required. The assumption that the attenuation of the neutron beam through the sample is exponential is valid only in an ideal case where a monochromatic beam, non scattering sample and non background contribution are assumed. In the real case these conditions are not fulfilled and in dependence on the sample material we have more or less deviation from the exponential attenuation law. Because of the high scattering cross-sections of hydrogen (σs=80.26 barn) for thermal neutrons, the problem with the scattered neutrons at quantitative radiography investigations of hydrogenous materials (as PE, Oil, H 2 O, etc) is not trivial. For these strong scattering materials the neutron beam attenuation is no longer exponential and a dependence of the macroscopic attenuation coefficient on the material thickness and on the distance between the sample and the detector appears. When quantitative radiography (2 D) or tomography investigations (3 D) are performed, some image correction procedures for a description of the scattering effect are required. This thesis presents a method that can be used to enhance the neutron radiography image for objects with high scattering materials like hydrogen, carbon and other light materials. This method uses the Monte Carlo code, MCNP5, to simulate the neutron radiography process and get the flux distribution for each pixel of the image and determine the scattered neutrons distribution that causes the image blur and then subtract it from the initial image to improve its quality.

The development of neutron radiography and its potential application in Malaysia

International Nuclear Information System (INIS)

Azali Muhammad

1994-01-01

The development of neutron radiography in Malaysia started with the availability of the country's first research reactor. The 1MW reactor was commissioned in June 1982, mainly for research purposes and the development of neutron radiography was one of the main application. In late 1983, a neutron radiography test facility known as NuR-1 was constructed out of small modular concrete blocks. Tests carried out in this facility enabled the design of the permanent facility known as NuR-2 to be finalised. The construction of NuR-2 took place in November 1984 and was completed in February 1985. In January 1987, a new collimator was installed in NuR-2 and direct exposure method was successfully performed using gadolinium metal converter and Kodak SR film. This facility will be used to solve specific problems in the field of air-craft, explosive, electronic and rubber industries, and also some research programs in biology

Recovery from Iridium-192 flakes of a radioactive source for industrial use after a radiation incident; Recuperacion de hojuelas de Iridio-192 provenientes de una fuente radiactivas de uso industrial despues de un incidente radiologico

Energy Technology Data Exchange (ETDEWEB)

Cruz, W.H.; Zapata, L.A., E-mail: wcruz@ipen.gob.pe, E-mail: lzapata@ipen.gob.pe [Instituto Peruano de Energia Nuclear (GRRA/IPEN), Lima (Peru). Division de Gestion de Residuos Radiactivos

2013-07-01

The Iridium-192 ({sup 192}Ir) is the most used and ideal for industrial radiography applications, especially in petrochemical plants and pipelines and provides better contrast sensitivity for thick (25.4 mm). This source has constructive sealed double encapsulation, the internal capsule containing stainless steel to radioactive material in the form of flakes and welded with TIG process. The radiological incident happened at a gas station fuel sales in circumstances in which there was a homogeneity test welds a tank, the flakes or Ir-192 fell off his ponytail and left scattered over an area of 2 m{sup 2}, some fell flat areas and other land so collected in lead shielding and metal container and ground source. Full recovery of the leaflets was performed at the Division of radioactive waste management (GRRA) gaining a total of 22 flakes with no radiation risk to staff performance and installation and the conclusion was reached that the misapplicaion of TIG welding was the main cause the incident. (author)

Assessment of risk of potential exposures on facilities industries; Estimativa do risco de exposicao potencial em instalacoes industriais

Energy Technology Data Exchange (ETDEWEB)

Leocadio, Joao Carlos

2007-03-15

This work develops a model to evaluate potential exposures on open facilities of industrial radiography in Brazil. This model will decisively contribute to optimize operational, radiological protection and safety procedures, to prevent radiation accidents and to reduce human errors in industrial radiography. The probabilistic safety assessment (PSA) methodology was very useful to assess potential exposures. The open facilities of industrial radiography were identified as the scenario to be analyzed in what concerns the evaluation of potential exposures, due to their high accidents indices. The results of the assessment of potential exposures confirm that the industrial radiography in Brazil is a high-risk practice as classified by the IAEA. The risk of potential exposure was estimated to be 40,5 x 10{sup -2} per year in Brazil, having as main consequences injuries to the workers' hands and arms. In the world scene, the consequences are worst, leading to fatalities of people, thus emphasizing the high risk of industrial radiography. (author)

Assessment of risk of potential exposures on facilities industries; Estimativa do risco de exposicao potencial em instalacoes industriais

Energy Technology Data Exchange (ETDEWEB)

Leocadio, Joao Carlos

2007-03-15

This work develops a model to evaluate potential exposures on open facilities of industrial radiography in Brazil. This model will decisively contribute to optimize operational, radiological protection and safety procedures, to prevent radiation accidents and to reduce human errors in industrial radiography. The probabilistic safety assessment (PSA) methodology was very useful to assess potential exposures. The open facilities of industrial radiography were identified as the scenario to be analyzed in what concerns the evaluation of potential exposures, due to their high accidents indices. The results of the assessment of potential exposures confirm that the industrial radiography in Brazil is a high-risk practice as classified by the IAEA. The risk of potential exposure was estimated to be 40,5 x 10{sup -2} per year in Brazil, having as main consequences injuries to the workers' hands and arms. In the world scene, the consequences are worst, leading to fatalities of people, thus emphasizing the high risk of industrial radiography. (author)

Digital chest radiography

DEFF Research Database (Denmark)

Debess, Jeanne Elisabeth; Johnsen, Karen Kirstine; Thomsen, Henrik

on collimation and dose reduction in digital chest radiography Methods and Materials A retrospective study of digital chest radiography is performed to evaluate the primary x-ray tube collimation of the PA and lateral radiographs. Data from one hundred fifty self-reliant female patients between 15 and 55 years...

Characterization of mono-ethylene-glycol based industrial polyurethanes samples by fast-neutron radiography and neutron tomography

Science.gov (United States)

Rogante, Massimo; Söllradl, Stefan

2016-09-01

A complicated structural organization of polyurethanes may have a strong influence on the materials functional properties. Under particular conditions such as mechanical and thermal loading and aging, it leads to the material degradation, even in fresh-prepared bulk polymers and especially if defects are present in the material. Unwanted bubbles can be observed, which form during the expansion of the mixture during its chemical reaction and remain present in the final product. These macro-, micro- and nano-bubbles influence the material's performance. In this work, neutron radiography and tomography have been adopted to characterize at a macro-scale level the bulk of commercially available polyurethane samples, obtained from dissimilar- mixture ratios with different densities and branching levels as well as from different zones of the production mould. The characterisation allowed an estimation of the different dense materials - as they are used, e.g., in soles of shoes - as well as the invisible defects like pores and cracks, responsible for the materials fracture by mechanical loading. The obtained information are expected to be useful for various industrial sectors such as automotive and footwear industry. It will be completed by applying SANS, which has already proved to characterize the microstructure of the bulk-polymer with respect to nano-pores, micro-cracks and their arrangement in the polymer matrix.

Characterization of mono-ethylene-glycol based industrial polyurethanes samples by fast-neutron radiography and neutron tomography

International Nuclear Information System (INIS)

Rogante, Massimo; Söllradl, Stefan

2016-01-01

A complicated structural organization of polyurethanes may have a strong influence on the materials functional properties. Under particular conditions such as mechanical and thermal loading and aging, it leads to the material degradation, even in fresh-prepared bulk polymers and especially if defects are present in the material. Unwanted bubbles can be observed, which form during the expansion of the mixture during its chemical reaction and remain present in the final product. These macro-, micro- and nano-bubbles influence the material's performance. In this work, neutron radiography and tomography have been adopted to characterize at a macro-scale level the bulk of commercially available polyurethane samples, obtained from dissimilar- mixture ratios with different densities and branching levels as well as from different zones of the production mould. The characterisation allowed an estimation of the different dense materials - as they are used, e.g., in soles of shoes - as well as the invisible defects like pores and cracks, responsible for the materials fracture by mechanical loading. The obtained information are expected to be useful for various industrial sectors such as automotive and footwear industry. It will be completed by applying SANS, which has already proved to characterize the microstructure of the bulk-polymer with respect to nano-pores, micro-cracks and their arrangement in the polymer matrix. (paper)

Portable abdomen radiography. Moving to thickness-based protocols

International Nuclear Information System (INIS)

Sanchez, Adrian A.; Reiser, Ingrid; Baxter, Tina; Zhang, Yue; Finkle, Joshua H.; Lu, Zheng Feng; Feinstein, Kate A.

2018-01-01

Default pediatric protocols on many digital radiography systems are configured based on patient age. However, age does not adequately characterize patient size, which is the principal determinant of proper imaging technique. Use of default pediatric protocols by inexperienced technologists can result in patient overexposure, inadequate image quality, or repeated examinations. To ensure diagnostic image quality at a well-managed patient radiation exposure by transitioning to thickness-based protocols for pediatric portable abdomen radiography. We aggregated patient thickness data, milliamperes (mAs), kilovoltage peak (kVp), exposure index (EI), source-to-detector distance, and grid use for all portable abdomen radiographs performed in our pediatric hospital in a database with a combination of automated and manual data collection techniques. We then analyzed the database and used it as the basis to construct thickness-based protocols with consistent image quality across varying patient thicknesses, as determined by the EI. Retrospective analysis of pediatric portable exams performed at our adult-focused hospitals demonstrated substantial variability in EI relative to our pediatric hospital. Data collection at our pediatric hospital over 4 months accumulated roughly 800 portable abdomen exams, which we used to develop a thickness-based technique chart. Through automated retrieval of data in our systems' digital radiography exposure logs and recording of patient abdomen thickness, we successfully developed thickness-based techniques for portable abdomen radiography. (orig.)

Portable abdomen radiography. Moving to thickness-based protocols

Energy Technology Data Exchange (ETDEWEB)

Sanchez, Adrian A.; Reiser, Ingrid; Baxter, Tina; Zhang, Yue; Finkle, Joshua H.; Lu, Zheng Feng; Feinstein, Kate A. [University of Chicago Medical Center, Department of Radiology, Chicago, IL (United States)

2018-02-15

Default pediatric protocols on many digital radiography systems are configured based on patient age. However, age does not adequately characterize patient size, which is the principal determinant of proper imaging technique. Use of default pediatric protocols by inexperienced technologists can result in patient overexposure, inadequate image quality, or repeated examinations. To ensure diagnostic image quality at a well-managed patient radiation exposure by transitioning to thickness-based protocols for pediatric portable abdomen radiography. We aggregated patient thickness data, milliamperes (mAs), kilovoltage peak (kVp), exposure index (EI), source-to-detector distance, and grid use for all portable abdomen radiographs performed in our pediatric hospital in a database with a combination of automated and manual data collection techniques. We then analyzed the database and used it as the basis to construct thickness-based protocols with consistent image quality across varying patient thicknesses, as determined by the EI. Retrospective analysis of pediatric portable exams performed at our adult-focused hospitals demonstrated substantial variability in EI relative to our pediatric hospital. Data collection at our pediatric hospital over 4 months accumulated roughly 800 portable abdomen exams, which we used to develop a thickness-based technique chart. Through automated retrieval of data in our systems' digital radiography exposure logs and recording of patient abdomen thickness, we successfully developed thickness-based techniques for portable abdomen radiography. (orig.)

Proton radiography of magnetic field in laser produced plasma

International Nuclear Information System (INIS)

Le Pape, S.; Patel, P.; Chen, S.; Town, R.; Mackinnon, A.

2009-01-01

Electromagnetic fields generated by the interaction with plasmas of long-pulse laser beams relevant to inertial confinement fusion have been measure. A proton beam generated by the interaction of an ultra intense laser with a thin metallic foil is used to probe the B-fields. The proton beam then generated is temporally short (of the order of a ps), highly laminar and hence equivalent to a virtual point which makes it an ideal source for radiography. We have investigated, using face-on radiography, B fields at intensity around 10 14 W/cm 2 due to the non co-linearity of temperature and density gradients. (authors)

Analyze image quality and comparative study between conventional and computed radiography applied to the inspection of alloys

International Nuclear Information System (INIS)

Machado, Alessandra S.; Oliveira, Davi F.; Silva, Aline S.S.; Nascimento, Joseilson R.; Lopes, Ricardo T.

2011-01-01

Piping system design takes into account relevant factors such as: internal coating, dimensioning, vibration system, adequate supports and principally, piping material. Cost is a decisive factor in the phase of material selection. The non-destructive testing method most commonly employed in industry to analyze the structure of an object is radiographic testing. Computed radiography (CR) is a quicker and much more efficient alternative to conventional radiography but, although CR presents numerous advantages, testing procedures are still largely based on trial and error, due to the lack of a consecrated methodology to choose parameters as it exists for conventional radiography. Notwithstanding, this paper presents a study that uses the technique of computed radiography to analyze metal alloys. These metal alloys are used as internal pipe coating aiming to protect against corrosion and cracks. This study seeks to evaluate parameters such as basic spatial resolution, Normalized Signal-to-Noise Ratio (SNRN), contrast, intensity and also to compare conventional radiography with CR. (author)

Apparatus for gamma ray radiography

International Nuclear Information System (INIS)

Kobayashi, Masatoshi; Enomoto, Shigemasa; Oga, Hiroshi

1979-01-01

This is the standard of Japan Non-Destructive Inspection Society, NDIS 1101-79, which stipulates on the design, construction and testing method of the apparatuses for gamma ray radiography used for taking industrial radiograms. The gamma ray apparatuses stipulated in this standard are those containing sealed radioactive isotopes exceeding 100 μCi, which emit gamma ray. The gamma ray apparatuses are classified into three groups according to their movability. The general design conditions, the irradiation dose rate and the sealed radiation sources for the gamma ray apparatuses are stipulated. The construction of the gamma ray apparatuses must be in accordance with the notification No. 52 of the Ministry of Labor, and safety devices and collimators must be equipped. The main bodies of the gamma ray apparatuses must pass the vibration test, penetration test, impact test and shielding efficiency test. The method of each test is described. The attached equipments must be also tested. The tests according to this standard are carried out by the makers of the apparatuses. The test records must be made when the apparatuses have passed the tests, and the test certificates are attached. The limit of guarantee by the endurance test must be clearly shown. The items to be shown on the apparatuses are stipulated. (Kako, I.)

Dose Estimates for Site Radiography outside the Border to the Premises

Energy Technology Data Exchange (ETDEWEB)

Tanzi, C. P.; Eleveld, H.

2004-07-01

Radiography with X-ray generators or sealed radioactive sources (e.g. cobalt-60 and iridium-192) is a well-established non-destructive technique for the detection of internal flaws in welds and castings. The quality of the weld during the fabrication of pressure vessels, pipelines, storage tanks and other engineering structures can thus be verified. Often radiography is performed in an adequately shielded enclosure, but it may be necessary to perform it on location (site radiography). Paradoxically, if measurements are performed with other employees present, the main beam might be directed away towards the border of the premises in order to minimise the exposure of the workers but thus increasing the potential exposure to the population. In all cases a clearly marked enclosure has to be defined, to which neither non-radiological workers nor members of the public can have access. During a testing period, the maximum allowed dose rate at this enclosure is 10 microSv in one hour (only in exceptional cases 40 microSv) in the Netherlands. In addition, the Decree on radiation protection (in Dutch: {sup B}esluit stralingsbescherming{sup e}stablishes a further limit per location of 100 microSv per year, and the duty of reporting when the number of 3300 recordings at any one site is reached. This number is based on the assumption of a multifunctional individual dose of 0.03 microSv per recording at the enclosure. This multifunctional individual dose is defined as the dose received of an individual who lives in the vicinity of the source or location; this is a conservative approach considering the fact that the area around an industrial site is usually not intended to be residential area. However, for radiography in the field, skyshine might be underestimated, good collimation of the beam might not be seen as a priority, and the required monitoring may be difficult to guarantee along all of the enclosure. Also, there is an increasing availability of commercial portable X

Dose Estimates for Site Radiography outside the Border to the Premises

International Nuclear Information System (INIS)

Tanzi, C. P.; Eleveld, H.

2004-01-01

Radiography with X-ray generators or sealed radioactive sources (e.g. cobalt-60 and iridium-192) is a well-established non-destructive technique for the detection of internal flaws in welds and castings. The quality of the weld during the fabrication of pressure vessels, pipelines, storage tanks and other engineering structures can thus be verified. Often radiography is performed in an adequately shielded enclosure, but it may be necessary to perform it on location (site radiography). Paradoxically, if measurements are performed with other employees present, the main beam might be directed away towards the border of the premises in order to minimise the exposure of the workers but thus increasing the potential exposure to the population. In all cases a clearly marked enclosure has to be defined, to which neither non-radiological workers nor members of the public can have access. During a testing period, the maximum allowed dose rate at this enclosure is 10 microSv in one hour (only in exceptional cases 40 microSv) in the Netherlands. In addition, the Decree on radiation protection (in Dutch: B esluit stralingsbescherming e stablishes a further limit per location of 100 microSv per year, and the duty of reporting when the number of 3300 recordings at any one site is reached. This number is based on the assumption of a multifunctional individual dose of 0.03 microSv per recording at the enclosure. This multifunctional individual dose is defined as the dose received of an individual who lives in the vicinity of the source or location; this is a conservative approach considering the fact that the area around an industrial site is usually not intended to be residential area. However, for radiography in the field, skyshine might be underestimated, good collimation of the beam might not be seen as a priority, and the required monitoring may be difficult to guarantee along all of the enclosure. Also, there is an increasing availability of commercial portable X-ray units

Real-time radiography

International Nuclear Information System (INIS)

Bossi, R.H.; Oien, C.T.

1981-01-01

Real-time radiography is used for imaging both dynamic events and static objects. Fluorescent screens play an important role in converting radiation to light, which is then observed directly or intensified and detected. The radiographic parameters for real-time radiography are similar to conventional film radiography with special emphasis on statistics and magnification. Direct-viewing fluoroscopy uses the human eye as a detector of fluorescent screen light or the light from an intensifier. Remote-viewing systems replace the human observer with a television camera. The remote-viewing systems have many advantages over the direct-viewing conditions such as safety, image enhancement, and the capability to produce permanent records. This report reviews real-time imaging system parameters and components

Application of X-ray radiography to archaeology

International Nuclear Information System (INIS)

Miura, Sadatoshi

1994-01-01

X-ray imaging techniques including radiography and scanning tomography are now often applied to archaeological and historical objects. In this report results of three imaging techniques are showed: radiography, X-ray scanning tomography and emissiography. X-ray radiography was applied to examine the technique used for a bronze object. The object was one of the national treasure from Horyuji-temple, Dragon-head Pitcher. The examination proved that the pitcher body was separated into three pieces and that the bronze was fairly homogeneous from 3 to 4 mm. The Pitcher was supposed to be made in Japan at the middle of the seventh century. A small gilt bronze statuette was investigated by an industrial X-ray scanner. The statuette about 30 cm high is supposed to be made in the seventh or eighth century. The head of the statuette was scanned by X-rays of 350kV. The computed tomograms revealed an inlaid metal and scraped hollow. It is supposed that the statuette was cast twice. The first casting might have failed causing the hollow and the missing part of the head. The hollow was scraped before the following casting so that the newly cast part would be tightly joined to the body. A piece of metal was inlaid to the missing part. A silver inlaid sword was excavated at a historic site called Etafunayama Kofun in Kumamoto in 1873. Seventy-five letters were discovered on the back of the sword, and they were regarded as important reference in studying Japanese history around the fifth century. However, the letters became illegible because of severe surface corrosion. So emissiography or electron radiography was used. All letters and even the details could be read. (author)

Dental radiography

International Nuclear Information System (INIS)

Shekhdar, J.

1993-01-01

Dental radiography must comply with the same regulations with which conventional radiography complies. Radiation doses to individual patients are low but, because of the large number of patients X-rayed, the collective dose to the population is not negligible. Care in siting and regular maintenance of the equipment will reduce doses to both staff and patients. To produce X-ray films with a good image quality using a low radiation dose requires attention to film processing; this is often a neglected area. (Author)

Safety assessment plans for authorization and inspection of radiation sources

International Nuclear Information System (INIS)

2002-05-01

The objective of this TECDOC is to enhance the efficacy, quality and efficiency of the whole regulatory process. It provides advice on good practice administrative procedures for the regulatory process for preparation of applications, granting of authorizations, inspection, and enforcement. It also provides information on the development and use of standard safety assessment plans for authorization and inspection. The plans are intended to be used in conjunction with more detailed advice related to specific practices. In this sense, this TECDOC provides advice on a systematic approach to evaluations of protection and safety while other IAEA Safety Guides assist the user to distinguish between the acceptable and the unacceptable. This TECDOC covers administrative advice to facilitate the regulatory process governing authorization and inspection. It also covers the use of standard assessment and inspection plans and provides simplified plans for the more common, well established uses of radiation sources in medicine and industry, i.e. sources for irradiation facilities, industrial radiography, well logging, industrial gauging, unsealed sources in industry, X ray diagnosis, nuclear medicine, teletherapy and brachytherapy

Safety assessment plans for authorization and inspection of radiation sources

International Nuclear Information System (INIS)

1999-09-01

The objective of this TECDOC is to enhance the efficacy, quality and efficiency of the whole regulatory process. It provides advice on good practice administrative procedures for the regulatory process for preparation of applications, granting of authorizations, inspection, and enforcement. It also provides information on the development and use of standard safety assessment plans for authorization and inspection. The plans are intended to be used in conjunction with more detailed advice related to specific practices. In this sense, this TECDOC provides advice on a systematic approach to evaluations of protection and safety while other IAEA Safety Guides assist the user to distinguish between the acceptable and the unacceptable. This TECDOC covers administrative advice to facilitate the regulatory process governing authorization and inspection. It also covers the use of standard assessment and inspection plans and provides simplified plans for the more common, well established uses of radiation sources in medicine and industry, i.e. sources for irradiation facilities, industrial radiography, well logging, industrial gauging, unsealed sources in industry, X ray diagnosis, nuclear medicine, teletherapy and brachytherapy

A system for fast neutron radiography

International Nuclear Information System (INIS)

Klann, R.T.

1997-01-01

A system has been designed and a neutron generator installed to perform fast neutron radiography. With this system, objects as small as a coin and as large as a 19 liter container have been radiographed. The neutron source is an MF Physics A-711 neutron generator which produces 3 x 10[sup 10] neutrons/second with an average energy of 14. 5 MeV. The radiography system uses x-ray scintillation screens and film in commercially available light-tight cassettes. The cassettes have been modified to include a thin sheet of plastic to produce protons from the neutron beam through elastic scattering from hydrogen and other low Z materials in the plastic. For film densities from 1.8 to 3.0, exposures range from 1.9 x 10[sup 7] n/cm[sup 2] to 3.8 x 10[sup 8] n/cm[sup 2] depending on the type of screen and film. The optimum source-to-film distance was found to be 150 cm. At this distance, the geometric unsharpness was determined to be approximately 2.2-2.3 mm and the smallest hole that could be resolved in a 1.25 cm thick sample had a diameter of 0.079 cm

Regulatory control of radiation sources in the Philippines

Energy Technology Data Exchange (ETDEWEB)

Daroy, Rosita R

1996-12-31

This paper is concerned with the radiation protection and safety infrastructure providing emphasis on the regulation and control of radiation sources in the Philippines. It deals with the experiences of the Philippine Nuclear Research Institute, as a regulatory body, in the regulation and control of radioactive materials in radiotherapy, nuclear medicine, industrial radiography, industrial gauges, industrial irradiators, and well logging. This paper includes an inventory of the sources and types of devices/equipment used by licensed users of radioactive materials in the Philippines as a contribution to the data base being prepared by the IAEA. The problems encountered by the regulatory body in the licensing and enforcement process, as well as the lessons learned from incidents involving radioactive materials are discussed. Plans for improving compliance to the regulations and enhancing the effectiveness of PNRI`s regulatory functions are presented. (author). Paper presented during the IAEA Regional (RCA) Workshop on System of Notification, Registration, Licensing, and Control of Radiation Sources and Installations, Jakarta, Indonesia, 24-28 April 1995. 6 refs., 2 figs., 12 tabs.

X-ray digital industrial radiography (DIR) for local liquid velocity (V(LL)) measurement in trickle bed reactors (TBRs): validation of the technique.

Science.gov (United States)

Mohd Salleh, Khairul Anuar; Rahman, Mohd Fitri Abdul; Lee, Hyoung Koo; Al Dahhan, Muthanna H

2014-06-01

Local liquid velocity measurements in Trickle Bed Reactors (TBRs) are one of the essential components in its hydrodynamic studies. These measurements are used to effectively determine a reactor's operating condition. This study was conducted to validate a newly developed technique that combines Digital Industrial Radiography (DIR) with Particle Tracking Velocimetry (PTV) to measure the Local Liquid Velocity (V(LL)) inside TBRs. Three millimeter-sized Expanded Polystyrene (EPS) beads were used as packing material. Three validation procedures were designed to test the newly developed technique. All procedures and statistical approaches provided strong evidence that the technique can be used to measure the V(LL) within TBRs.

Magnification radiography

International Nuclear Information System (INIS)

Genant, H.K.; Resnick, D.

1988-01-01

The relative clinical value of magnification compared with conventional radiography for skeletal applications is presented qualitatively. The presentation is based on the authors' experience with over 25,000 cases in which magnification has been used. For most areas in which magnification (optical or geometric) proves useful, subtle abnormalities of clinical importance are present at bone surfaces or at host-lesion interfaces. This is particularly true for arthritis and metabolic and infectious disorders of bone. In additional instances, serial assessment of the progression of disease or its response to therapy is enhanced by magnification. When gross abnormalities are present, as in most instances of trauma and bone dysplasia, the findings are obvious on conventional radiography, and magnification is not necessary. Thus, the magnification techniques appear to provide important diagnostic information, depending upon the anatomic part that is studied and the clinical question that is posed. It is also apparent that the demonstration of subtle skeletal abnormalities to clinical colleagues for educational purposes is greatly enhanced by magnification radiography

Bone X-Ray (Radiography)

Medline Plus

Full Text Available ... are the limitations of Bone X-ray (Radiography)? What is Bone X-ray (Radiography)? An x-ray ( ... leg (shin), ankle or foot. top of page What are some common uses of the procedure? A ...

Radioactive sources in trade and industry

International Nuclear Information System (INIS)

Vroom, H.; Bolt, R.; Lange, H. de.

1989-04-01

An inventory has been drawn up of the most important applications of radioactive sources in the Netherlands, with emphasis on nuclear measuring instruments for industrial use. This inventory has been supplemented with a brief survey of the most important legal demand (among which, the 'decree radiation protection') with regard to the use of such instruments and some data about the construction of the radioactive source present in the instrument. Also the processing of exhausted sources is discussed briefly. (author). 14 refs.; 3 figs.; 6 tabs

Plasma focus sources: Supplement to the neutron resonance radiography workshop proceedings

International Nuclear Information System (INIS)

Nardi, V.; Brzosko, J.

1989-01-01

Since their discovery, plasma focus discharges have been recognized as very intense pulsed sources of deuterium-deuterium (D-D) or deuterium-tritium (D-T) fusion-reaction neutrons, with outstanding capabilities. Specifically, the total neutron emission/shot, YN, and the rate of neutron emission, Y/sub n/, of an optimized plasma focus (PF) are higher than the corresponding quantities observed in any other type of pinched discharge at the same level of powering energy W 0 . Recent developments have led to the concept and experimental demonstration of an Advanced Plasma Focus System (APF) that consists of a Mather-geometry plasma focus in which field distortion elements (FDEs) are inserted in the inter-electrode gap for increasing the neutron yield/shot, Y/sub n/. The FDE-induced redistribution of the plasma current increases Y/sub n/ by a factor ≅5-10 above the value obtained without FDEs under otherwise identical conditions of operation of the plasma focus. For example, an APF that is fed by a fast capacitor bank with an energy, W 0 = 6kJ, and voltage, V 0 = 16.5 kV provides Y/sub n/ /congruent/ 4 /times/ 10 9 D-D neutrons/shot (pure D 2 filling) and Y/sub n/ = 4 /times/ 10 11 D-T neutrons/shot (filling is 50% deuterium and 50% tritium). The FDE-induced increase of Y/sub n/ for fixed values of (W 0 , V 0 ), the observed scaling law Y/sub n/ /proportional to/ W 0 2 for optimized plasma focus systems, and our experience with neutron scattering in bulk objects lead us to the conclusion that we can use an APF as a source of high-intensity neutron pulses (10 14 n/pulse) in the field off neutron radiography (surface and bulk) with a nanosecond or millisecond time resolution

Transitioning to digital radiography

Energy Technology Data Exchange (ETDEWEB)

Miranda, F., E-mail: Francisco.Miranda@pwc.ca [Pratt & Whitney Canada, Longueuil, Quebec (Canada)

2015-09-15

This article provides insight on the technical and business considerations necessary to implement or to transition to digital radiography Continued refinements in digital radiography technology have resulted in significant improvements in image quality and detectability of indications. These improvements have resulted in the acceptance of the technology by users and aerospace primes for final product inspection and disposition. Digital radiography has also been identified as an interesting cost reduction initiative with the potential of providing gains in productivity through increased throughput and decreased inspection lead-times and resulting costs. (author)

The stationary neutron radiography system: a TRIGA-based production neutron radiography facility

International Nuclear Information System (INIS)

Chesworth, Robert H.; Hagmann, Dean B.

1988-01-01

General Atomics (GA) is under contract to construct a Stationary Neutron Radiography System (SNRS) - on a turnkey basis - at McClellan Air Force Base in Sacramento, California. The SNRS is a custom designed neutron radiography system which will utilize a 1000 KW TRIGA reactor as the neutron source. The partially below-ground reactor will be equipped with four inclined beam tubes originating near the top of the reactor graphite reflector and installed tangential to the reactor core to provide a strong current of thermal neutrons with minimum gamma ray contamination. The inclined beam tubes will terminate in four large bays and will interface with rugged component positioning systems designed to handle intact aircraft wings, other honeycomb aircraft structures, and pyrotechnics. The SNRS will be equipped with real-time, near real-time, and film radiographic imaging systems to provide a broad spectrum of capability for detection of entrained moisture or corrosion in large aircraft panels. GA is prime contractor to the Air Force for the SNRS and is specifically responsible for the TRIGA reactor system and a portion of the neutron beam system design. Science Applications International Corporation and the Lionakis-Beaumont Design Group are principal subcontractors to GA on the project. (author)

Development of Portable Digital Radiography System with a Device for Monitoring X-ray Source-Detector Angle and Its Application in Chest Imaging

Directory of Open Access Journals (Sweden)

Tae-Hoon Kim

2017-03-01

Full Text Available This study developed a device measuring the X-ray source-detector angle (SDA and evaluated the imaging performance for diagnosing chest images. The SDA device consisted of Arduino, an accelerometer and gyro sensor, and a Bluetooth module. The SDA values were compared with the values of a digital angle meter. The performance of the portable digital radiography (PDR was evaluated using the signal-to-noise (SNR, contrast-to-noise ratio (CNR, spatial resolution, distortion and entrance surface dose (ESD. According to different angle degrees, five anatomical landmarks were assessed using a five-point scale. The mean SNR and CNR were 182.47 and 141.43. The spatial resolution and ESD were 3.17 lp/mm (157 μm and 0.266 mGy. The angle values of the SDA device were not significantly difference as compared to those of the digital angle meter. In chest imaging, the SNR and CNR values were not significantly different according to the different angle degrees. The visibility scores of the border of the heart, the fifth rib and the scapula showed significant differences according to different angles (p < 0.05, whereas the scores of the clavicle and first rib were not significant. It is noticeable that the increase in the SDA degree was consistent with the increases of the distortion and visibility score. The proposed PDR with a SDA device would be useful for application in the clinical radiography setting according to the standard radiography guidelines.

Digital radiography of the chest

International Nuclear Information System (INIS)

Sakurai, Kenji; Hachiya, Junichi; Korenaga, Tateo; Nitatori, Toshiaki; Miyasaka, Yasuo; Furuya, Yoshiro

1984-01-01

Initial clinical experience in digital chest radiography utilizing photostimulable phosphor and scanning laser stimulated luminescence was reported. Image quality of conventional film/screen radiography and digital radiography was compared in 30 normal cases. Reflecting wide dynamic range of the system, improved image quality was confirmed in all 30 cases, particularly in visibility of various mediastinal structures and pulmonary vessels. High sensor sensitivity of the system enabled digital radiography to reduce radiation dose requirement significantly. Diagnostically acceptable chest images were obtained with approximately 1/5 of routine dose for conventional radiography without significant image quality degradation. Some artifact created by digital processing were mostly overcome by a routine use of simultaneous display of two different types of image processing and therefore was not an actual drawback from diagnostic standpoint. Further technical advancement of the system to be seen for digital storage, retrieval and tranceference of images. (author)

neutron radiography. Report prepared from contributions by members of the MOD Working Party on Neutron Radiography

International Nuclear Information System (INIS)

Halmshaw, R.

1977-03-01

Radiography with thermal or cold neutrons has some special advantages over X-rays and gamma rays, and some facilities for neutron radiography exist in the Ministry of Defence. This report gives a brief and simple description of the technique, its advantages and disadvantages, and is illustrated with a number of Ordnance applications taken from MOD work, to show examples where neutron radiographs provided extra important information not available from X- or gamma radiography. The facilities available in the UK for neutron radiography are listed. (author)

Quality assurance in digital radiography

International Nuclear Information System (INIS)

Busch, H.P.; Lehmann, K.J.

1989-01-01

At present, there is no standard way of evaluating performance characteristics of digital radiography systems. Continuous measurements of performance parameters are necessary in order to obtain images of high quality. Parameters of quality assurance in digital radiography, which can be evaluated with simple, quick methods, are spatial resolution, low-contrast detectability, dynamic range and exposure dose. Spatial resolution was determined by a lead bar pattern, whereas the other parameters were measured by commercially available phantoms. Performance measurements of 10 digital subtraction angiography (DSA) units and one digital radiography system for unsubtracted digital radiography were assessed. From these results, recommendations for performance parameter levels will be discussed. (author)

Selenium-based digital radiography of the cervical spine. Comparison with screen-film radiography for the depiction of anatomic details

International Nuclear Information System (INIS)

Ludwig, K.; Diederich, S.; Wormanns, D.; Link, T.M.; Lenzen, H.; Heindel, W.

2002-01-01

Purpose: To compare selenium-based digital radiography with conventional screen-film radiography of the cervical spine. Materials and Methods: In a prospective study X-ray images of the cervical spine were obtained in 25 patients using selenium-based digital radiography and conventional screen-film radiography. All images were clinically indicated. Selenium-based digital radiography and conventional screen-film radiography were used in a randomized order. Four radiologists independently evaluated all 50 examinations for the visibility of 76 anatomic details according to a five-level confidence scale (1=not visible, 5=very good visibility). From the evaluation of these anatomic details scores for the upper and middle cervical spine, the cervicothoracic junction and the cervical soft tissues were calculated. The scores for selenium-based digital radiography and conventional screen-film radiography were compared using Wilcoxon's signed rank test. Results: From a total of 15,200 observations (608 per patient) the following scores were calculated for selenium-based digital radiography and for screen-film radiography, respectively: Upper cervical spine 3.88 and 3.94; middle cervical spine 4.60 and 4.48; cervico-thoracic junction 3.64 and 2.62; cervical soft tissue 4.47 and 3.46. The differences between the last two scores were statistically significant (p [de

Advances in pulsed-power-driven radiography system design

International Nuclear Information System (INIS)

Portillo, Salvador; Hinshelwood, David D.; Rovang, Dean Curtis; Cordova, Steve Ray; Oliver, Bryan Velten; Weber, Bruce V.; Welch, Dale Robert; Shelton, Bradley Allen; Sceiford, Matthew E.; Cooperstein, Gerald; Gignac, Raymond Edward; Puetz, Elizabeth A.; Rose, David Vincent; Barker, Dennis L.; Van De Valde, David M.; Droemer, Darryl W.; Wilkins, Frank Lee; Molina, Isidro; Jaramillo, Deanna M.; Swanekamp, Stephen Brian; Commisso, Robert J.; Bailey, Vernon Leslie; Maenchen, John Eric; Johnson, David Lee; Griffin, Fawn A.; Hahn, Kelly Denise; Smith, Ian

2004-01-01

Flash x-ray radiography has undergone a transformation in recent years with the resurgence of interest in compact, high intensity pulsed-power-driven electron beam sources. The radiographic requirements and the choice of a consistent x-ray source determine the accelerator parameters, which can be met by demonstrated Induction Voltage Adder technologies. This paper reviews the state of the art and the recent advances which have improved performance by over an order of magnitude in beam brightness and radiographic utility.

Spatial resolution measurements of the advanced radiographic capability x-ray imaging system at energies relevant to Compton radiography

Energy Technology Data Exchange (ETDEWEB)

Hall, G. N., E-mail: hall98@llnl.gov; Izumi, N.; Landen, O. L.; Tommasini, R.; Holder, J. P.; Hargrove, D.; Bradley, D. K.; Lumbard, A.; Cruz, J. G.; Piston, K.; Bell, P. M.; Carpenter, A. C.; Palmer, N. E.; Felker, B.; Rekow, V.; Allen, F. V. [Lawrence Livermore National Laboratory, 7000 East Avenue, Livermore, California 94550 (United States); Lee, J. J.; Romano, E. [National Security Technologies LLC, 161 S Vasco Rd., Livermore, California 94551 (United States)

2016-11-15

Compton radiography provides a means to measure the integrity, ρR and symmetry of the DT fuel in an inertial confinement fusion implosion near peak compression. Upcoming experiments at the National Ignition Facility will use the ARC (Advanced Radiography Capability) laser to drive backlighter sources for Compton radiography experiments and will use the newly commissioned AXIS (ARC X-ray Imaging System) instrument as the detector. AXIS uses a dual-MCP (micro-channel plate) to provide gating and high DQE at the 40–200 keV x-ray range required for Compton radiography, but introduces many effects that contribute to the spatial resolution. Experiments were performed at energies relevant to Compton radiography to begin characterization of the spatial resolution of the AXIS diagnostic.

Experience in industrial radiography equipment into carry out inspections in Brazil

International Nuclear Information System (INIS)

Lopes, Valdir Maciel; Silva, Joao

2008-01-01

The Nuclear and Energy Research Institute (IPEN), in accordance with the attributions given by the National Commission of Nuclear Energy (CNEN), has been supplying the market with radioactive sealed sources of Iridium 192 ( 192 Ir), for Brazil and some South America Countries, for more than 24 years. In this period, the experience acquired in the accompanied of the technological improvement in the industrial gammagraphy equipment; into Sealed Sources Production Laboratory (LPFS) will be show. Of the set of operations carry out in the LPFS, since the assemblies, tests of qualification of the sources also inspection at of the equipment for posterior applications in field, it is intended to demonstrate to the technological improvement associate to the radiological and operational security. In this work, the data base of the system of the LPFS will be used, as well as the professional experience of the laboratory team in the daily relationship with the companies responsible for the equipment operation. (author)

Perceptions of radiography and the National Health Service: a qualitative study

Energy Technology Data Exchange (ETDEWEB)

Coombs, C.R. E-mail: c.r.coombs@lboro.ac.uk; Park, J.R.; Loan-Clarke, J.; Arnold, J.; Preston, D.; Wilkinson, A.J

2003-05-01

Purpose: To identify the factors that determine the attractiveness of radiography as a career choice and of the National Health Service (NHS) as an employer to potential recruits and returners. Methods: Individual and group interviews were conducted in the East Midlands region to explore participants' perceptions of the attractiveness of the NHS as an employer to potential radiography staff. Interviews were conducted with school pupils, radiography students, mature students, radiography assistants, agency radiographers and independent sector radiographers. Results: Eighty-eight individuals participated in the qualitative stage of the study. Analysis of the interview transcripts indicated that radiography as a career choice is perceived as boring and routine, involving high workloads and little recognition from the general public. Working with patients is the source of considerable job satisfaction but is offset by staff shortages, lack of flexibility over working hours and a lack of consideration of family commitments in the NHS. Financial costs are highlighted as dissuading many participants from considering a career as a radiographer in the NHS or returning to work for the NHS. Greater use of open days in conjunction with more advertising of the profession is suggested as tactics to improve recruitment. Conclusions: The provision of more flexible working hours, greater consideration of family commitments and increased financial support for training are necessary to improve the attractiveness of a radiography career. NHS Human Resource Managers should consider these findings concerning the applicant and returner pools when developing strategies to address the current shortfall of radiographers.

Perceptions of radiography and the National Health Service: a qualitative study

International Nuclear Information System (INIS)

Coombs, C.R.; Park, J.R.; Loan-Clarke, J.; Arnold, J.; Preston, D.; Wilkinson, A.J.

2003-01-01

Purpose: To identify the factors that determine the attractiveness of radiography as a career choice and of the National Health Service (NHS) as an employer to potential recruits and returners. Methods: Individual and group interviews were conducted in the East Midlands region to explore participants' perceptions of the attractiveness of the NHS as an employer to potential radiography staff. Interviews were conducted with school pupils, radiography students, mature students, radiography assistants, agency radiographers and independent sector radiographers. Results: Eighty-eight individuals participated in the qualitative stage of the study. Analysis of the interview transcripts indicated that radiography as a career choice is perceived as boring and routine, involving high workloads and little recognition from the general public. Working with patients is the source of considerable job satisfaction but is offset by staff shortages, lack of flexibility over working hours and a lack of consideration of family commitments in the NHS. Financial costs are highlighted as dissuading many participants from considering a career as a radiographer in the NHS or returning to work for the NHS. Greater use of open days in conjunction with more advertising of the profession is suggested as tactics to improve recruitment. Conclusions: The provision of more flexible working hours, greater consideration of family commitments and increased financial support for training are necessary to improve the attractiveness of a radiography career. NHS Human Resource Managers should consider these findings concerning the applicant and returner pools when developing strategies to address the current shortfall of radiographers

An application of neutron radiography to archaeology

International Nuclear Information System (INIS)

Tugrul, B.

1990-01-01

Neutron radiography is more useful for certain materials than are the other radiographic techniques. Some neutrons are attenuated by light materials such as water, hydrocarbons and boron, but penetrate through heavy materials such as steel, lead and uranium. The object must be irradiated by neutrons for neutron radiography. The neutron irradiation can take place in a reactor or with a neutron source. The transfer technique relies on the build-up of radioactivity in a foil due to neutron absorption. In this way an activation image is formed in the foil. For this technique, dysprosium ( 164 Dy) and indium ( 115 In) foils can be used. After this irradiation, foils are transferred to a film in the dark-room, the latent image being formed in the film by decay radiation from the foil. The neutron radiography technique has been applied to a sword together with its sheath (inventory number 83/173) (Tugrul and Erdal 1987); a piece of cloth was visible on the handle of the sword. Sword and sheath had become corroded together. The artefact is from the Ikiztepe excavation near the city of Samsun in north Anatolia and belongs to the Early Bronze Age. First, X-ray radiography showed that the sword had been destroyed in large part and was not suitable for conservation and restoration procedures. Second, neutron radiography was carried out. Dysprosium-164 was used for the transfer method as a foil screen and irradiated in the reactor at 100 kW for half an hour. The dysprosium foil remained against the radiographic (Structurix, D-7) film for approximately three half-lives after the irradiation. The neutron radiograph shows the cloth layer continuing towards the bottom of the sheath. Through the cloth, water would have been introduced to the inside of the sheath and this was the main cause of corrosion to the artefact and so of the sword's destruction. (author)

Euratom Neutron Radiography Working Group

DEFF Research Database (Denmark)

Domanus, Joseph Czeslaw

1986-01-01

reactor fuel as well as establish standards for radiographic image quality of neutron radiographs. The NRWG meets once a year in each of the neutron radiography centers to review the progress made and draw plans for the future. Besides, ad-hoc sub-groups or. different topics within the field of neutron......In 1979 a Neutron Radiography Working Group (NRWG) was constituted within Buratom with the participation of all centers within the European Community at which neutron facilities were available. The main purpose of NRWG was to standardize methods and procedures used in neutron radiography of nuclear...... radiography are constituted. This paper reviews the activities and achievements of the NRWG and its sub-groups....

Noise analysis of a digital radiography system

International Nuclear Information System (INIS)

Arnold, B.A.; Scheibe, P.O.

1984-01-01

The sources of noise in a digital video subtraction angiography system were identified and analyzed. Signal-to-noise ratios of digital radiography systems were measured using the digital image data recorded in the computer. The major sources of noise include quantum noise, TV camera electronic noise, quantization noise from the analog-to-digital converter, time jitter, structure noise in the image intensifier, and video recorder electronic noise. A new noise source was identified, which results from the interplay of fixed pattern noise and the lack of image registration. This type of noise may result from image-intensifier structure noise in combination with TV camera time jitter or recorder time jitter. A similar noise source is generated from the interplay of patient absorption inhomogeneities and patient motion or image re-registration. Signal-to-noise ratios were measured for a variety of experimental conditions using subtracted digital images. Image-intensifier structure noise was shown to be a dominant noise source in unsubtracted images at medium to high radiation exposure levels. A total-system signal-to-noise ratio (SNR) of 750:1 was measured for an input exposure of 1 mR/frame at the image intensifier input. The effect of scattered radiation on subtracted image SNR was found to be greater than previously reported. The detail SNR was found to vary approximately as one plus the scatter degradation factor. Quantization error noise with 8-bit image processors (signal-to-noise ratio of 890:1) was shown to be of increased importance after recent improvements in TV cameras. The results of the analysis are useful both in the design of future digital radiography systems and the selection of optimum clinical techniques

Fracture healing: direct magnification versus conventional radiography

International Nuclear Information System (INIS)

Link, T.M.; Kessler, T.; Lange, T.; Overbeck, J.; Fiebich, M.; Peters, P.E.

1994-01-01

The aim of the study was to evaluate the potential of magnification radiography in diagnosing fracture healing and assessing its complications. Seventy-three patients with fractures or who had undergone osteotomy were radiographed with both conventional (non-magnified) and magnification (5-fold) techniques. Since 10 patients were radiographed twice and 1 three times, 83 radiographs using each technique were obtained. All radiographs were analysed and the findings correlated with the patients' follow-up studies. The microfocal X-ray unit used for magnification radiography had a focal spot size of 20-130 μm. As an imaging system, digital luminescence radiography was employed with magnification, while normal film-screen systems were used with conventional radiography. Magnification radiography proved superior to conventional radiography in 47% of cases: endosteal and periosteal callus formations were seen earlier and better in 26 cases, and osseous union could be evaluated with greater certainty in 33 cases. In 49% of cases magnification radiography was equal and in 4% inferior to conventional radiography. Additionally an ''inter-observer analysis'' was carried out. Anatomical and pathological structures were classified into one of four grades. Results were significantly (P < 0.01) better using magnification radiography. We conclude that the magnification technique is a good method for monitoring fracture healing in its early stages. (orig.)

Basic studies in X-ray radiography and imaging techniques

International Nuclear Information System (INIS)

Vaidya, Paresh R.

2000-01-01

The aim of this research was to study the basic characteristics related to a new branch of radiography viz. the micro-focal radiography. The most important among them was to find methods of measurement of focal spot size of these X-ray sources. It is important to accomplish this because the design of such units is specifically meant to produce very fine source size. To this end. first the process of radiography test was introduced. Among other things. various properties of an image and image forming systems (like PSF, LSF, MTF etc.) were introduced and explained. Methods used for microfocus measurement of focal spot size in conventional units were reviewed. It was shown how they are not suitable for microfocal tubes. Next the microfocus X-ray unit meant for the study was installed and commissioned. Features which are different from conventional X-ray units were observed more carefully. Data was collected and analyzed for various aspects. Procedure for focussing the electron beam while getting the feed back about beam diameter from the oscilloscope was established by experiments. In addition, influence of change in tube voltage and tube current on the focal spot size was studied. Relationship between tube current and target current vis-a-vis focus size was established. Radiation zone was determined. Focal spot size was qualitatively compared with that of a conventional X-ray unit by taking radiographs of different wire meshes at different magnifications by both the units

First experience with digital radiography

International Nuclear Information System (INIS)

Buchmann, F.

1987-01-01

The digital radiogram is explained, its advantages being the various possibilities of image processing, loss-free transmission, recording and storage capabilities, and in special cases, prompt availability of processed images. Digital subtraction angiography (DSA) and the high-resolution method of digital, luminescent radiography, which replaced the conventional film-foil radiography, are explained as the first developments for the introduction of digital radiography, which today already is an applicable technique. (orig./MG) [de

Problems associated with digital luminescence radiography in the neonate and young infant. Problems with digital radiography.

Science.gov (United States)

Arthur, R J; Pease, J N

1992-01-01

An evaluation of the Siemens Digiscan has been undertaken to determine whether digital luminescence radiography (DLR) could replace conventional radiography in the examination of the neonate and young infant. Whilst the overall image quality of the digital radiograph was consistently higher than for conventional radiography the difference was less marked than we had expected. Furthermore, the potential for reduction in radiation dose by reducing the repeat rate due to incorrect exposure was limited. The potential advantages of DLR have been critically examined in relationship to neonatal radiography and a number of problems encountered during the evaluation have been highlighted.

Studies and applications of neutron radiography with film methods

International Nuclear Information System (INIS)

Ikeda, Yasushi

1989-01-01

Neutron radiography has been studied with film methods and applied to some industrial applications. The film methods include not only conventional silver-halide emulsion films, such as industrial, medical or soft X-ray ones, but also track-etch films and those for indirect methods. The characteristics of the film methods are analyzed and investigated with using various image converters, such as gadolinium metal foil and evaporation films, or some scintillation converters such as NE426. The sensitivities and MTFs for various sets of films and converters have been obtained, which gives a chart of the correlation between the appropriate exposure and resolving powers for them. From the chart, one can select some proper sets for the purpose and given conditions of neutron radiography facilities. The film methods have been applied to inspect very fine cracks in thick steel blocks and plates. It is also applied to observe nuclear fuel pellets or irradiated nuclear fuel pins. Furthermore, the film method has been used for neutron computed tomography. Very fine Eu-particles in TiO pellets, which diameters are nearly 300 micron, can be reconstructed by the neutron CT. The fine neutron CT will be useful for the inspection of Pu-particles in mixed oxide nuclear fuel pellets for future advance nuclear reactors. (author)

X-ray digital industrial radiography (DIR) for local liquid velocity (V{sub LL}) measurement in trickle bed reactors (TBRs): Validation of the technique

Energy Technology Data Exchange (ETDEWEB)

Mohd Salleh, Khairul Anuar, E-mail: kmfgf@mst.edu; Lee, Hyoung Koo [Department of Mining and Nuclear Engineering, Missouri University of Science and Technology, Fulton Hall, 310 W. 14th St., Rolla, Missouri 65409 (United States); Rahman, Mohd Fitri Abdul [Department of Chemical and Biochemical Engineering, Missouri University of Science and Technology, 143 Schrenk Hall, 400 W. 11th St., Rolla, Missouri 65409 (United States); Al Dahhan, Muthanna H. [Department of Mining and Nuclear Engineering, Missouri University of Science and Technology, Fulton Hall, 310 W. 14th St., Rolla, Missouri 65409 (United States); Department of Chemical and Biochemical Engineering, Missouri University of Science and Technology, 143 Schrenk Hall, 400 W. 11th St., Rolla, Missouri 65409 (United States)

2014-06-15

Local liquid velocity measurements in Trickle Bed Reactors (TBRs) are one of the essential components in its hydrodynamic studies. These measurements are used to effectively determine a reactor's operating condition. This study was conducted to validate a newly developed technique that combines Digital Industrial Radiography (DIR) with Particle Tracking Velocimetry (PTV) to measure the Local Liquid Velocity (V{sub LL}) inside TBRs. Three millimeter-sized Expanded Polystyrene (EPS) beads were used as packing material. Three validation procedures were designed to test the newly developed technique. All procedures and statistical approaches provided strong evidence that the technique can be used to measure the V{sub LL} within TBRs.

Radiography in the X-ray region of a laser implosed microball

International Nuclear Information System (INIS)

Launspach, J.; Bayer, C.; Billon, D.; Decroisette, M.; Juraszek, D.; Meynial, D.

1981-05-01

The OCTAL laser of the Limeil CEA Research Center was used to realize the implosion of small targets containing a mixture of DT and to produce thermonuclear fusion reactions. The experimental device in which the experiments were carried out is called Camelia. Its main component is a vacuum chamber upon which the following elements are fixed: - devices for adjusting the focussing lenses; - a device for positioning targets; - extensive diagnostic means enabling the maximum amount of information to be obtained from each shot. These experiments were performed in order to study laser implosion mechanisms and to measure the density and temperature characteristics that can be reached in this way. The X-ray radiography device is relatively simple. It consists of an X-ray source, the target to be analyzed, one or two stenopies and a detector which is either a simple film (Kodak Kodirex) for diagnostics without temporal resolution or a scanning camera with a slit when temporal resolution is required. The device can be used: - without an x-ray source for emission diagnostics with spatio-temporal resolution, - to study the pre-heating of targets by radiography of the dust at the beginning of the implosion, - for diagnostics of the plasma core by radiography of dust after the implosion [fr

Characterization of the rod-pinch diode at 2 to 4 Mv as a high-resolution source for flash radiography

International Nuclear Information System (INIS)

Commisso, R.J.; Allen, R.J.; Cooperstein, G.; Mosher, D.; Young, F.C.; Boller, J.R.; Swanekamp, S.B.; Bayol, F.; Charre, P.; Garrigues, A.; Gonzales, C.; Pompier, F.; Vezinet, R.

2002-01-01

The ASTERIX generator is used to evaluatate the rod-pinch electron-beam diode as an intense source of x-rays for high-resolution, pulsed (30- to 40-ns FWHM) radiography at peak diode voltages of voltages of 2.4 to 4.4 MV and peak diode currents of 55 to 135 kA. At 4 MV, tungsten anode rods of 1-mm or 2-mm diameter produce on-axis doses at 1 meter of 16 rad(Si) or 20 rad(Si), respectively. The on-axis source diameter based on the full-width at half-maximum (FWHM) of the line-spread-function (LSF) is 0.9 ± 0.1 mm for a 1-mm diameter rod and 1.4 ± 0.1 mm for a 2-mm diam rod, independent of voltage. The LANL source diameter is nearly twice the FWHM. The measured rod-pinch current is reproduced with a diode model that includes ions and accounts for anode and cathode plasma expansion. A composite diode with a large diameter carbon-rod anode followed by a smaller-diameter tungsten-tip converter shows promise for applications where a small central source feature is desired

Radioactive wastes storage rock porosity study using neutron radiography

International Nuclear Information System (INIS)

Peterka, F.

1995-01-01

Neutron radiography and neutron transmission analysis application to porosity study was mainly dealing with the building industry, the art protection and the basic research. Cooperation with the building industry has produced the solution of number of problems. Cement hydratation, concrete material, red brick sample, roofing tiles protection and epoxy resin efficiency for sand stones sculpture protection, can be cited as example. Many valuable experiences (like samples thickness, penetrating substances, detection techniques for the different experiments) were achieved. These can be used in the rockies formation studies too. Resolution is the proposal to JAERI and PNC for the cooperation, which can even be on the international basis. (J.P.N.)

Neutron-induced alpha radiography

International Nuclear Information System (INIS)

Pereira, Marco Antonio Stanojev

2008-01-01

A new radiography technique to inspect thin samples was developed. Low energy alpha particles, generated by a boron based screen under thermal neutron irradiation, are used as penetrating radiation. The solid state nuclear track detector CR-39 has been used to register the image. The interaction of the α - particles with the CR-39 gives rise to damages which under an adequate chemical etching became tracks the basic units forming the image. A digital system was developed for data acquisition and data analysis as well as for image processing. The irradiation and etching conditions to obtain the best radiography are 1,3 hours and 25 minutes at 70 deg C respectively. For such conditions samples having 10 μm in thickness can be inspected with a spatial resolution of 32 μm. The use of the digital system has reduced the time spent for data acquisition and data analysis and has improved the radiography image visualization. Furthermore, by using the digital system, it was possible to study several new parameters regarding the tracks which are very important to understand and study the image formation theory in solid state nuclear track detectors, the one used in this thesis. Some radiography images are also shown which demonstrate the potential of the proposed radiography technique. When compared with the other radiography techniques already in use to inspect thin samples, the present one developed in the present paper allows a smaller time to obtain the image, it is not necessary to handle liquid radioactive substances, the detector is insensitive to β, γ, X-ray and visible light. (author)

Radiation Effects in Paediatric radiography

International Nuclear Information System (INIS)

Mutwasi, O.

2006-01-01

Diagnostic imaging has evolved from single technique to a field which we have a choice from many modalities. Some without radiation. Radiation producing modalities include plain films (low dose), Fluoroscopy (mid range dose), Computed tomography (high dose). Radiography dose can significantly be influenced in plain radiography by varying speed of screens, cassette construction and type of radiography. E.g. digital or computed. In computed or digital radiography we are no longer able to tell h igh dose b y the quality of images. The final image is by great extend a product of post processing algorithms. It's for this reasons that the basic understanding of the sensitivity and specifying of various types of examinations and of specifically radiation effects is mandatory for a paediatric imager

Inspection of high density materials by means of X and gamma radiography and X and gamma radioscopy

International Nuclear Information System (INIS)

Deleuze, M.

1985-11-01

We present the tests carried out on uranium for a comparative evaluation of the capabilities and limitations of gamma radiography and X and gamma radioscopy. The following comparison subjects are: the exposure and inspection times of uranium pieces from exposure charts, the radiographic contrast, the sensitivity of defect detection, the choice of radiation source. Theses tests made it possible to determine the limiting thicknesses of uranium able to be inspected by these two techniques. Accordingly, we decided to exchange 192 Ir gamma radiography for a 420 kV X radioscopy and radiography

Developing open-source codes for electromagnetic geophysics using industry support

Science.gov (United States)

Key, K.

2017-12-01

Funding for open-source software development in academia often takes the form of grants and fellowships awarded by government bodies and foundations where there is no conflict-of-interest between the funding entity and the free dissemination of the open-source software products. Conversely, funding for open-source projects in the geophysics industry presents challenges to conventional business models where proprietary licensing offers value that is not present in open-source software. Such proprietary constraints make it easier to convince companies to fund academic software development under exclusive software distribution agreements. A major challenge for obtaining commercial funding for open-source projects is to offer a value proposition that overcomes the criticism that such funding is a give-away to the competition. This work draws upon a decade of experience developing open-source electromagnetic geophysics software for the oil, gas and minerals exploration industry, and examines various approaches that have been effective for sustaining industry sponsorship.

Neutron radiography of Apollo ordnance

International Nuclear Information System (INIS)

Golliher, K.G.

1983-01-01

Neutron radiography played an important role in the successful Apollo missions. Neutron radiography was used, for the first time, on a production basis to examine the internal details of ordnance devices employed in the Apollo Program. Ordnance devices ranged from charges which separated the massive booster stages to those which triggered the release of re-entry parachutes. Discussed are the early developments in neutron radiography and the conversion of this infant nondestructive technology into production capabilities. (Auth.)

Radiographic evaluation of corrosion/erosion failures in pressure vessels and pipings in fertilizer industry

International Nuclear Information System (INIS)

Sinha, G.S.; Sahay, K.N.; Sundaram, K.V.; Banerji, K.C.

1977-01-01

The uses of radiography in combating the corrosion/erosion failures of pressure equipments used in the fertilizer industry are highlighted. Premature failures in fertilizer plants have proved to be very costly. One of the principal agencies responsible for such failures in process industry is corrosion/erosion. Radiography, when supplemented with other NDT-techniques, has been found to be ideal and highly useful method for on-stream inspection and evaluation of corrosion/erosion failures of pressure vessels and pipings. Three case-histories have been presented to illustrate the importance of radiography. (author)

Neutron radiography at the Institut de Maintenance Aeronautique

International Nuclear Information System (INIS)

Cluzeau, S.

1999-01-01

Recently the French Institut de Maintenance Aeronautique (IMA) decided to open a new field of research specially devoted to the inspection methods that should be used by the aircraft overhauling industry. Taking into account its proved ability for an early corrosion detection, neutron radiography (NR) was selected as an inspection method to be appraised. This paper presents the approach that IMA intends to follow for achieving this objective and involving selection of equipment, design of the facility and research program.(author)

Proton radiography using highpower femtosecond laser

International Nuclear Information System (INIS)

Choi, Chang Il