Comparative Study on Radiological Impact Due To Direct Exposure to a Radiological Dispersal Device Using A Sealed Radiation Source

International Nuclear Information System (INIS)

Margeanu, C.A.

2011-01-01

Nowadays, one of the most serious terrorist threats implies radiological dispersal devices (RDDs), the so-called dirty bombs, that combine a conventional explosive surrounded by an inflammatory material (like thermit) with radioactive material. The paper objective is to evaluate the radiological impact due to direct exposure to a RDD using a sealed radiation source (used for medical and industrial applications) as radioactive material. The simulations were performed for 60Co, 137Cs and 192Ir radiation sources. In order to model the contamination potential level and radiation exposure due to radioactive material spreading from RDD, Lawrence Livermore National Laboratory's HOTSPOT 2.07 computer code was used. The worst case scenario has been considered, calculations being performed for two radioactive material dispersion models, namely General radioactive Plume and General Explosion. Following parameters evolution with distance from the radiation source was investigated: total effective dose equivalent, time-integrated air concentration, ground surface deposition and ground shine dose rates. Comparisons between considered radiation sources and radioactive material dispersion models have been performed. The most drastic effects on population and the environment characterize 60Co sealed radiation source use in RDD.

Sealed radioactive source management

International Nuclear Information System (INIS)

2005-01-01

Sealed radioactive sources have been used in a wide range of application in medicine, agriculture, geology, industry and other fields. Since its utilization many sources have become out of use and became waste but no proper management. This has lead to many accidents causing deaths and serious radiation injuries worldwide. Spent sources application is expanding but their management has seen little improvements. Sealed radioactive sources have become a security risk calling for prompt action. Source management helps to maintain sources in a good physical status and provide means of source tracking and control. It also provides a well documented process of the sources making any future management options safe, secure and cost effective. Last but not least good source management substantially reduces the risk of accidents and eliminates the risk of malicious use. The International Atomic Energy Agency assists Member States to build the infrastructure to properly manage sealed radioactive sources. The assistance includes training of national experts to handle, condition and properly store the sources. For Member States that do not have proper facilities, we provide the technical assistance to design a proper facility to properly manage the radioactive sources and provide for their proper storage. For Member States that need to condition their sources properly but don't have the required infrastructure we provide direct assistance to physically help them with source recovery and provide an international expert team to properly condition their sources and render them safe and secure. We offer software (Radioactive Waste Management Registry) to properly keep a complete record on the sources and provide for efficient tracking. This also helps with proper planning and decision making for long term management

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

Safety considerations of disposal of disused sealed sources in near surface facilities

International Nuclear Information System (INIS)

Pla, E.

2003-01-01

The report presents European commission studies on sealed radioactive sources - Management of Spent Radiation Sources in the European Union: Quantities, Storage, Recycling and Disposal. EUR 16960 EN. EC 1996; Management of sealed radioactive sources produced and sold in the Russian Federation. EUR 18191 EN. EC, 1999; Management and Disposal of Disused Sealed Radioactive Sources in the European Union. EUR 18186 EN. EC, 2000; Management of Spent Sealed Radioactive Sources in Central and Eastern Europe. EUR 19842 EN. EC, April 2001; Management of Spent Sealed Radioactive Sources in Bulgaria, Latvia, Lithuania, Romania and Slovakia. EUR 20654 EN. EC, January 2003. The conclusions and recommendations in them are given. The International catalogue of sealed radioactive sources and devices is described

Management of spent sealed radioactive sources

International Nuclear Information System (INIS)

Vicente, Roberto; Sordei, Gian-Maria; Hiromoto, Goro

2002-01-01

The number of sealed radiation sources used in industrial, medical, and research applications in Brazil amounts to hundreds of thousands. Spent or disused sources are being collected and stored as radioactive waste in nuclear research centers, awaiting for a decision on their final disposal. However, a safe and economically feasible disposal technology is unavailable. The aim of this paper is to report the development of the concept of a repository and a treatment process that will allow the final disposal of all the spent sealed sources in a safe, dedicated, and exclusive repository. The concept of the disposal system is a deep borehole in stable geologic media, meeting the radiological performance standards and safety requirements set by international organizations. (author)

Radiation protection problems with sealed Pu radiation sources

International Nuclear Information System (INIS)

Naumann, M.; Wels, C.

1982-01-01

A brief outline of the production methods and most important properties of Pu-238 and Pu-239 is given, followed by an overview of possibilities for utilizing the different types of radiation emitted, a description of problems involved in the safe handling of Pu radiation sources, and an assessment of the design principles for Pu-containing alpha, photon, neutron and energy sources from the radiation protection point of view. (author)

THE PROBLEMS OF USING EXEMPTION ACTIVITY VALUES FOR REGULATING THE MANAGEMENT OF SEALED RADIONUCLIDE SOURCES OF GAMMA-RADIATION

Directory of Open Access Journals (Sweden)

A. N. Barkovsky

2017-01-01

Full Text Available The article focuses on the procedure for exemption of the sealed and unsealed radionuclide sources of gamma radiation from regulatory control. The contradictory nature of the existing set of exemption criteria has been noted, leading, in some cases, to paradoxical situations. It is shown that the exempt activity values determined in NRB-99/2009 and in the international basic safety standards of the IAEA are significantly overestimated (in comparison with the activity values of a point source creating the ambient dose equivalent rate of 1 μSv / h at a distance of 0.1 m for a number of the most widely used gamma-emitting radionuclides, including 22Na, 54Mn, 75Se, 152Eu and 154Eu. It is proposed to revise the current values of exempt activity, bringing them in line with the dose rate criterion for the exempt of sealed radionuclide sources of gamma radiation, and to present them with one significant digit. The corrected values of exempt activity for  seven selected radionuclides are proposed for further use in the process of revision of the national radiation safety standards.

Radioactive sealed sources production process for industrial radiography

International Nuclear Information System (INIS)

Santos, Paulo de S.; Ngunga, Daniel M.G.; Camara, Julio R.; Vasquez, Pablo A.S.

2017-01-01

providing products and services to the private and governmental Brazilian users of industrial radiography and nucleonic control systems. Radioactive sealed sources are commonly used in nondestructive tests as radiography to make inspections and verify the internal structure and integrity of materials and in nucleonic gauges to control level, density, viscosity, etc. in on-line industrial processes. One of the most important activities carried out by this laboratory is related to the inspection of source projectors devices used in industrial radiography and its constituent parts as well as remote handle control assembly drive cable and guide tube systems. The laboratory also provide for the users iridium-192, cobalt-60 and selenium-75 sealed sources and performs quality control tests replacing spent or contaminated radiative sources. All discard of radioactive source is treated as radioactive waste. Additionally, administrative and commercial processes and protocols for exportation and transport of radioactive material are developed by specialized departments. In this work are presented the mean processes and procedures used by the Sealed Source Production Laboratory such as the arrival of the radioactive material to the laboratory and the source projectors, mechanical inspections, source loading, source leaking tests, etc. (author)

Radioactive sealed sources production process for industrial radiography

Energy Technology Data Exchange (ETDEWEB)

Santos, Paulo de S.; Ngunga, Daniel M.G.; Camara, Julio R.; Vasquez, Pablo A.S., E-mail: psantos@ipen.br, E-mail: hobeddaniel@gmail.com, E-mail: jrcamara@ipen.br, E-mail: pavsalva@ipen.br [Instituto de Pesquisas Energética s e Nucleares (IPEN/CNEN-SP), São Paulo, SP (Brazil)

2017-07-01

providing products and services to the private and governmental Brazilian users of industrial radiography and nucleonic control systems. Radioactive sealed sources are commonly used in nondestructive tests as radiography to make inspections and verify the internal structure and integrity of materials and in nucleonic gauges to control level, density, viscosity, etc. in on-line industrial processes. One of the most important activities carried out by this laboratory is related to the inspection of source projectors devices used in industrial radiography and its constituent parts as well as remote handle control assembly drive cable and guide tube systems. The laboratory also provide for the users iridium-192, cobalt-60 and selenium-75 sealed sources and performs quality control tests replacing spent or contaminated radiative sources. All discard of radioactive source is treated as radioactive waste. Additionally, administrative and commercial processes and protocols for exportation and transport of radioactive material are developed by specialized departments. In this work are presented the mean processes and procedures used by the Sealed Source Production Laboratory such as the arrival of the radioactive material to the laboratory and the source projectors, mechanical inspections, source loading, source leaking tests, etc. (author)

Safe management of spent radiation source

International Nuclear Information System (INIS)

Kosako, Toshiso; Sugiura, Nobuyuki; Valdezco, E.M.; Choi, Kwang-Sub

2003-01-01

Presented are 8 investigation reports concerning the safe management of spent radiation source (SRS) during the current 2 years. Four reports from Japan are: Scheme for SRS management (approach and present status of the SRS management and consideration toward solving problems); Current International Atomic Energy Agency (IAEA) activities related to safety of radiation sources (Chronology of action plan development, Outline of revised action plan, and Asian regional activities); Current status of SRS management in Japan (Regulation system, Obligations of licensed users, Regulatory system on sealed sources, Status in the incidents on sources occurred, Incident of source loss, and Incidents of orphan sources); and SRS management system in Japan (Current status of using of sealed sources, collection system of SRS-Japan Radioisotope Association (JRIA) services, and Disposal of SRS). Four reports from the Asian countries also concern the current statuses of SRS management in the Philippine (Radioactive waste sources, Waste management strategies, Conditioning of Ra sources, Ra project action plan, as low as reasonably achievable (ALARA) program, Dose assessment, Regulations on radioactive waste, Action plan on the safety and security of sources, IAEA Regional Demonstration Centers, and sitting studies for a near surface disposal facility); Thailand (Current status of using sealed sources, Inventory of SRS, and Current topics of SRS management); Indonesia (Principles of management of radiation sources, Legislative framework of SRS management practices, Regulatory on SRS, management of sealed SRS, management hurdles, and reported incidents); and Korea (Regulatory frame work, Collection systems of SRS, Radioisotope waste generation, Radiation exposure incident, and Scrap monitoring system). (N.I.)

Collaboration and Commitment to Sealed Source Safety, Security, and Disposition - 13627

International Nuclear Information System (INIS)

Jennison, Meaghan; Martin, David W.

2013-01-01

EnergySolutions, the Division of Radiation Control at the Utah Department of Environmental Quality (UDEQ), the Conference of Radiation Control Program Directors (CRCPD), and the Department of Energy's Global Threat Reduction Initiative (GTRI) are collaborating on a truly innovative effort to expand opportunities for cost-effective sealed source disposal. These entities have developed a first-of-its-kind initiative to dispose of certain sealed sources at the EnergySolutions disposal facility near Clive, Utah, which normally cannot accept sealed sources of any type. This creative and collaborative effort to improve radiation health, safety, and security exemplifies the spirit and commitment represented by the Richard S. Hodes, M.D. Honor Lecture Award, which is presented annually at the Waste Management Symposia by the Southeast Compact Commission to encourage environmental professionals and political leaders to develop innovative approaches to waste management in the United States. The participants in the collaborative initiative are honored to receive special recognition for their efforts thus far. They also recognize that the hard work remains to be done. (authors)

Development of radioactive sealed sources in epoxy matrix

International Nuclear Information System (INIS)

Benega, Marcos A.G.; Nagatomi, Helio R.; Rostelato, Maria Elisa C.M.; Karan Junior, Dib; Souza, Carla D.; Tiezzi, Rodrigo; Rodrigues, Bruna T.; Peleias Junior, Fernando S.

2013-01-01

The aim of the present work is to study and develop commercial resins for manufacturing solid sealed sources. The sources are produced with radionuclides of barium-133, cesium-137 and cobalt-57. They are used in radiation detectors verification. For the immobilization of the radionuclides in the epoxy matrix, it is made use of emulsifying agents that ensure the miscibility between resin and aqueous radioactive solution, as well as curing agents for controlling, curing and sealing the standard radioactive solution completely. As a result, it is expected to obtain standard sealed sources and equivalent to water. The equivalence to water is an important and necessary characteristic. The radioisotopes used in nuclear medicine are supplied in an aqueous form and the resin applied must have a very similar density comparing to the water. The sources must also be comparable in quality to sources produced internationally, but with low cost and wide available materials in the market. It is intended to create a national technology able to meet the demand of this product in the domestic market and achieve excellence in quality through accreditation and certification of the product by the appropriate agencies. The study of the necessary parameters used in the production of these sources, will bring technology for the manufacture of other categories of standard sealed sources, those used for nuclear medicine, image, laboratories and industry. (author)

INEL storage facility for sealed sources from the commercial sector

International Nuclear Information System (INIS)

Kingsford, C.O.; Satterthwaite, B.C.

1994-08-01

Commercially owned sealed radiation sources determine by the US Nuclear Regulatory Commission to be a public health or safety hazard are accepted by the US Department of Energy, under the Atomic Energy Act of 1954, as material for reuse of recycle. To implement this policy, the sealed sources must be stored until proper disposition is determined. This report documents the investigation and selection process undertaken to locate a suitable storage facility at the Idaho National Engineering Laboratory

Characterization and packaging of disused sealed radioactive sources

International Nuclear Information System (INIS)

Aguilar, S.L.

2013-01-01

In Bolivia are generated disused sealed sources and radioactive waste resulting from the use of radioactive materials in industrial, research and medicine. The last includes the diagnosis and treatment. Whereas exposure to ionizing radiation is a potential hazard to personnel who applies it, to those who benefit from its use or for the community at large, it is necessary to control the activities in this field. The Instituto Boliviano de Ciencia y Tecnologia Nuclear - IBTEN is working on a regional project from International Atomic Energy Agency - IAEA, RLA/09/062 Project - TSA 4, Strengthening the National Infrastructure and Regulatory Framework for the Safe Management of Radioactive waste in Latin America. This Project has strengthened the regulatory framework regarding the safe management of radioactive waste. The aim of this work was focused primarily on the security aspects in the safe management of disused sealed sources. The tasks are listed below: 1. Characterization of disused sealed sources 2. Preparation for transport to temporary storage 3. Control of all disused radioactive sources. (author)

Sure confinement of spent sealed sources

International Nuclear Information System (INIS)

Lizcano, D.

2013-10-01

The industrial and technological development of the last decades produced and increment in the radiations application in different human activities. One of the main effects has been the production of radioactive wastes of all the levels. In Mexico, several stages of the waste management of low and intermediate level have not been completely resolved, as the case of the treatment and the final storage. In this work the confinement of spent sealed sources is described, maintaining as main objective the security of these sources and the protection to the workers and the people. (author)

Standard operational radiation protection instructions for process instrumentation and control engineering applying radiometric equipment containing sealed sources

International Nuclear Information System (INIS)

1989-01-01

According to article 16(3) of the Ordinance on the Implementation of Atomic Safety and Radiation Protection of 11 October 1984, operational radiation protection instructions have to be worked out for each type of nuclear energy application. Based on the valid legal provisions of the GDR and on experience and knowledge gained in practice, the most important operational instructions and procedures for the operation of radiometric equipment containing sealed sources were compiled. The example should enable the management to make the instructions directly applicable and, if necessary, to modify or supplement them

Procedure to carry out leakage test in beta radiation sealed sources emitters of 90Sr/90Y

International Nuclear Information System (INIS)

Alvarez R, J. T.

2010-09-01

In the alpha-beta room of the Secondary Laboratory of Dosimetric Calibration of the Metrology Department of Ionizing Radiations ophthalmic applicators are calibrated in absorbed dose terms in water D w ; these applicators, basically are emitter sealed sources of pure beta radiation of 90 Sr / 90 Y. Concretely, the laboratory quality system indicates to use the established procedure for the calibration of these sources, which establishes the requirement of to carry out a leakage test, before to calibrate the source. However, in the Laboratory leakage test certificates sent by specialized companies in radiological protection services have been received, in which are used gamma spectrometry equipment s for beta radiation leakage tests, since it is not reliable to detect pure beta radiation with a scintillating detector with NaI crystal, (because it could detect the braking radiation produced in the detector). Therefore the Laboratory has had to verify the results of the tests with a correct technique, with the purpose of determining the presence of sources with their altered integrity and radioactive material leakage. The objective of this work is to describe a technique for beta activity measurement - of the standard ISO 7503, part 1 (1988) - and its application with a detector Gm plane (type pankage) in the realization of leakage tests in emitter sources of pure beta radiation, inside the mark of quality assurance indicated by the report ICRU 76. (Author)

Radioactive waste management in sealed sources laboratory production

International Nuclear Information System (INIS)

Carvalho, Gilberto

2001-01-01

The laboratory of sealed sources production, of Instituto de Pesquisas Energeticas e Nucleares, was created in 1983 and since then, has produced radioactive sources for industry and engineering in general, having specialization in assembly of radiation sources for non destructive testings, by gammagraphy, with Iridium-192, that represents 98% of the production of laboratory and 2% with the Cobalt-60, used in nuclear gages. The aim of this work, is to quantify and qualify the radioactive wastes generated annually, taking into account, the average of radioactive sources produced, that are approximately 220 sources per year

Radiation protection rules for handling of sealed radioactive sources in medicine

International Nuclear Information System (INIS)

1985-02-01

The rules presented here relate to the use of sealed radioactive sources in medical therapy, with the radioactive sources being temporarily or permanently incorporated into body cavities or body tissues, or fixed to the body surface. They also relate to radioactive sources with dimensions below 5 mm (as e.g. seeds). (orig./HP) [de

Sealed Radioactive Sources. Information, Resources, and Advice for Key Groups about Preventing the Loss of Control over Sealed Radioactive Sources

International Nuclear Information System (INIS)

2013-10-01

Among its many activities to improve the safety and security of sealed sources, the IAEA has been investigating the root causes of major accidents and incidents since the 1980's and publishes findings so that others can learn from them. There are growing concerns today about the possibility that an improperly stored source could be stolen and used for malicious purposes. To improve both safety and security, information needs to be in the hands of those whose actions and decisions can prevent a source from being lost or stolen in the first place. The IAEA developed this booklet to help improve communication with key groups about hazards that may result from the loss of control over sealed radioactive sources and measures that should be implemented to prevent such loss of control. Many people may benefit from the information contained in this booklet, particularly those working with sources and those likely to be involved if control over a source is lost; especially: officials in government agencies, first responders, medical users, industrial users and the metal recycling industry. The general public may also benefit from an understanding of the fundamentals of radiation safety. This booklet is comprised of several stand-alone chapters intended to communicate with these key groups. Various accidents that are described and information that is provided are relevant to more than one key group and therefore, some information is repeated throughout the booklet. This booklet seeks to raise awareness of the importance of the safety and security of sealed radioactive sources. However, it is not intended to be a comprehensive 'how to' guide for implementing safety and security measures for sealed radioactive sources. For more information on these measures, readers are encouraged to consult the key IAEA safety and security-related publications identified in this booklet

Keeping Sealed Radioactive Sources Safe and Secure

International Nuclear Information System (INIS)

Potterton, Louise

2013-01-01

Radioactive sources are used in a wide variety of devices in medical, industrial, agricultural and research facilities worldwide. These sources, such as cobalt-60 and caesium-137, emit high levels of ionizing radiation, which can treat cancer, measure materials used in industry and sterilize food and medical appliances. Problems may arise when these sources are no longer needed, or if they are damaged or decayed. If these sources are not properly stored they can be a threat to human health and the environment and pose a security risk. Procedures to secure these spent or 'disused' sources are often highly expensive and need specialized assistance. The IAEA helps its States find long term solutions for the safe and secure storage of disused sealed radioactive sources (DSRSs)

Code of practice for the use of sealed radioactive sources in borehole logging (1998)

International Nuclear Information System (INIS)

1989-12-01

The purpose of this code is to establish working practices, procedures and protective measures which will aid in keeping doses, arising from the use of borehole logging equipment containing sealed radioactive sources, to as low as reasonably achievable and to ensure that the dose-equivalent limits specified in the National Health and Medical Research Council s radiation protection standards, are not exceeded. This code applies to all situations and practices where a sealed radioactive source or sources are used through wireline logging for investigating the physical properties of the geological sequence, or any fluids contained in the geological sequence, or the properties of the borehole itself, whether casing, mudcake or borehole fluids. The radiation protection standards specify dose-equivalent limits for two categories: radiation workers and members of the public. 3 refs., tabs., ills

Repatriation of disused sealed sources in Peru

International Nuclear Information System (INIS)

Mallaupoma, Mario; Abeyta, Cristy; Matzke, Jim

2013-01-01

Sealed radioactive sources are used around the world in medicine, industry and research within a wide range of applications. Sources may contain a large spectrum of radionuclides, which can have different levels of activity as well as different periods of half-life. At the end of their useful life, they are considered as worn-out or obsolete. However, the residual levels of radioactivity, which have those sources, can be high, representing a high radiation risk. This publication describes the technical actions carried out by the specialized group of the Peruvian Institute of Nuclear energy (IPEN) and Los Alamos National Laboratory which supports the program of 'Global Threat Reduction Initiative's' (GTRI) within the implementation of 'Offsite Source Recovery Program' (OSRP)

Radiation protection: data sheets for use of 11C, 18F, 22Na, 24Na, 33P, 35S, 36Cl, 45Ca in non sealed sources

International Nuclear Information System (INIS)

Anon.

1994-01-01

These data sheets give the essential datas for the use of non sealed radioactive sources They are made for users in view of their radiation protection and give the administrative procedures, the radiation protection procedures and equipments to be used in function of the activity

Methods to identify and locate spent radiation sources

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-07-01

The objective of this manual is to provide essential guidance to Member States with nuclear applications involving the use of a wide range of sealed radiation sources on the practical task of physically locating spent radiation sources not properly accounted for. Advice is also provided to render the located source safe on location. Refs, figs and tabs.

Methods to identify and locate spent radiation sources

International Nuclear Information System (INIS)

1997-06-01

The objective of this manual is to provide essential guidance to Member States with nuclear applications involving the use of a wide range of sealed radiation sources on the practical task of physically locating spent radiation sources not properly accounted for. Advice is also provided to render the located source safe on location. Refs, figs, tabs

Methods to identify and locate spent radiation sources

International Nuclear Information System (INIS)

1995-07-01

The objective of this manual is to provide essential guidance to Member States with nuclear applications involving the use of a wide range of sealed radiation sources on the practical task of physically locating spent radiation sources not properly accounted for. Advice is also provided to render the located source safe on location. Refs, figs and tabs

S.I. No 17 of 1972, Factories Ionising Radiations (Sealed Sources) Regulations, 1972

International Nuclear Information System (INIS)

1972-03-01

The purpose of the Regulations in general is to prescribe measures which must be taken to ensure the adequate protection of persons employed in factories and other places to which the Factories Act 1955 applies, against ionizing radiations arising from radioactive substances sealed in a container and from any machine or apparatus including irradiating apparatus that is intended to produce ionizing radiations in which charged particles are accelerated by a voltage of not less than 5 kilovolts. The Schedule lays down the maximum permissible doses of radiation for the different categories of workers. The Regulations entered into force on 1 March 1972 [fr

Nature and magnitude of the problem of spent radiation sources

International Nuclear Information System (INIS)

1991-09-01

Various types of sealed radiation sources are widely used in industry, medicine and research. Virtually all countries have some sealed sources. The activity in the sources varies from kilobecquerels in consumer products to hundreds of pentabecquerels in facilities for food irradiation. Loss or misuse of sealed sources can give rise to accidents resulting in radiation exposure of workers and members of the general public, and can also give rise to extensive contamination of land, equipment and buildings. In extreme cases the exposure can be lethal. Problems of safety relating to spent radiation sources have been under consideration within the Agency for some years. The first objective of the project has been to prepare a comprehensive report reviewing the nature and background of the problem, also giving an overview of existing practices for the management of spent radiation sources. This report is the fulfilment of this first objective. The safe management of spent radiation sources cannot be studied in isolation from their normal use, so it has been necessary to include some details which are relevant to the use of radiation sources in general, although that area is outside the scope of this report. The report is limited to radiation sources made up of radioactive material. The Agency is implementing a comprehensive action plan for assistance to Member States, especially the developing countries, in all aspects of the safe management of spent radiation sources. The Agency is further seeking to establish regional or global solutions to the problems of long-term storage of spent radiation sources, as well as finding routes for the disposal of sources when it is not feasible to set up safe national solutions. The cost of remedial actions after an accident with radiation sources can be very high indeed: millions of dollars. If the Agency can help to prevent even one such single accident, the cost of its whole programme in this field would be more than covered. Refs

Integrated Management Program for Radioactive Sealed Sources in Egypt IMPRSS

International Nuclear Information System (INIS)

Hasan, A.; El-Adham, K.

2004-01-01

Sealed sources are usually in capsules made of stainless steel. They are the size of a pen or a finger and contain one of hundreds of radioactive elements (e.g., Iridium, Radium) or their isotopes. They are air-tight and very durable, contain the radioactive material but not radiation. They are used in the health sector, industry, military, and universities. Incidents occurred in Met Halfa, Egypt, 2000 (Iridium-192); Goiania, Brazil, 1987 (Cesium-137); Mexico and Southwest U.S., 1977 -1984 (Cobalt-60); Peru, 1999 (Iridium-1992); Poland 2001 (Cobalt-60). The IMPRSS Mission is based on a joined partnership between the Egyptian Atomic Energy Authority, the Egyptian Ministry of Health, the Sandia National Laboratories, the International Atomic Energy Agency and others. The IMPRSS Mission protects human health and the environment in Egypt from mismanaged sealed sources, is developed jointly with MOH and EAEA, provides capabilities for managing radioactive sealed sources in Egypt, increases public awareness, provides education and training, improves emergency response capabilities, develops a permanent disposal facility, ensures the program is self-sustaining and ensures close coordination with the IAEA. Infrastructure how to manage sealed sources is discussed. It includes awareness, tracking and inventory control, security, recovery, conditioning and storage, recycling and disposal. Emergency response, regulatory reform, education and training and its targets are provided. The government of Egypt can protect the people of Egypt and is ready for emergencies. Prevention is the first line of defence and detection is the second line of defence. Adequate Emergency Response saves lives and adequate control reduces risk of mismanaged uses or deliberate misuses of sources. A Cradle-to-Grave approach is built on existing capabilities at EAEA and MOH

Prototypes of phosphorus-32 sealed sources for use in Brachytherapy

International Nuclear Information System (INIS)

Anaya Garro, Olgger; Vela Mora, Mariano; Revilla Silva, Angel Revilla

2005-01-01

It has developed prototypes of phosphorus-32 sealed sources for use in Brachytherapy. This one was made in two stages, at the first one, we designed and constructed the container (capsule), the filling system and the sealed system; at the second one, we made the irradiation of the capsules containing the 'target'. The prototypes was made of aluminum in cylindrical geometry. During the irradiation test was made using two different dimensions: one of 1 mm outer diameter and 1 cm length and another one of 0.8 mm outer diameter and 5 mm length. They were radiated in the core of the RP-10 research reactor, at 7.93 x10 13 n/cm 2 .s thermal neutron flux during 27 operation cycles. Activities of 144.53 MBq (3.91 mCi) and 107.67 MBq (2.91 mCi) was obtained for each case. This activities are adequate to restenosis and for some tumors treatment. We can observed that the capsules irradiated passed visual inspection in its physical integrity (leakage and geometry). It has been demonstrated, that the beta radiation for his minor power of penetration and its high interaction, causes major local damage to the malignant tissue, minimizing the damage of the healthy surrounding tissues. It has been advisable to use for the treatment of illnesses of the circulatory system and some tumors. At the present, the source of strontium-90 are the most beta ray source used, but of this one are obtained as fission product of uranium target, where valuable radioactive waste is generated, whereas if we were using phosphorus-32 that we propose, radioactive waste would not be generated since it would take place directly as sealed source, for reaction (n, β). (author)

Radioactive sealed sources inventory and management

International Nuclear Information System (INIS)

Rodriguez C, G.; Mallaupoma G, M.; Cruz C, W.

1996-01-01

This report is related to the management of radioactive wastes, that is to say, related to the sealed sources utilized in industry, medicine and research jobs, that can not be used anymore, because of their life time termination or their activity decay to useless limits. Owing to this fact, it is necessary to take them to the Management Plant of Radioactive waste in the 'RACSO' Nuclear Center, as it is specified by the National Authority Technical Office (OTAN) regulations in Peru. The experience gained by IPEN in the sealed source management is shown in the table which informs about the radionuclide types, activity and volume amount for years. In the 'RACSO' Nuclear Center, 63 sealed sources are stored and right measures are being adopted in order to be conditioned by cementation in 200 lt steel reinforced cylinders, which are proper to their transportation and storage. A flow-chart shows the steps that the national users should follow in order to manage radioactive sealed sources and so that minimize the risks. Resulting from the agreement between the users and managers, a systematic coordination is developed, verifying the information related to the source characterization, the way of transportation and the future conditioning. It also involves the cost aspects, which in some cases, represent a big problem in the management. (authors). 3 refs., 3 figs., 1 tab

Management of Disused Sealed Sources in Hungary - 13077

International Nuclear Information System (INIS)

Kapitany, Sandor

2013-01-01

Since 1976 the spent and disused radioactive sources arisen in Hungary are stored in a central storage facility called Radioactive Waste Treatment and Disposal Facility operated by Public Limited Company for Radioactive Waste Management. The Facility is responsible for the record keeping, the waste acceptance procedure, the shipment and the storage or disposal (whether a certain source meets the waste acceptance criteria for disposal or not) of sources. Based on the more than 35 year old operation of the facility many experiences have been gathered regarding the technology for long-term storage of sources, the attitude of the users of sources, the evolution of the legislation and the national record keeping system. Recently a new legislation for the security of radioactive materials (including sources) was introduced, first in Central-Europe. It requires special security arrangements from the facility for transport and for storage. Due to the ongoing retrieval of radioactive waste formerly disposed of, partly containing sealed sources, there is a new challenge in the physical inventory control of historical waste. The paper would show the effect of the changes in the legislation system of record keeping or security on the users' attitude for discard of sources and on the management of the sources in the facility. The facility has a unique storage technology (shallow boreholes) in the narrow region. The sealed sources are placed into vertical pipes sunk into the surface. In the beginning, each of the sources were dropped into the pipe directly, recently they are placed in a metal tube first ensuring the retrieval. The lessons learned will be presented. There were several issues to introduce the new security arrangements (partly financially supported by US DOE) for storage and for transportation of sealed sources. These issues are addressed. In the past part of the sealed sources were disposed together with solid radioactive waste packaged in plastic bags. A waste

Management of Disused Sealed Sources in Hungary - 13077

Energy Technology Data Exchange (ETDEWEB)

Kapitany, Sandor [PURAM, Puskas Tivadar street 11, Budaors, Pest 2040 (Hungary)

2013-07-01

Since 1976 the spent and disused radioactive sources arisen in Hungary are stored in a central storage facility called Radioactive Waste Treatment and Disposal Facility operated by Public Limited Company for Radioactive Waste Management. The Facility is responsible for the record keeping, the waste acceptance procedure, the shipment and the storage or disposal (whether a certain source meets the waste acceptance criteria for disposal or not) of sources. Based on the more than 35 year old operation of the facility many experiences have been gathered regarding the technology for long-term storage of sources, the attitude of the users of sources, the evolution of the legislation and the national record keeping system. Recently a new legislation for the security of radioactive materials (including sources) was introduced, first in Central-Europe. It requires special security arrangements from the facility for transport and for storage. Due to the ongoing retrieval of radioactive waste formerly disposed of, partly containing sealed sources, there is a new challenge in the physical inventory control of historical waste. The paper would show the effect of the changes in the legislation system of record keeping or security on the users' attitude for discard of sources and on the management of the sources in the facility. The facility has a unique storage technology (shallow boreholes) in the narrow region. The sealed sources are placed into vertical pipes sunk into the surface. In the beginning, each of the sources were dropped into the pipe directly, recently they are placed in a metal tube first ensuring the retrieval. The lessons learned will be presented. There were several issues to introduce the new security arrangements (partly financially supported by US DOE) for storage and for transportation of sealed sources. These issues are addressed. In the past part of the sealed sources were disposed together with solid radioactive waste packaged in plastic bags. A

Regulatory control of radiation sources in Slovakia

International Nuclear Information System (INIS)

Auxtova, L.

2001-01-01

In Slovakia, there are two regulatory authorities. Regulatory control of the utilization of nuclear energy, based on the Slovak National Council's law No. 130/1998 on the peaceful uses of nuclear energy, is exercised by the Nuclear Regulatory Authority of the Slovak Republic. The second regulatory authority - the Ministry of Health - is empowered by law No. 72/1994 on the protection of human health to license radiation sources and is responsible for radiation protection supervision (there are nearly 3000 establishments with sealed sources, radiation generators and unsealed sources in Slovakia). Pursuant to a new radiation protection regulation based on international standards, radiation sources are to be categorized in six classes according to the associated exposure and contamination hazards. A national strategy for improving the safety of radiation sources over their life-cycle and for the management of disused and orphan sources is being prepared for governmental approval. (author)

Management of spent and disused sealed radiation sources in Russian Federation

International Nuclear Information System (INIS)

Sobolev, I.A.; Ojovan, M.I.; Karlina, O.K.; Arustamov, A.E.

2001-01-01

Full text: The system of management of spent and disused sealed radiation sources (SDSRS) in Russian Federation is based on centralised approach. This system involves 16 regional facilities of the system 'Radon' which provide safe management of SDSRS. The scientific and methodical guidance on activities of regional facilities 'Radon' carries out the Scientific and Industrial Association 'Radon', Moscow. Recently the Moscow SIA 'Radon' examined activities at regional facilities 'Radon' accordingly with the program approved by the State Supervision Authority of Russia (GAN). It was revealed that the main type of radioactive waste at these facilities comprises SDSRS. This is the case both on summarised quantity of accumulated radioactivity (more than 99%) and on general quantity of the containers with waste (more than 80%). The average radionuclide composition of the SDSRS accumulated at regional facilities 'Radon' is as follows: Cs-137 (40%), Co-60 (25%), Sr-90 (22%), Ir-192 (8%) and Tm-170 (4%). The content of other radionuclides in SDSRS is not more than 1%. At regional facilities 'Radon' SDSRS mainly are disposed of in bore hole type repositories. Nevertheless SDSRS are also stored in containers being placed into repositories for solid radioactive waste. SDSRS which contain long lived radionuclides are stored until the decision on their final disposal into a deep geological formation. So far as free (not conditioned) storage of SDSRS can not provide safe conditions for environment for a long time, it is necessary to immobilise sources additionally into a suitable matrix material. Supplemental sources inclusion in a lead (or lead based alloy) matrix using Moscow SIA 'Radon' mobile plant was carried out at five regional 'Radon' facilities as follows: Zagorsk branch of Moscow SIA 'Radon', Volgograd, Ekaterinburg, Nizhny Novgorod, and Ufa. More than 1 million Ci of SDSRS are stored at present time in conditioned form in bore hole repositories. In 1998-1999 the Moscow

Safety assessment of borehole disposal of unwanted radioactive sealed sources in Egypt using Goldsim

International Nuclear Information System (INIS)

Cochran, John Russell; Mattie, Patrick D.

2004-01-01

A radioactive sealed source is any radioactive material that is encased in a capsule designed to prevent leakage or escape of the radioactive material. Radioactive sealed sources are used for a wide variety of applications at hospitals, in manufacturing and research. Typical uses are in portable gauges to measure soil compaction and moisture or to determine physical properties of rocks units in boreholes (well logging). Hospitals and clinics use radioactive sealed sources for teletherapy and brachytherapy. Oil exploration and medicine are the largest users. Accidental mismanagement of radioactive sealed sources each year results in a large number of people receiving very high or even fatal does of ionizing radiation. Deliberate mismanagement is a growing international concern. Sealed sources must be managed and disposed effectively in order to protect human health and the environment. Effective national safety and management infrastructures are prerequisites for efficient and safe transportation, treatment, storage, and disposal. The Integrated Management Program for Radioactive Sealed Sources in Egypt (IMPRSS) is a cooperative development agreement between the Egyptian Atomic Energy Authority (EAEA), Egyptian Ministry of Health (MOH), Sandia National Laboratories (SNL), the University of New Mexico (UNM), and Agriculture Cooperative Development International (ACDI/VOCA). The EAEA, teaming with SNL, is conducting a Preliminary Safety Assessment (PSA) of an intermediate-depth borehole disposal in thick arid alluvium in Egypt based on experience with the U.S. Greater Confinement Disposal (GCD). Goldsim has been selected for the preliminary disposal system assessment for the Egyptian GCD Study. The results of the PSA will then be used to decide if Egypt desires to implement such a disposal system

Management of Spent Radiation Source from Radiotherapy

International Nuclear Information System (INIS)

Aisyah

2008-01-01

Nowadays the use of radioactive source for both radiodiagnostic and radiotherapy in Indonesia hospital increases rapidly. Sealed source used in radiotherapy among others for brachytherapy, teletherapy, bone densitometry, whole blood irradiation and gamma knife (radiosurgery). In line with this, the waste of spent radiation sources will be generated in hospitals. Of course these spent radiation sources must be treated correctly in order to maintain the safety of both the public and the environment. According to the Act No. 10/1997, BATAN, in care of the Radioactive Waste Management Center is the national appointed agency for the management of radioactive waste. The option for waste management by hospitals needs to be expound, either by re-exporting to the supplier of origin, re-exporting to other supplier, re-use by other licensee or sending to the Radioactive Waste Management Center. Usually the waste sent by the hospitals to the center comprises of sealed radiation source of 60 Co, 137 Cs or 226 Ra. The management of spent radiation source in the center is carried out in several steps i.e. conditioning, temporary storage, and long-term storage (final disposal). The conditioning of non 226 Ra is carried out by placing the waste in a 200 litter drum shell, 950 or 350 litter concrete shells, depends on the activity and dimension of the spent radiation source. The conditioning of 226 Ra is carried out by encapsulating the waste in a stainless steel container for long-term storage shield which then placed in a 200 litter drum shell. The temporary storage of the conditioned spent radiation source is carried out by storing it in the center’s temporary storages, either low or medium activity waste. Finally, the conditioned spent radiation source is buried in a disposal facility. For medium half-life spent radiation source, the final disposal is burial it in a shallow-land disposal; mean while, for long half-life spent radiation source, the final disposal is burial it in

Management of Disused Radioactive Sealed Sources in Egypt - 13512

International Nuclear Information System (INIS)

Mohamed, Y.T.; Hasan, M.A.; Lasheen, Y.F.

2013-01-01

The future safe development of nuclear energy and progressive increasing use of sealed sources in medicine, research, industry and other fields in Egypt depends on the safe and secure management of disused radioactive sealed sources. In the past years have determined the necessity to formulate and apply the integrated management program for radioactive sealed sources to assure harmless and ecological rational management of disused sealed sources in Egypt. The waste management system in Egypt comprises operational and regulatory capabilities. Both of these activities are performed under legislations. The Hot Laboratories and Waste Management Center HLWMC, is considered as a centralized radioactive waste management facility in Egypt by law 7/2010. (authors)

Safe management of discussed sealed sources in Peru

International Nuclear Information System (INIS)

Mallaupoma, M.

2000-01-01

The future safe development of nuclear energy and progressive increasing use of sealed sources in medicine, research, industry and other fields in Peru, in the past years have determined the necessity to formulate and apply an Institutional policy to assure harmless and ecologically rational management of disused sealed sources in Peru. Some results of the studies, which served as a basis for design and construction of a facility for treatment, conditioning and storage of conditioned sealed sources are presented in this paper. The waste management system in Peru comprises operational and regulatory capabilities. Both of these activities are performed under a legislation. The Nuclear Research Center RACSO has a radioactive waste management department which is in charge of the management of disused sealed sources produced in the country. It is considered as a centralized waste processing and storage facility (WPSF). (author)

Sealed Source Security and Disposition: Progress and Prospects - 13515

International Nuclear Information System (INIS)

Jennison, Meaghan; Martin, David W.; Cuthbertson, Abigail

2013-01-01

Due to their high activity and portability, unsecured or abandoned sealed sources could cause significant health or environmental damage. Further, some of these sources could be used either individually or in aggregate in radiological dispersal devices commonly referred to as 'dirty bombs', resulting in significant social disruption and economic impacts in the billions of dollars. Disposal access for disused sealed sources, however, has been a serious challenge. From 2008 to 2012, sealed source disposal was available to only 14 states; additionally, waste acceptance criteria for sealed sources at the low-level waste disposal facilities in operation both prior to and after 2012 exclude some common yet potentially dangerous sealed sources. Recent developments, however, suggest that significant improvement in addressing this challenge is possible, although challenges remain. These developments include 1) the initiation of operations at the Waste Control Specialists (WCS) commercial low-level radioactive waste (LLRW) disposal facility in Andrews County, Texas; 2) the potential for significant revisions of the U.S. Nuclear Regulatory Commission's (NRC) 1995 'Final Branch Technical Position on Concentration Averaging and Encapsulation' (1995 BTP); and 3) the Utah Department of Environmental Quality's (UDEQ) approval of a license variance for sealed source disposal at the EnergySolutions LLRW disposal facility near Clive, Utah. (authors)

Control of sealed sources and equipments used in gammagraphy

International Nuclear Information System (INIS)

Sahyun, A.; Sordi, G.-M.A.A.; Biazzini Filho, F.L.

1988-01-01

The Radiation Protection Department of the IPEN-CNEN/SP, in 1987, formed a section incharged to control all radioactive material: a) received by the IPEN-CNEN/SP; b) produced by the IPEN-CNEN/SP; c) delivered from the IPEN-CNEN/SP. The aim of this section is to maintain a permanent control of all radioactive sources movement got at the IPEN-CNEN/SP. This control is performed with a microcomputer, trademark MICRODIGITAL, model TK3000 //e, 256 KBytes of memory, utilizing the TOTALWORKS program. This program permits to have the origin, characteristics and address of the radioactive sources, its sites in the IPEN, its uses, etc. Already we have put in the microcomputer, the control of the sealed sources produced used in nondestructive test, the inspection control of the gamagraphy irradiator and the control of the depleted sources. The next step is to introduce in the computer the inspection of the remote control of the irradiator. The aim of this paper is to describe the control program that was already put on. This radioactive material control was started with the sealed sources used in gamagraphy because we believe that is the field with the most likelihood of accident in the population, and therefore it's that need the most hard control about the site and the performance of the irradiation facility. (author) [pt

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

An ideal sealed source life-cycle

International Nuclear Information System (INIS)

Tompkins, Joseph Andrew

2009-01-01

In the last 40 years, barriers to compliant and timely disposition of radioactive sealed sources have become apparent. The story starts with the explosive growth of nuclear gauging technologies in the 1960s. Dozens of companies in the US manufactured sources and many more created nuclear solutions to industrial gauging problems. Today they do not yet know how many Cat 1, 2, or 3 sources there are in the US. There are, at minimum, tens of thousands of sources, perhaps hundreds of thousands of sources. Affordable transportation solutions to consolidate all of these sources and disposition pathways for these sources do not exist. The root problem seems to be a lack of necessary regulatory framework that has allowed all of these problems to accumulate with no national plan for solving the problem. In the 1960s, Pu-238 displaced Pu-239 for most neutron and alpha source applications. In the 1970s, the availability of inexpensive Am-241 resulted in a proliferation of low energy gamma sources used in nuclear gauging, well logging, pacemakers, and X-ray fluorescence applications for example. In the 1980s, rapid expansion of worldwide petroleum exploration resulted in the expansion of Am-241 sources into international locations. Improvements of technology and regulation resulted in a change in isotopic distribution as Am-241 made Pu-239 and Pu-238 obsolete. Many early nuclear gauge technologies have been made obsolete as they were replaced by non-nuclear technoogies. With uncertainties in source end of life disposition and increased requirements for sealed source security, nuclear gauging technology is the last choice for modern process engineering gauging solutions. Over the same period, much was learned about licensing LLW disposition facilities as evident by the closure of early disposition facilities like Maxey Flats. The current difficulties in sealed source disposition start with adoption of the NLLW policy act of 1985, which created the state LLW compact system they

Sealed sources in Peru: advances and outlook

International Nuclear Information System (INIS)

Rodriguez, C.G.

1998-01-01

Cementation of spent sealed sources is performed by the Radioactive Waste Management Group of the Peruvian Institute of Nuclear Energy (IPEN). The sealed sources are collected in different areas of the country and brought to the RACSO nuclear centre, a national storage and conditioning facility for spent sources from industry and medical institutions. In addition to its amenities dedicated to research and the production of radioisotopes, the RACSO nuclear centre features a complex of some 1.5 ha for radioactive waste management that includes an infiltration bed and chemical treatment plant for liquid waste, compacting equipment and trenches for solid radioactive waste, a tank for the elimination of biological residues and a temporary storage emplacement for radioactive waste immobilized in cement cylinder casings. The steps described are the unpacking, identification of spent sealed sources, placement of the source in shielding, cementation, solidification, tagging and storage, as well as the actions taken to comply with the appropriate measures of radiological protection. (author)

Lesson Learned from Conditioning of Disused Sealed Radioactive Sources (DSRS) in Malaysia

International Nuclear Information System (INIS)

Nik Marzukee Nik Ibrahim; Mohd Abdul Wahab Yusof; Norasalwa Zakaria

2016-01-01

This paper presents the conditioning of disused sealed radioactive source (DSRS) in Malaysia. In Malaysia, sealed radioactive sources (SRS) are widely used in Malaysia especially in industry, medicine and research. Once SRS are no longer in use, they are declared disused and managed as radioactive waste. In order to reduce the risk associated with disused sealed radioactive sources (DSRS), the first priority would be to bring them under appropriate controls. This paper describes the experience developed and activities performed by Nuclear Malaysia throughout the period in conditioning of DSRS as well as future programme to further enhancing the infrastructure. Collaborative efforts with the various relevant groups such as Loji and Prototaip Development Centre (PDC) and Industrial Technology Division (BTI) provide an effective avenue in ensuring successful implementation of the programme. Currently, until August 2015, Malaysia has in possession about 12,154 unit of DSRS categories 3-5 and 4 units of DSRS category 2 sources which being stored at the interim storage facility Nuclear Malaysia. A national activity was implemented for the on-the-job training of personnel tasked with the conditioning of DSRS, at the Waste Technology Development Centre (WasTeC) facilities. This is part of -cradle-to-grave- control of radioactive sources to protect the workers and public from the hazards of ionizing radiation. (author)

The safe use of radiation sources

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-12-01

As a means of promoting safety in the use of radiation sources, as well as encouraging consistency in regulatory control, the IAEA has from time to time organized training courses with the co-operation of Member State governments and organizations, to inform individuals from developing countries with appropriate responsibilities on the provisions for the safe use and regulation of radiation sources. Three such courses on the safe use of radiation sources have been held in both the USA, with the co-operation of the United States Government, and in Dublin, Ireland, with the co-operation of the Irish Government. The Training Course on the Safe Use and Regulation of Radiation Sources has been successfully given to over 77 participants from over 30 countries during the last years. The course is aimed at providing a basis of radiation protection knowledge in all aspects of the uses of radiation and of radiation sources that are used today. It is the intention of this course to provide a systematic enhancement of radioisotope safety in countries with developing radiological programmes through a core group of national authorities. The IAEA's training programmes provide an excellent opportunity for direct contact with lecturers that have extensive experience in resolving issues faced by developing countries and in providing guidance documents useful in addressing their problems. This document uses this collective experience and provides valuable technical information regarding the safety aspects of the uses not only of sealed and unsealed sources of radiation, but also for those machines that produce ionizing radiation. The first of these training courses, 'Safety and Regulation of Unsealed Sources' was held in Dublin, Ireland, June through July 1989 with the co-operation of the Nuclear Energy Board and Trinity College. This was an interregional training course, the participants came from all over the world. The second and third interregional courses, 'Safety and Regulation

The safe use of radiation sources

International Nuclear Information System (INIS)

1995-01-01

As a means of promoting safety in the use of radiation sources, as well as encouraging consistency in regulatory control, the IAEA has from time to time organized training courses with the co-operation of Member State governments and organizations, to inform individuals from developing countries with appropriate responsibilities on the provisions for the safe use and regulation of radiation sources. Three such courses on the safe use of radiation sources have been held in both the USA, with the co-operation of the United States Government, and in Dublin, Ireland, with the co-operation of the Irish Government. The Training Course on the Safe Use and Regulation of Radiation Sources has been successfully given to over 77 participants from over 30 countries during the last years. The course is aimed at providing a basis of radiation protection knowledge in all aspects of the uses of radiation and of radiation sources that are used today. It is the intention of this course to provide a systematic enhancement of radioisotope safety in countries with developing radiological programmes through a core group of national authorities. The IAEA's training programmes provide an excellent opportunity for direct contact with lecturers that have extensive experience in resolving issues faced by developing countries and in providing guidance documents useful in addressing their problems. This document uses this collective experience and provides valuable technical information regarding the safety aspects of the uses not only of sealed and unsealed sources of radiation, but also for those machines that produce ionizing radiation. The first of these training courses, 'Safety and Regulation of Unsealed Sources' was held in Dublin, Ireland, June through July 1989 with the co-operation of the Nuclear Energy Board and Trinity College. This was an interregional training course, the participants came from all over the world. The second and third interregional courses, 'Safety and Regulation

Control of sources of ionizing radiation in Lithuania

International Nuclear Information System (INIS)

Mastauskas, Albinas; Ziliukas, Julius; Morkunas, Gendrutis

1997-01-01

Aspects connected with regulatory control of radioactive sources in Lithuania, such as keeping of the computer-based registry, investigation of arrested illegal radioactive material, decision making, control of users of radioactive sources are discussed. Most of the sources of ionizing radiation are smoke detectors and x-ray equipment. Potentially most dangerous sources (both sealed and unsealed) of therapy and industry are also presented

Production of the sealed gamma-radiation sources of with iridium-192 radionuclide at the WWR-K research reactor

International Nuclear Information System (INIS)

Petukhov, V.K.; Chernayev, V.P.; Chabeyev, N.T.; Ermakov, E.L.; Chakrov, P.V.

2005-01-01

Full text: Conversion orientation of the WWR-K research reactor activity was established after renewal of its operation in 1997. A priority in reactor works was determined in the decision of tasks of practical use of nuclear technologies in a national economy in the next directions: in an industry, public health services and agriculture. The items of prime tasks: development and introduction of radiation technologies and manufacturing of radioisotopes for industry. This task included both scientific and technical program in the list of works of the Republican goals. At the WWR-K reactor within the framework of the this task solution the works on pilot production of the sealed sources of radioactive radiations (SSRR) with Ir-192 radionuclide for an industry of Republic of Kazakhstan were made. Organizational questions related to the Kazakhstan authority body and the regulating documentation were solved the first of all. The second stage was the development of the techniques of creating of devices providing an samples irradiation in reactor, control of sources sealing, measurements of the equivalent radiation doze from sources and high-quality support of SSRR manufacture over all technological way. At the third stage was made a little quantity SSRR with Ir-192 radionuclide, such as GIID-A1 (G6), for 'TEKOPS-660' Gammaray Projectors. This work served as experimental check of the decisions correctness, and has allowed to remove those lacks, to find out which it was possible only during direct manufacturing of radioactive sources. During performance of all these works the following was carried out: development and release of the documents and specifications regulating work on SSRR manufacture at the Institute of Nuclear Physics; personnel preparation and certification; preparation and equipment providing of reactor hot chambers by additional devices for work with irradiated iridium samples; development and manufacturing of the devices for iridium samples irradiation in

State Register of Sources of Ionizing Radiation and Occupational exposure

CERN Document Server

2002-01-01

One of main tasks of Radiation Protection Centre is to collect, process, systematize, store and provide the data on sources of ionizing radiation and occupational exposures. The number of sources in 2002 is provided and compared with previous year. Distribution of workers according to the type of practice is compared with previous year. Distribution of sealed sources and x-ray machines according their use is presented.

Safe management of sealed radioactive sources at Karachi nuclear power complex

International Nuclear Information System (INIS)

Tahir, T.B.; Qamar, A.

2000-01-01

This paper describes the conditioning of sealed radioactive sources, carried out at the Karachi Nuclear Power Complex (KNPC) in co-operation with the IAEA. The radioactive sources were radium needles of various size, used by various radiotherapy units in different hospitals throughout the country. For some time the use of radium needles had been abandoned and they were stored in hospitals awaiting proper disposal. Since their storage conditions were not ideal and there was a potential of leakage of radioactive material into the environment, it was decided to condition and store them safely. A significant logistic effort was required to identify these sources, bring them to a central facility and condition them according to current international standards. Various steps were involved in conditioning the sources: place it in a stainless steel capsule, weld the capsule, test it for a leak, place the capsule in a lead shielded package, put and seal the shielded package in a concrete-lined steel drum and finally store it at the waste storage facility. A total amount of about 1500 mg of Radium needles were conditioned. Radiation exposure during the entire operation was within acceptable limits. (author)

Review of Sealed Source Designs and Manufacturing Techniques Affecting Disused Source Management

International Nuclear Information System (INIS)

2012-10-01

This publication presents an investigation on the influence of the design and technical features of sealed radioactive sources (SRSs) on predisposal and disposal activities when the sources become disused. The publication also addresses whether design modifications could contribute to safer and/or more efficient management of disused sources without compromising the benefits provided by the use of the sealed sources. This technical publication aims to collect information on the most typical design features and manufacturing techniques of sealed radioactive sources and examines how they affect the safe management of disused sealed radioactive sources (DSRS). The publication also aims to assist source designers and manufacturers by discussing design features that are important from the waste management point of view. It has been identified that most SRS manufacturers use similar geometries and materials for their designs and apply improved and reliable manufacturing techniques e.g. double- encapsulation. These designs and manufacturing techniques have been proven over time to reduce contamination levels in fabrication and handling, and improve source integrity and longevity. The current source designs and materials ensure as well as possible that SRSs will maintain their integrity in use and when they become disused. No significant improvement options to current designs have been identified. However, some design considerations were identified as important to facilitate source retrieval, to increase the possibility of re-use and to ensure minimal contamination risk and radioactive waste generation at recycling. It was also concluded that legible identifying markings on a source are critical for DSRS management. The publication emphasizes the need for a common understanding of the radioactive source's recommended working life (RWL) for manufacturers and regulators. The conditions of use (COU) are important for the determination of RWL. A formal system for specification

Characterization of Greater-Than-Class C sealed sources. Volume 3, Sealed sources held by general licensees

International Nuclear Information System (INIS)

Harris, G.

1994-09-01

This is the third volume in a series of three volumes characterizing the population of sealed sources that may become greater-than-Class C low-level radioactive waste (GTCC LLW). In this volume, those sources possessed by general licensees are discussed. General-licensed devices may contain sealed sources with significant amounts of radioactive material. However, the devices are designed to be safe to use without special knowledge of radiological safety practices. Devices containing Am-241 or Cm-244 sources are most likely to become GTCC LLW after concentration averaging. This study estimates that there are about 16,000 GTCC devices held by general licensees; 15,000 of these contain Am-241 sources and 1,000 contain Cm-244 sources. Additionally, this study estimates that there are 1,600 GTCC devices sold to general licensees each year. However, due to a lack of available information on general licensees in Agreement States, these estimates are uncertain. This uncertainty is quantified in the low and high case estimates given in this report, which span approximately an order of magnitude

A general description of the Swedish radiation protection regulations of radioactive sources

International Nuclear Information System (INIS)

Staalnacke, C.-G.

2001-01-01

The regulation of ionizing radiation in Sweden is based on both the Radiation Protection Act and Ordinance from 1998. The Swedish Radiation Protection Institute (SSI) acts as the regulatory authority for radiation safety and issues detailed regulations in specific areas. The report summarizes how the SSI controls radiation sources, including orphan sources for which a process for analyzing their occurrence has started in Sweden. A number of proposed procedures for the control and follow-up of sealed radioactive sources is provided. (author)

Sure confinement of spent sealed sources; Confinamiento seguro de fuentes selladas gastadas

Energy Technology Data Exchange (ETDEWEB)

Lizcano, D., E-mail: david.lizcano@inin.gob.mx [ININ, Departamento de Desechos Radiactivos, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

2013-10-15

The industrial and technological development of the last decades produced and increment in the radiations application in different human activities. One of the main effects has been the production of radioactive wastes of all the levels. In Mexico, several stages of the waste management of low and intermediate level have not been completely resolved, as the case of the treatment and the final storage. In this work the confinement of spent sealed sources is described, maintaining as main objective the security of these sources and the protection to the workers and the people. (author)

Control of sources of ionizing radiation in Lithuania

Energy Technology Data Exchange (ETDEWEB)

Mastauskas, Albinas; Ziliukas, Julius; Morkunas, Gendrutis [Radiation Protection Centre, Vilnius (Lithuania)

1997-12-31

Aspects connected with regulatory control of radioactive sources in Lithuania, such as keeping of the computer-based registry, investigation of arrested illegal radioactive material, decision making, control of users of radioactive sources are discussed. Most of the sources of ionizing radiation are smoke detectors and x-ray equipment. Potentially most dangerous sources (both sealed and unsealed) of therapy and industry are also presented 2 refs., 2 tabs.; e-mail: rsc at post.omnitel.net

Systematic management of sealed source and nucleonic counting system in field service

International Nuclear Information System (INIS)

Mahadi Mustapha; Mohd Fitri Abdul Rahman; Jaafar Abdullah

2005-01-01

PAT group have received a lot of service from the oil and gas plant. All the services use sealed source and nucleonic counting system. This paper described the detail of management before going to the field service. This management is important to make sure the job is smoothly done and safe to the radiation worker and public. Furthermore this management in line with the regulation from LPTA. (Author)

Categorization of In-use Radioactive Sealed Sources in Egypt

International Nuclear Information System (INIS)

Hasan, M.A.; Mohamed, Y.T.; El Haleim, K.A.

2006-01-01

Radioactive sealed sources have widespread applications in industry, medicine, research and education. While most sources are of relatively low activity, there are many of medium or very high activity. The mismanagement of high activity sources is responsible for most of the radiological accidents that result in loss of life or disabling injuries. Because of the variety of applications and activities of radioactive sources, a categorization system is necessary so that the controls that are applied to the sources are adequate with its radiological risk. The aim of this work is to use the international Atomic Energy Agency (IAEA) categorization system to provide a simple, logical system for grading radioactive sealed sources in Egypt. The categorizations of radioactive sealed sources are based on their potential to cause harm to human health. This study revealed that total of 1916 sources have been used in Egypt in the different applications with a total activity of 89400 Ci according to available data in October 2005. (authors)

Management of disused sealed sources

International Nuclear Information System (INIS)

Lukauskas, D.; Skridaila, N.

2003-01-01

The report presents the requirements on management of disused sealed sources in Lithuania; disused sealed source disposal facilities; performed safety analysis and planed repository safety improvements. The requirements on pre-disposal management of Disused Sealed Sources (DSS) are presented. The requirements on disposal of short lived VLLW and LILW (A, B and C classes) radioactive waste approved in 2002-2003. Generic Waste Acceptance Criteria for Near Surface Disposal, P-2003-01 approved in 2003. Requirements on disposal of Low and intermediate level long lived waste do not exist (D and E classes). Requirements for the disposal of disused sealed sources (F class) do not exist. Disposal method for the F class - Near Surface or Deep geological repository, depending on the waste acceptance criteria. Only one repository for institutional radioactive waste exist in Lithuania - Maisiagala repository. It is near surface RADON type disposal facility, built in 1963 and closed in 1988. It was constructed of the monolithic reinforced concrete with the dimensions 5 m x 15 m x 3 m, the thickness of the sidewalls is about 0.25 m and the thickness of the bottom is about 0.2 m. The overall volume is about 200 m 3 . At time of closure only three fifths of the volume had been filled. The empty two fifths of the vault were filled with concrete, then with sand, then with the concrete (0.01 m), hot bitumen and the 0.05 m asphalt layers. Monolithic concrete that was covered with bitumen and 0.05 m thick layer of asphalt closed the vault. Sand layer the thickness of which was not less than 1.2 m formed the cap. Disused radioactive sources embedded in a biological shielding were buried together with their shielding, the sources without the shielding were buried in two stainless steel containers. The total activity of buried radioactive nuclides is 3.42.10 -15 Bq (calculated according the documentation). There are some uncertainties about the inventory: from 1963 to 1973. After the

10 CFR 39.35 - Leak testing of sealed sources.

Science.gov (United States)

2010-01-01

... 10 Energy 1 2010-01-01 2010-01-01 false Leak testing of sealed sources. 39.35 Section 39.35 Energy....35 Leak testing of sealed sources. (a) Testing and recordkeeping requirements. Each licensee who uses... record of leak test results in units of microcuries and retain the record for inspection by the...

R1800: a new Co 60 sealed source

International Nuclear Information System (INIS)

Freijo, Jose L.; Gomez, Gonzalo

2005-01-01

The increasing demand of Co 60 sealed sources in the international market has made necessary the development of new models of sealed sources. R 1800 type source up to 65 KCi has a design that allows to accommodate a wide spectrum of capsules with different specific activities. The company Dioxitek has developed the fabrication process and the design specifications needed to obtain the approval of the product. A first shipment of 100 KCi has been made with success to the United Kingdom in October of the current year. (author) [es

BOSS: Borehole Disposal of Disused Sealed Sources. A Technical Manual

International Nuclear Information System (INIS)

2011-01-01

The management of disused radioactive sources is the responsibility of individual Member States. Accordingly, interest in technologies to allow the safe, secure and sustainable management of disused sealed radioactive sources is growing. This publication is a technical summary on preparing and planning predisposal and disposal activities with regard to the BOSS (borehole disposal of disused sealed sources) system, a safe, simple and cost effective solution for the management of disused sealed radioactive sources. It advises potential implementers and decision makers on the implementation of BOSS, which is expected to provide Member States with a successful tool to contribute to the safety and security of current and future generations.

The Nonactinide Isotope and Sealed Sources Management Group

International Nuclear Information System (INIS)

Low, J. L.; Polansky, G. F.; Parks, D. L.

2002-01-01

The Nonactinide Isotope and Sealed Sources Management Group (NISSMG) is sponsored by the Department of Energy (DOE) Office of Environmental Management and managed by Albuquerque Operations Office (DOE/AL) to serve as a complex-wide resource for the management of DOE-owned Nonactinide Isotope and Sealed Source (NISS) materials. NISS materials are defined as including: any isotope in sealed sources or standards; and isotopes, regardless of form, with atomic number less than 90. The NISSMG assists DOE sites with the storage, reuse, disposition, transportation, and processing of these materials. The NISSMG has focused its efforts to date at DOE closure sites due to the immediacy of their problems. Recently, these efforts were broadened to include closure facilities at non-closure sites. Eventually, the NISSMG plans to make its resources available to all DOE sites. This paper documents the lessons learned in managing NISS materials at DOE sites to date

Investigation of the present management status of calibration source based on the law concerning prevention of radiation hazards due to radioisotopes

International Nuclear Information System (INIS)

Takahashi, Yasuyuki; Igarashi, Hiroshi; Hirano, Kunihiro; Kawaharada, Yasuhiro; Igarashi, Hitoshi; Murase, Ken-ya; Mochizuki, Teruhito

2007-01-01

An amendment concerning the enforcement of the law on the prevention of radiation hazards due to radioisotopes, etc., and the medical service law enforcement regulations were promulgated on June 1, 2005. This amendment concerned international basic safety standards and the sealing of radiation sources. Sealed radiation sources ≤3.7 MBq, which had been excluded from regulation, were newly included as an object of regulation. Investigation of the single photon emission computed tomography (SPECT) system instituted in hospitals indicated that almost all institutions adhere to the new amendment, and the calibration source, the checking source, etc., corresponding to this amendment were maintained appropriately. Any institutions planning to return sealed radioisotopes should refer to this report. (author)

Radiation sources and technical services

International Nuclear Information System (INIS)

Stonek, K.; Satorie, Z.; Vyskocil, I.

1981-01-01

Work is briefly described of the department for sealed sources production of the Institute, including leak testing and surface contamination of sealed sources. The department also provides technical services including the inspections of sealed sources used in medicine and geology and repair of damaged sources. It carries out research of the mechanical and thermal strength of sealed sources and of the possibility of reprocessing used 226 Ra sources. The despatch department is responsible for supplying the entire country with home and imported radionuclides. The department of technical services is responsible for testing imported radionuclides, assembling materials testing, industrial and medical irradiation devices, and for the collection and storage of low-level wastes on a national scale. (M.D.)

Characterization and packaging of disused sealed radioactive sources; Caracterizacion y acondicionamiento de fuentes radiactivas selladas en desuso

Energy Technology Data Exchange (ETDEWEB)

Aguilar, S.L. [Instituto Boliviano de Ciencia y Tecnologia Nuclear (IBTEN), La Paz (Bolivia, Plurinational State of)

2013-07-01

In Bolivia are generated disused sealed sources and radioactive waste resulting from the use of radioactive materials in industrial, research and medicine. The last includes the diagnosis and treatment. Whereas exposure to ionizing radiation is a potential hazard to personnel who applies it, to those who benefit from its use or for the community at large, it is necessary to control the activities in this field. The Instituto Boliviano de Ciencia y Tecnologia Nuclear - IBTEN is working on a regional project from International Atomic Energy Agency - IAEA, RLA/09/062 Project - TSA 4, Strengthening the National Infrastructure and Regulatory Framework for the Safe Management of Radioactive waste in Latin America. This Project has strengthened the regulatory framework regarding the safe management of radioactive waste. The aim of this work was focused primarily on the security aspects in the safe management of disused sealed sources. The tasks are listed below: 1. Characterization of disused sealed sources 2. Preparation for transport to temporary storage 3. Control of all disused radioactive sources. (author)

Dismantling, conditioning and repatriation of disused sealed radioactive sources

International Nuclear Information System (INIS)

Aguilar, S.L.; Miranda, C.A.; Saire, A.E.; Ontiveros, G.P.

2015-01-01

In Bolivia sealed radioactive sources for medical, industrial and research applications are used; radioactive sources containing a wide range of radionuclides and have different levels of activity and half-lives, they generated a problem when they stop being used. At the end of its useful life these sources are considered obsolete. However, residual levels of radioactivity, which have these sources can be high constituting a potential hazard to personnel and applies to those who benefit from its use and the general public. The aim of this work has been focused mainly on safety issues in the safe handling and management of disused sealed sources. Assignments listed below: 1. Dismantling; 2. Packaging; 3. Return of disused sealed radioactive sources. The actions taken were carried out by the technical teams of the Bolivian Institute of Nuclear Science and Technology (IBTEN) and Los Alamos National Laboratory (LANS) which supports the program 'Global Threat Reduction Initiative's' (GTRI) in the implementation of 'Off -site Source Recovery Program' (OSRP). [es

The regulatory control of ionizing radiation sources in Lithuania

International Nuclear Information System (INIS)

Mastauskas, A.; Ziliukas, J.; Morkunas, G.

1998-01-01

The Radiation Protection Centre of the Ministry of Health is the regulatory authority responsible for radiation protection of the public and of workers using sources of ionizing radiation in Lithuania. One of its responsibilities is the control of radioactive sources, which includes keeping the registry, investigating persons arrested while illegally carrying or in possession of radioactive material, decision making and control of users of radioactive sources. The computer based registry contains a directory of more than 24,000 sources and some 800 users in research, medicine and industry. Most of these sources are found in smoke detectors and X ray equipment. The potentially most dangerous sources for therapy and industry (sealed and unsealed) are also listed in this registry. Problems connected with the regulatory control of radioactive sources in Lithuania are presented and their solution is discussed. (author)

Control of sealed radioactive sources in Peru

International Nuclear Information System (INIS)

Ramirez Quijada, R.

2001-01-01

The paper describes the inventory of radioactive sources in Peru and assesses the control. Three groups of source conditions are established: controlled sources, known sources, and lost and orphan sources. The potential risk, described as not significant, for producing accidents is established and the needed measures are discussed. The paper concludes that, while the control on sealed sources is good, there is still room for improvement. (author)

Sealed source and device removal and consolidation feasibility study

International Nuclear Information System (INIS)

Ward, J.E.; Carter, J.G.; Meyers, R.L.

1993-02-01

The purpose of this study is to assess the feasibility of removing Greater-Than-Class C (GTCC) sealed sources from their containment device and consolidating them for transport to a storage or disposal facility. A sealed source is a sealed capsule containing a radioactive material that is placed in a device providing radioactive containment. It is used in the medical, industrial, research, and food-processing communities for calibrating, measuring, gauging, controlling processes, and testing. This feasibility study addresses the key operational, safety, regulatory, and financial requirements of the removal/consolidation process. This report discusses the process to receive, handle, repackage, and ship these sources to an interim or dedicated storage facility until a final disposal repository can be built and become operational (∼ c. 2010). The study identifies operational and facility requirements to perform this work. Hanford, other DOE facilities, and private hot-cell facilities were evaluated to determine which facilities could perform this work. The personnel needed, design and engineering, facility preparation, process waste disposal requirements, and regulatory compliance were evaluated to determine the cost to perform this work. Cost requirements for items that will have to meet future changing regulatory requirements for transportation, transportation container design and engineering, and disposal were not included in this study. The cost associated with in-process consolidation of the sealed sources reported in this study may have not been modified for inflation and were based on 1992 dollars. This study shows that sealed source consolidation is possible with minimal personnel exposure, and would reduce the risk of radioactive releases to the environment. An initial pilot-scale operation could evaluate the possible methods to reduce the cost and consolidate sources

Installation for producing sealed radioactive sources

International Nuclear Information System (INIS)

Fradin, J.; Hayoun, C.

1969-01-01

This installation has been designed and built for producing sealed sources of fission elements: caesium 137, strontium 90, promethium 147, ruthenium 106 and cerium 144 in particular. The installation consists of sealed and protected cells, each being assigned to a particular production. The safety and the operational reliability of the equipment are the principal considerations which have governed this work. The report describes the installation and, in particular, the apparatus used as well as the various control devices. In conclusion, a review as presented of six years operation. (authors) [fr

Offsite source recovery project - ten years of sealed source recovery and disposal

Energy Technology Data Exchange (ETDEWEB)

Whitworth, Julia Rose [Los Alamos National Laboratory; Pearson, Mike [Los Alamos National Laboratory; Witkowski, Ioana [Los Alamos National Laboratory; Wald - Hopkins, Mark [Los Alamos National Laboratory; Cuthbertson, A [NNSA

2010-01-01

The Global Threat Reduction Initiative's (GTRI) Offsite Source Recovery Project (OSRP) has been recovering excess and unwanted radioactive sealed sources for ten years. In January 2009, GTRI announced that the project had recovered 20,000 sealed radioactive sources (this number has since increased to more than 23,000). This project grew out of early efforts at Los Alamos National Laboratory (LANL) to recover and disposition excess Plutonium-239 (Pu-239) sealed sources that were distributed in the 1960s and 1970s under the Atoms for Peace Program. Decades later, these sources began to exceed their special form certifications or fall out of regular use. As OSRP has collected and stored sealed sources, initially using 'No Path Forward' waste exemptions for storage within the Department of Energy (DOE) complex, it has consistently worked to create disposal pathways for the material it has recovered. The project was initially restricted to recovering sealed sources that would meet the definition of Greater-than-Class-C (GTCC) low-level radioactive waste, assisting DOE in meeting its obligations under the Low-level Radioactive Waste Policy Act Amendments (PL 99-240) to provide disposal for this type of waste. After being transferred from DOE-Environmental Management (EM) to the U.S. National Nuclear Security Administration (NNSA) to be part of GTRI, OSRP's mission was expanded to include not only material that would be classified as GTCC when it became waste, but also any other materials that might constitute a 'national security consideration.' It was recognized at the time that the GTCC category was a waste designation having to do with environmental consequence, rather than the threat posed by deliberate or accidental misuse. The project faces barriers to recovery in many areas, but disposal continues to be one of the more difficult to overcome. This paper discusses OSRP's disposal efforts over its 10-year history. For sources

Management for the prevention of accidents from disused sealed radioactive sources

International Nuclear Information System (INIS)

2001-04-01

The objective of this report is to provide advice to sealed radiation source (SRS) users, radioactive waste operators, and other concerned public sectors on the measures to be taken to reduce the risk of accidents associated with disused or spent SRS. The report also explains policies as well as technical and administrative procedures to minimize the risk of accidents and to mitigate the consequences should an accident occur. The report emphasizes areas of high risk in handling disused or spent SRS in any form and condition to help to save health, life and financial resources

Management of disused sealed sources from the nuclear industry in China

International Nuclear Information System (INIS)

Fan Xuanlin

2002-01-01

Since the founding of the nuclear industry in China, more than 8000 disused sealed sources accumulated of which more than 1800 are Radium sources. Most of these sources were produced during the period 1960-1980. The disused radioactive sources are temporarily stored in a user's interim store. A project to manage these disused sealed sources is under way which includes inventory investigation, inspection, collection, transportation and long-term storage. (author)

Radiation protection and regulatory aspects in the use of radiation sources

International Nuclear Information System (INIS)

Sen, Amit; Dash Sharma, P.K.; Sonawane, A.U.

2012-01-01

The uses of ionising radiation sources (i.e. radioisotopes and radiation generating equipment such as accelerators and X-ray machines) for multifarious applications in industry, medicine, agriculture, research and teaching have been significantly increasing all over the world. In India, the application of radiation sources in various fields has registered phenomenal growth during the last decade. The use of radiation sources mainly include radiation processing for food preservation and sterilization of healthcare products, radiotherapy for treatment of cancer, nuclear medicine for diagnosis and therapy, gamma chambers for several R and D studies, blood irradiators, industrial radiography for non destructive examinations of steel structures, industrial ionising radiation gauging devices for monitoring/measurement of on-line quality control parameters (e.g. thickness, level, density, moisture, elemental analysis), consumer products such as gaseous tritium light sources (GTLS), gaseous tritium light devices (GTLD), ionisation chamber smoke detectors (ICSD), fluorescent light starters, antistatic devices and incandescent gas mantles containing thorium etc. All these beneficial applications involve use of both sealed and unsealed radioactive sources and amount of radioactivity varies from few kBq (μCi) to hundreds of TBq (thousands of curies). Radiation sources emit ionising radiations and if not handled properly and safely, may give rise to potential exposures leading to an unacceptable hazard. Therefore, it is necessary to ensure a high standard of safety and reliability in handling of radiation equipment and sources through their careful design by ensuring adequate built-in-safety as per applicable national/international standard, safe operation and periodic maintenance procedures, safe transport from one place to another, secured storage when not in use, physical security to radiation sources, effective emergency response plans and preparedness, including safe

10 CFR 34.27 - Leak testing and replacement of sealed sources.

Science.gov (United States)

2010-01-01

... 10 Energy 1 2010-01-01 2010-01-01 false Leak testing and replacement of sealed sources. 34.27... SAFETY REQUIREMENTS FOR INDUSTRIAL RADIOGRAPHIC OPERATIONS Equipment § 34.27 Leak testing and replacement... radiographic exposure device and leak testing of any sealed source must be performed by persons authorized to...

Reduction of Radioactive Waste Through the Reuse and Recycle Policy of the Sealed Radioactive Sources Management

Directory of Open Access Journals (Sweden)

T. Marpaung

2012-08-01

Full Text Available In the past few years, the utilization of sealed source for medical, industrial and research purposes has shown an accelerating increase. This situation will lead to increases in the amount of sealed radioactive. During its use, a sealed radioactive waste will eventually become either a spent sealed source or disused sealed radioactive source (DSRS, due to certain factors. The reduction of the amount of radioactive waste can be executed through the application of reuse and recycle of sealed source. The reuse and recycle policy for spent and disused sealed sources are not already specified yet. The reuse of spent sealed sources can be applied only for the sources which had been used in the medical field for radiotherapy, namely the reuse of a teletherapy Co-60 source in a calibration facility. The recycle of a spent sealed source can be performed for radioactive sources with relatively high activities and long half-lives; however, the recycling activity may only be performed by the manufacturer. To avoid legal conflicts, in the amendment to the Government Regulation No.27 Year 2002 on Management of Radioactive Waste, there will be a recommendation for a new scheme in the management of radioactive waste to facilitate the application of the principles of reduce, reuse, and recycle

Reduction of Radioactive Waste Through the Reuse and Recycle Policy of the Sealed Radioactive Sources Management

International Nuclear Information System (INIS)

Marpaung, T.

2012-01-01

In the past few years, the utilization of sealed source for medical, industrial and research purposes has shown an accelerating increase. This situation will lead to increases in the amount of sealed radioactive. During its use, a sealed radioactive waste will eventually become either a spent sealed source or disused sealed radioactive source (DSRS), due to certain factors. The reduction of the amount of radioactive waste can be executed through the application of reuse and recycle of sealed source. The reuse and recycle policy for spent and disused sealed sources are not already specified yet. The reuse of spent sealed sources can be applied only for the sources which had been used in the medical field for radiotherapy, namely the reuse of a teletherapy Co-60 source in a calibration facility. The recycle of a spent sealed source can be performed for radioactive sources with relatively high activities and long half-lives; however, the recycling activity may only be performed by the manufacturer. To avoid legal conflicts, in the amendment to the Government Regulation No.27 Year 2002 on Management of Radioactive Waste, there will be a recommendation for a new scheme in the management of radioactive waste to facilitate the application of the principles of reduce, reuse, and recycle (author)

Reduction of Radioactive Waste Through the Reuse and Recycle Policy of the Sealed Radioactive Sources Management

OpenAIRE

Marpaung, T

2012-01-01

In the past few years, the utilization of sealed source for medical, industrial and research purposes has shown an accelerating increase. This situation will lead to increases in the amount of sealed radioactive. During its use, a sealed radioactive waste will eventually become either a spent sealed source or disused sealed radioactive source (DSRS), due to certain factors. The reduction of the amount of radioactive waste can be executed through the application of reuse and recycle of sealed ...

Experience with first aid in radiation sources accidents

International Nuclear Information System (INIS)

Klener, V.

1979-01-01

More than 20 years of experience at the Radiation Hygiene Centre of the Prague Institute of Hygiene and Epidemiology with prevention of accidents involving sources of radiation and the Centre's participation in providing medical aid in such accidents are described. A list is given of major types of accidents over the past decade. Prevalent were accidents involving sealed gamma sources, resulting in excessive local irradiation with serious skin damage or injury to some of the deeper structures of the hands, requiring plastic operation. Chromosomal picture investigation allows the estimation of the equivalent body dose which only reached higher values in a single case recorded (1.5 Gy = 150 rad). Organisational measures are described for emergencies and the task is shown by radiation hygiene departments attached to regional hygiene stations. The present system is capable of providing adequate, prompt and effective assistance. (author)

International Catalogue of Sealed Radioactive Sources and Devices

International Nuclear Information System (INIS)

2010-01-01

The international catalogue of sealed radioactive sources and devices have two major objectives. The first objective is to provide vital information for a wide range of individuals and organizations on industrially manufactured radioactive sources and devices. The second objective is to facilitate identification of design specifications based on limited information from orphan sources and devices to allow safe handling of these items.

Protection during work with ionizing radiation sources; Ochrana pri praci se zdroji ionizujiciho zareni

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-12-31

The publication has been set up as a textbook for training courses dealing with health protection during work with ionizing radiation, designed for supervisory staff and persons directly responsible for activities which involve the handling of ionizing radiation sources. The book consists of a preface and the following chapters: (1) Fundamentals of ionizing radiation physics; (2) Quantities and units used in ionizing radiation protection; (3) Principles of ionizing radiation dosimetry; (4) Biological effects of ionizing radiation; (5) An overview of sources of public irradiation; (6) Principles and methods of health protection against ionizing radiation; (7) Examples of technical applications of sources of ionizing radiation; (8) Personnel and working environment monitoring; (9) Documentation maintained at sites with ionizing radiation sources; (10) Methods of personnel protection against external irradiation and internal radionuclide contamination; (11) Radiation incidents and accidents; (12) Health care of personnel exposed to the ionizing radiation risk; (12) Additional radiation protection requirements in handling radioactive substances other than sealed sources; (13) Measurement and metrology. (P.A.).

Safety considerations in the disposal of disused sealed radioactive sources in borehole facilities

International Nuclear Information System (INIS)

2003-08-01

Sealed radioactive sources are used in medicine, industry and research for a wide range of purposes. They can contain different radionuclides in greatly varying amounts. At the end of their useful lives, they are termed 'disused sources' but their activity levels can still be quite high. They are, for all practical purposes, another type of radioactive waste that needs to be disposed of safely. Disused sealed radioactive sources can represent a significant hazard to people if not managed properly. Many countries have no special facilities for the management or disposal of radioactive waste, as they have no nuclear power programmes requiring such facilities. Even in countries with developed nuclear programmes, disused sealed sources present problems as they often fall outside the common categories of radioactive waste for which disposal options have been identified. As a result, many disused sealed sources are kept in storage. Depending on the nature of the storage arrangements, this situation may represent a high potential risk to workers and to the public. The IAEA has received numerous requests for assistance from Member States faced with the problem of safely managing disused sealed sources. The requests have related to both technical and safety aspects. Particularly urgent requests have involved emergency situations arising from unsafe storage conditions and lost sources. There is therefore an important requirement for the development of safe and cost-effective final disposal solutions. Consequently, a number of activities have been initiated by the IAEA to assist Member States in the management of disused sealed sources. The objective of this report is to address safety issues relevant to the disposal of disused sealed sources, and other limited amounts of radioactive waste, in borehole facilities. It is the first in a series of reports aiming to provide an indication of the present issues related to the use of borehole disposal facilities to safely disposal

Methods to identify and locate spent radiation sources; Metodos para la identificacion y localizacion de fuentes radiactivas gastadas

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-06-01

The objective of this manual is to provide essential guidance to Member States with nuclear applications involving the use of a wide range of sealed radiation sources on the practical task of physically locating spent radiation sources not properly accounted for. Advice is also provided to render the located source safe on location. Refs, figs, tabs.

Safety considerations in the disposal of disused sealed radioactive sources in borehole facilities

CERN Document Server

International Atomic Energ Agency. Vienna

2003-01-01

Sealed radioactive sources are used in medicine, industry and research for a wide range of purposes. They can contain different radionuclides in greatly varying amounts. At the end of their useful lives, they are termed 'disused sources' but their activity levels can still be quite high. They are, for all practical purposes, another type of radioactive waste that needs to be disposed of safely. Disused sealed radioactive sources can represent a significant hazard to people if not managed properly. Many countries have no special facilities for the management or disposal of radioactive waste, as they have no nuclear power programmes requiring such facilities. Even in countries with developed nuclear programmes, disused sealed sources present problems as they often fall outside the common categories of radioactive waste for which disposal options have been identified. As a result, many disused sealed sources are kept in storage. Depending on the nature of the storage arrangements, this situation may represent a ...

Reducing Risks from Sealed Radioactive Sources in Medicine

International Nuclear Information System (INIS)

2014-01-01

Sealed radioactive sources are commonly used in a variety of medical applications for both diagnosis and therapy. The sources used in medical applications usually have high levels of radioactivity and, therefore, have the potential to cause serious and life threatening injuries if used improperly or maliciously, or risky if they become lost or are stolen

Strategic planning as a competitive differential: A case study of the Sealed Sources Production Laboratory

International Nuclear Information System (INIS)

Vieira, Imário; Nascimento, Fernando C.; Calvo, Wilson A. Parejo

2017-01-01

Strategic planning has always been and continues to be one of the most important management tools for decision making. Amidst the uncertainties of the 21"s"t century, public, private and third sector organizations are steadily struggling to improve their strategic plans by using more effective results management tools such as BSC-Balanced Scorecard. Nuclear research institutes and research centers around the world have been using more and more these types of tools in their strategic planning and management. The objective of this article was to recommend the use the BSC as a strategic tool for decision making for the Sealed Sources Production Laboratory located in the Radiation Technology Center, at Nuclear and Energy Research Institute (IPEN/CNEN-SP), in Sao Paulo, Brazil. The methodology used in this academic article was a case study, which considered the object of the study, the Sealed Sources Production Laboratory, from January 2014 to August 2016. Among the main results obtained with this study can be cited: the improvement of the information flow, the visualization and proposition to change the periodicity of analysis of the results, among others. In view of the expected results, it was possible to conclude that this study may be of value to the Sealed Sources Production Laboratory for Industrial Radiography and Industrial Process Control and also to other research centers, as it will allow and contribute with an additional management support tool. (author)

Strategic planning as a competitive differential: A case study of the Sealed Sources Production Laboratory

Energy Technology Data Exchange (ETDEWEB)

Vieira, Imário; Nascimento, Fernando C.; Calvo, Wilson A. Parejo, E-mail: imariovieira@yahoo.com, E-mail: wapcalvo@ipen.br, E-mail: fcodelo@gmail.com [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil); Faculdade SENAI de Tecnologia Ambiental, Sao Bernardo do Campo, SP (Brazil)

2017-11-01

Strategic planning has always been and continues to be one of the most important management tools for decision making. Amidst the uncertainties of the 21{sup st} century, public, private and third sector organizations are steadily struggling to improve their strategic plans by using more effective results management tools such as BSC-Balanced Scorecard. Nuclear research institutes and research centers around the world have been using more and more these types of tools in their strategic planning and management. The objective of this article was to recommend the use the BSC as a strategic tool for decision making for the Sealed Sources Production Laboratory located in the Radiation Technology Center, at Nuclear and Energy Research Institute (IPEN/CNEN-SP), in Sao Paulo, Brazil. The methodology used in this academic article was a case study, which considered the object of the study, the Sealed Sources Production Laboratory, from January 2014 to August 2016. Among the main results obtained with this study can be cited: the improvement of the information flow, the visualization and proposition to change the periodicity of analysis of the results, among others. In view of the expected results, it was possible to conclude that this study may be of value to the Sealed Sources Production Laboratory for Industrial Radiography and Industrial Process Control and also to other research centers, as it will allow and contribute with an additional management support tool. (author)

Disposal of disused sealed sources in France

International Nuclear Information System (INIS)

Certes, C.

2003-01-01

The current status of the disused sealed sources in France is presented and a proposal for future management is given.About 150 000 disused source are registered, most of which are located in the Centre de l'Aube (130 000) and the rest are in about 250 installations. Since 2002 the tracing of the sources are made bu the IRSN/UES. A scheme of sealed sources management is given consisting of collecting, channeling (recycling, reconditioning, interim storage, denaturation) and elimination (surface disposal, long interim or deep disposal). The capacity of the CDA for disposal is 1 mill. m 3 (about 2 mill. tons of waste). It is intended for waste packages containing (basic safety rule I.2) - Low and Intermediate specific activity levels ( ∼ 103 ∼ 106 Bq/g); Short-lived radionuclides (half-life 60 Co). For sources containing one concentrated long-lived radionuclide in case of non-conformity with the basic safety rule I.2 (heterogeneity and long half-life) for example refusal is received for a few sources containing 241 Am). Radiological capacity id base on inventories nad safety evaluation scenarios. Fixed by decree (TBq) are: 60 Co(5.3 y) - 400 000; 3 H(12.3 y) - 4000; 137 Cs(30 y); - 200 000; 90 Sr(29 y) -40 000; Σ alpha (at 300 years) - 750. Waste acceptance criterion is based on the mass activity limit. The importance of the calculation method in this criterion is emphasised. IRSN reflexion basis for disposal is discussed

Development of sealed sheet sources for calibration of whole-body counters

International Nuclear Information System (INIS)

Miyamoto, Mai; Ishigure, Nobuhito; Ogata, Yoshimune; Narita, Norihiko; Kawaura, Chiyo; Nakano, Takashi

2009-01-01

Whole body counters are usually calibrated with the aid of a whole body phantom assembled with simply-shaped plastic vessels that are filled with an aqueous solution of the relevant radioisotopes. Most vessel-type phantoms represent only a human body in which radioisotopes are homogeneously distributed, whereas the radioisotopes in vivo are sometimes localized to specific organs. Each set of the vessels is usually applicable only to a specific combination of radioisotopes, because the replacement of radioisotopes requires troublesome procedures. Possible leakage of the solution is another disadvantage of the vessel-type phantom. The authors are developing a new-type calibration phantom that is free from these disadvantages, in which sealed sheet sources are sandwiched between sections of a sliced anthropomorphic phantom. This paper describes a method to prepare sealed sheet sources for this calibration phantom. Instead of γ-ray emitters a pure β-ray emitter 32 P was used. This isotope is suitable for autoradiography and is easy to handle as its half-life is relatively short. An ink-jet printer was used to spread the solution of 32 P mixed with ink on a sheet of paper. The surface concentration of radioactivity was regulated by the function of color density adjustment of an image processing software. The radioisotope-printed paper was laminated for sealing. Through the measurement of surface concentration of radioactivity with a liquid scintillation counter, the autoradiographical investigation of the pattern of the radioactivity distributed on the sheet sources, the immersion test of the sealed sheet sources and the monitoring of the concentration of 32 P in air during the printing, it was demonstrated that sealed sheet sources for the calibration phantom can be prepared safely by the method described in this paper. Furthermore, by using sheet sources of 99m Tc prepared as a trial it was confirmed that discrete arrangement of sheet sources in a phantom at a

Challenges in Regulating Radiation Sources and Associated Waste Management

International Nuclear Information System (INIS)

Shehzad, A.

2016-01-01

Radiation sources are widely used in the fields of medical, industry, agriculture, research, etc. Owing to the inherent risk of exposure to ionizing radiations while using the radiation sources and management of associated waste, safety measures are of utmost importance including robust regulatory control. Pakistan Nuclear Regulatory Authority (PNRA) is responsible for supervising all matters pertaining to nuclear safety and radiation protection in the country. Since its inception, PNRA has made rigorous efforts to regulate the radiation facilities for which regulatory framework was further strengthened by taking into account international norms/practices and implemented afterwards. However, due to vibrant use of these facilities, there are numerous challenges being faced while implementing the regulatory framework. These challenges pertains to shielding design of some facilities, control over service provider for QC/repair maintenance of radiation equipment, assessment of patient doses, and establishment of national diagnostic reference levels for radiological procedures. Further, the regulatory framework also delineate requirements to minimize the generation of associated radioactive waste as low as practicable. The requirements also necessitates that certain sealed radioactive sources (SRS) are returned to the supplier upon completion of their useful life, while other radioactive sources are required to be transported for storage at designated radioactive waste storage facilities in the country, which requires commitment from the licensee. This paper will briefly describe the challenges in regulating the radiation sources and issues related to the waste management associated with these facilities. (author)

Technology, safety, and costs of decommissioning a reference large irradiator and reference sealed sources

Energy Technology Data Exchange (ETDEWEB)

Haffner, D.R.; Villelgas, A.J. [Pacific Northwest Lab., Richland, WA (United States)

1996-01-01

This report contains the results of a study sponsored by the US Nuclear Regulatory Commission (NRC) to examine the decommissioning of large radioactive irradiators and their respective facilities, and a broad spectrum of sealed radioactive sources and their respective devices. Conceptual decommissioning activities are identified, and the technology, safety, and costs (in early 1993 dollars) associated with decommissioning the reference large irradiator and sealed source facilities are evaluated. The study provides bases and background data for possible future NRC rulemaking regarding decommissioning, for evaluation of the reasonableness of planned decommissioning actions, and for determining if adequate funds are reserved by the licensees for decommissioning of their large irradiator or sealed source facilities. Another purpose of this study is to provide background and information to assist licensees in planning and carrying out the decommissioning of their sealed radioactive sources and respective facilities.

Technology, safety, and costs of decommissioning a reference large irradiator and reference sealed sources

International Nuclear Information System (INIS)

Haffner, D.R.; Villelgas, A.J.

1996-01-01

This report contains the results of a study sponsored by the US Nuclear Regulatory Commission (NRC) to examine the decommissioning of large radioactive irradiators and their respective facilities, and a broad spectrum of sealed radioactive sources and their respective devices. Conceptual decommissioning activities are identified, and the technology, safety, and costs (in early 1993 dollars) associated with decommissioning the reference large irradiator and sealed source facilities are evaluated. The study provides bases and background data for possible future NRC rulemaking regarding decommissioning, for evaluation of the reasonableness of planned decommissioning actions, and for determining if adequate funds are reserved by the licensees for decommissioning of their large irradiator or sealed source facilities. Another purpose of this study is to provide background and information to assist licensees in planning and carrying out the decommissioning of their sealed radioactive sources and respective facilities

Cover-gas seals: 11-LMFBR seal-test program

International Nuclear Information System (INIS)

Steele, O.P. III; Horton, P.H.

1977-01-01

The objective of the Cover Gas Seal Material Development Program is to perform the engineering development required to provide reliable seals for LMFBR application. Specific objectives are to verify the performance of commercial solid cross-section and inflatable seals under reactor environments including radiation, to develop advanced materials and configurations capable of achieving significant improvement in radioactive gas containment and seal temperature capabilities, and to optimize seal geometry for maximum reliability and minimal gas permeation

Management of disused long lived sealed radioactive sources (LLSRS)

International Nuclear Information System (INIS)

2003-06-01

The document provides advice the sealed source users and the national waste management organizations with the technical know-how on the management of disused and spent long lived sealed radioactive sources (LLSRS) and with the particular guidelines required for handling, conditioning for storage, and storage of these sources. The guidance is intended to assist in establishing compliance with the present standards, requirements, and adopted practices. It also provides background material for any possible technical assistance to developing countries and serves as a reference for technical staff involved with IAEA programmes on the subject. Because of the historic nature of many of the sources under this category and the lack of well developed technical procedures recognized on the international level, this publication can serve as a basis for establishing future handling and conditioning procedures. The LLSRS addressed in this publication are primarily those containing radionuclides having half-lives greater than 30 years. These sources may contain long lived alpha-emitters, mainly 238 Pu, 239 Pu, 237 Np, 241 Am, 226 Ra; beta-emitters: 14 C, and 63 Ni and could be neutron sources such as PuBe, RaBe and AmBe

Industrial applications of radiotracer and sealed source technology promoted by IAEA

International Nuclear Information System (INIS)

Joon-Ha Jin; Thereska, J.

2004-01-01

Great technical and economical benefits can be obtained by applying radioisotope technologies to various industries. The International Atomic Energy Agency (IAEA) has contributed to the development of radiotracer and sealed source technology as applied to industry and environment through coordinated research projects (CRPs). The mature and competitive techniques have been transferred and implemented to developing countries through the Agency's technical co-operation (TC) projects. The paper presents the main achievements in radiotracer and sealed source technology promoted by IAEA as well as the perspective of the technology transfer to developing countries. (author)

Evaluation of the sealing properties and TMA study of multilayer PA/PE film treated with e-beam radiation

International Nuclear Information System (INIS)

Ortiz, Angel V.; Gargalaka Junior, Joao; Wiebeck, Helio

2007-01-01

Multilayer films are widely used in the food industry as thermoforming as well as non thermoforming vacuum packaging. In this study a PA6/LDPE multilayer film underwent E-beam radiation and its sealing properties were evaluated over 3 years after the film was irradiated. Packaging materials have been widely processed by ionizing radiation in order to improve their chemical and physical properties and also for sterilization purposes. Basically, flexible packaging manufacturers apply specific radiation doses to promote cross-linking and scission of the polymeric chains and thus obtain alterations in certain properties. While enhancing a specific property, significant losses may result in others. We examined the effects of E-beam radiation on the sealing properties of the multilayer film irradiated with doses up to 127 kGy. Results showed that as doses go up, the sealing strength goes down. The TMA study shows that the softening/melting temperatures of the LDPE layer (sealing layer) varies according to the irradiation doses and helps explain the results of the sealing strength tests. (author)

Design and production of activimeters verification sealed radioactive sources

International Nuclear Information System (INIS)

Serra, R.; Hernandez Rivero, A. T.; Oropesa, P.; Rapado, M.; Falcon, L.

2006-01-01

Measurement in a radionuclide calibrator (activimeter) of the doses to be administered to a patient for diagnosis or radiotherapeutic treatment is an essential element in Nuclear Medicine practice. To assure that patient will receive the optimal doses that guarantee the necessary quality of the image to be studied or optimum radiotherapeutic effect, the activity determination should fulfil established accuracy requirements. To this aim, the overall uncertainty in activity determination must not surpass a preestablished limit of about 10 % for the expanded uncertainty of the activity value (with a coverage factor k = 3). To have suitable equipment, periodically calibrated for specialized and authorized specialists and frequently verified in inter calibration periods to guarantee detection of any malfunctioning, are essential requirements to assure the compliance with the prescribed regulations and limiting values. This paper describes the design and production of two models of 137 Cs activimeters verification sealed radioactive sources elaborated with this aim at the Radionuclide Metrology Department of the Isotope Centre of Cuba. Taking into account the international experience in this field was defined 3 -10 MBq as convenient activity range, the 137 Cs as a suitable radionuclide, and a classification ISO/99/C22212 (ISO 2919:1999) for the sealed sources to be obtained. In designed and produced models the activity is bonded in a hydrogel copolymer obtained by gamma irradiation, in a 60 Co irradiator, of a mixture of a 137 Cs aqueous solution with an approximate activity of 5 MBq with two proper monomers (acrylamide and methacrylic acid). The density of obtained copolymer is similar to that of the radioactive solutions employed in nuclear medicine departments for diagnosis and therapy. The obtained sources have appropriate physical stability for a temperature range between 40 o C below zero and 80 o C, as well as for defined activity range. The stability of the

Conditioning and storage of spent sealed radium sources

International Nuclear Information System (INIS)

Cholerzynski, A.; Tomczak, W.

2001-01-01

In Poland sealed radioactive sources (SRS) are extensively used in medicine and in industry. There are mainly Co-60, Cs-137, lr-192 and also historical sources contain in Ra-226. The Radioactive Waste Management Department (ZDUOP) of the Institute of Atomic Energy at Swierk is the only organization licensed for the management, storage and disposal of radioactive waste in Poland. ZDUOP deals with all radioactive waste in the country. Storage and disposal of SRS is one of the most important part of its activity. Every year ZDUOP collects about 1000 spent SRS which total activity is near 600 GBq. Spent Ra-226 sources are a special case and therefore are required suitable procedures. Due to their production according to earlier standards and their undesirable characteristics, leakage of these sources is highly possible and practically observed. For this reason conditioning of radium sources needs strict requirements and quality assurance procedure to guarantee their safe storage for an extended period of time (e.g. 40-70 years). The National Radioactive Waste Repository is superficial type repository and considered as temporary storage site for long-lived waste. A storage facility for spent SRS has been properly prepared and licensed by the regulatory body. This facility consist of several concrete chambers which floor is lined stainless steel. The existing regulatory framework for sealed radioactive sources entered into force with issue of the Atomic Law in 1986

Development of an externally controllable sealed isotope generator.

Science.gov (United States)

Sasaki, Toru; Aoki, Katsumi; Yamashita, Ryosuke; Hori, Kensuke; Kato, Taiga; Saito, Misaki; Niisawa, Kazuhiro; Nagatsu, Kotaro; Nozaki, Tadashi

2018-03-01

An externally controllable sealed isotope generator has been proposed for radiation education activities. Column ( 68 Ge- 68 Ga and 137 Cs- 137m Ba) and solvent extraction ( 68 Ge- 68 Ga)-based isotope generators were applied as radioactive sources. These generators showed high milking efficiencies and low breakthrough after repeated uses, and are expected to promote the use of isotope generators without radioactive contamination or the emission of radioactive waste. This isotope generator provides a new concept for sealed radioisotope sources. Copyright © 2017 Elsevier Ltd. All rights reserved.

R I 800. A new cobalt-60 sealed source design

International Nuclear Information System (INIS)

Freijo, Jose L.; Gomez, Gonzalo

2006-01-01

The consolidation of the international market of Co-60 sources and the perspective of its growth has encouraged the development of new types of sealed sources. The model R I 800 is designed for activities up to 65 kCi and allows a large spectrum of capsules with different specific activities. During three years Dioxitek developed the process of fabrication and qualifications to comply the design requirements and succeeded in the product approval. Today, the initial lot at an industrial scale of R I 800 sources is under fabrication and a first partial shipment of 100 kCi to the United Kingdom was successfully carried out at the end of October 2005. The whole lot is for export. Due to the versatility of the R I 800 sealed sources it was possible to use as raw material 1 MCi of Co-60 imported from Russia, irradiated in Leningrad nuclear power plant. (author) [es

Use of reports on accidents with sealed sources to conceive scenarios of human intrusion into waste repositories

International Nuclear Information System (INIS)

Leite, Eliana Rodrigues; Oliveira, Rosana Lagua de; Vicente, Roberto

2011-01-01

The Radioactive Waste Management Department (GRR) at the Nuclear and Energy Research Institute (IPEN) develops the concept of a repository for disposal of disused sealed radioactive sources (SRS) in a deep borehole. In this concept, the estimated few hundred thousand SRS of the Brazilian inventory will be packaged in lead containers stacked in an encased and cemented borehole, drilled to a depth of a few hundred meters, in a crystalline bedrock geological setting. A generic safety analysis for this concept of repository must achieve two goals: to be acceptable by regulatory bodies and be simple enough so that the engineering of licensing a facility has technical and economical feasibility. It must be kept in mind that the disposition of the SRS must be paid by the users of the sources, and thal the costs of applying the existing methods for the performance and safety assessment of a geological repository dedicated exclusively for sealed sources may be exceedingly high. In this respect, the disposal concept development work includes the search for methodologies that could be applied to the disposal facility for demonstrating safety without unduly increasing the project costs. One line of research is to identify and characterize human intrusion scenarios that could result in significant radiation exposures. Results of a survey on the published literature and on databases of reported accidents involving sealed sources are being used to construct a number of model accident scenarios with which the time evolution of the exposure risks can be assessed for each radioisotope inventory and each relevant disposed of source. Among the 252 accident descriptions recovered in the survey, the 1954 Russian accident report with Po-210 is the oldest, and that of the 2010 accident in Mayapuri, India, with a Co-60 source is the latest. The results of this assessment will be used as a safety indicator of the disposal concept. (author)

Conditioning of disused sealed sources in countries without disposal facility: Short term gain - long term pain

International Nuclear Information System (INIS)

Benitez-Navarro, J.C.; Salgado-Mojena, M.

2002-01-01

Owing to the considerable development in managing disused sealed radioactive sources (DSRS), the limited availability of disposal practices for them, and the new recommendations for the use of borehole disposal concept, it was felt that a paper reviewing the existing recommendations could be a starting point of discussion on the retrievability of the sources. Even when no international consensus exists as to an acceptable solution for the challenge of disposal of disused sealed sources, the 'Best Available Technology' for managing most of them, recommended for developing countries, included the cementation of the sources. The waste packages prepared in such a way do not allow any flexibility to accommodate possible future disposal requirements. Therefore, the 'Wait and See' approach could be also recommended for managing not only the sources with long-live radionuclides and high activity, but probably for all kind of existing disused sealed sources. The general aim of the current paper is to identify and review the current recommendations for managing disused sealed sources and to meditate on the most convenient management schemes for disused sealed radioactive sources in Member States without disposal capacities (Latin America, Africa). The risk that cemented DSRS could be incompatible with future disposal requirements was taken into account. (author)

The present problems of hygienic supervising of workplaces with ionizing radiation sources

International Nuclear Information System (INIS)

Husar, J.

1995-01-01

This paper deals with the problems of hygienic supervising of workplaces with ionizing radiation sources in Bratislava. Most problems consist in present economic transformation of State Corporations. Abolishing of previous State Corporations and arising of new organizations means new field of their activities. It often happens, that previously used ionizing radiation sources, X-ray tubes, or radioactive sources, are not longer to use and it is necessary to remove corresponding workplaces.The big State Corporation with series of subsidiaries in whole Slovakia was divided to many new smaller Joint-stock Corporations. A subsidiary possessed workplace with X-ray tube and sealed radioactive source of medium radioactivity. During a routine hygienic inspection was found, that the original establishment was abolished, all personal dismissed and another organization is going to move at this place. New organization personnel has not known,that the previous workplace was such one with radiation sources. The situation was complicated by the fact, that new management had no connection to previous personnel and had not sufficient information about abolished establishment. The problem of supervising workplaces with ionizing radiation sources is described. (J.K.)

The present problems of hygienic supervising of workplaces with ionizing radiation sources

Energy Technology Data Exchange (ETDEWEB)

Husar, J [State Health Institute of Slovak Republic, Bratislava (Czech Republic)

1996-12-31

This paper deals with the problems of hygienic supervising of workplaces with ionizing radiation sources in Bratislava. Most problems consist in present economic transformation of State Corporations. Abolishing of previous State Corporations and arising of new organizations means new field of their activities. It often happens, that previously used ionizing radiation sources, X-ray tubes, or radioactive sources, are not longer to use and it is necessary to remove corresponding workplaces.The big State Corporation with series of subsidiaries in whole Slovakia was divided to many new smaller Joint-stock Corporations. A subsidiary possessed workplace with X-ray tube and sealed radioactive source of medium radioactivity. During a routine hygienic inspection was found, that the original establishment was abolished, all personal dismissed and another organization is going to move at this place. New organization personnel has not known,that the previous workplace was such one with radiation sources. The situation was complicated by the fact, that new management had no connection to previous personnel and had not sufficient information about abolished establishment. The problem of supervising workplaces with ionizing radiation sources is described. (J.K.).

Production techniques and quality control of sealed radioactive sources of palladium-103, iodine-125, iridium-192 and ytterbium-169. Final report of a coordinated research project 2001-2005

International Nuclear Information System (INIS)

2006-06-01

Radioisotopes have been used extensively for many years for several medical and industrial applications either in the form of an open source or encapsulated in an appropriate metallic container (sealed source). The design and technology for the preparation of radioactive sealed sources is an area of continuous development to satisfy an ever increasing demand for a larger variety of shapes, sizes, type of radioisotope and levels of radioactivity required for newer and specialized applications. In medicine, sealed sources using the radioisotopes of 125 I, 192 Ir and 103 Pd are commonly used for brachytherapy for the treatment of malignant diseases, and for bone density measurements. In industry, they are widely used for non-destructive testing (NDT), radiation processing, 'on-line' process control systems and on-line elemental analysis of mineral resources. Some well-known examples of such sources are 60 Co for industrial nucleonic gauges, 192 Ir sources for industrial radiography, 241 Am sources for smoke detectors and chemical analysers and, more recently, 169 Yb for NDT measurements of thin metallic tubes and plates. The current challenges in development include the production of miniature size sources with a high level of activity, a high degree of uniformity in the distribution of the radioactivity and the highest degree of safety, requiring stringent quality control methods. The IAEA has been promoting and supporting activities designed to increase the utilization of radiation and radioisotopes in several areas. In particular, in view of the proven benefits of, and an increasing demand for radioactive sealed sources for medical and industrial applications, upon the recommendation of several experts, a Coordinated Research Project (CRP) on Development of Radioactive Sources for Emerging Therapeutic and Industrial Applications was begun in 2002. The aim of the CRP was the optimization and testing of procedures and methods for the fabrication and quality control

Management and disposal of disused sealed radioactive sources in Europe

International Nuclear Information System (INIS)

Wells, D.A.; Angus, M.J.; Cecille, L.

2001-01-01

Full text: Sealed radioactive sources have been widely used for many decades in industry, medicine and research. Although most countries have laid down a regulatory framework to control sealed sources, there are still a number of uncertainties concerning the management of historical Ra- 226 alpha sources and the possibility of retrieving non-registered sources. Both these uncertainties may represent high radiological risks for the population. In addition, management schemes and practises implemented in different countries can be somewhat conflicting and create problems for storage and disposal. This paper describes the results of three studies that were carried out between 1998 and 2001 to consider the situation relating to the regulation and management of spent sealed radioactive sources (SSRS) in each of the fifteen current European Union (EU) member states and the ten central and eastern European (C and EE) countries that are currently being considered for admission to the European Union (namely, Bulgaria, Czech Republic, Estonia, Hungary, Latvia, Lithuania, Poland, Romania, Slovakia and Slovenia). The general aim of the studies was to acquire a thorough understanding of the management of SSRS in each country, in order to recommend improvements in management schemes and to establish whether the application of common disposal criteria would be advantageous. The studies covered the following activities: Estimation of the inventory of SSRS in store and disposed in each country; Analysis of the relevant regulations and regulatory framework in each country; Description and review of the current management practises in each country; Estimation of the number of unregistered SSRS (including identification of the reasons why SSRS are lost' and recommending ways of recovering lost' sources). It was important to understand the full life-cycle of sealed radioactive sources, from manufacture through to disposal. Much of the information contained in these studies was obtained

Cover gas seals: FFTF-LMFBR seal test program

International Nuclear Information System (INIS)

Kurzeka, W.; Oliva, R.; Welch, T.S.; Shimazaki, T.

1974-01-01

The objectives of this program are to: (1) conduct static and dynamic tests to demonstrate or determine the mechanical performance of full-size (cross section) FFTF fuel transfer machine and reactor vessel head seals intended for use in a sodium vapor-inert gas environment, (2) demonstrate that these FFTF seals or new seal configurations provide acceptable fission product and cover gas retention capabilities at Clinch River Breeder Reactor Plant (CRBRP) operating environmental conditions other than radiation, and (3) develop improved seals and seal technology for the CRBRP to support the national objective to reduce all atmospheric contaminations to low levels

Radiation sources safety and radioactive materials security regulation in Ukraine

International Nuclear Information System (INIS)

Smyshliaiev, A.; Holubiev, V.; Makarovska, O.

2001-01-01

Radiation sources are widely used in Ukraine. There are about 2500 users in industry, science, education and about 2800 in medicine. About 80,000 sealed radiation sources with total kerma-equivalent of 450 Gy*M 2 /sec are used in Ukraine. The exact information about the radiation sources and their users will be provided in 2001 after the expected completion of the State inventory of radiation sources in Ukraine. In order to ensure radiation source safety in Ukraine, a State System for regulation of activities dealing with radiation sources has been established. The system includes the following elements: establishment of norms, rules and standards of radiation safety; authorization activity, i.e. issuance of permits (including those in the form of licences) for activities dealing with radiation sources; supervisory activity, i.e. control over observance of norms, rules and standards of radiation safety and fulfilment of conditions of licences for activities dealing with radiation sources, and also enforcement. Comprehensive nuclear legislation was developed and implemented from 1991 to 2000. Radiation source safety is regulated by three main nuclear laws in Ukraine: On the use of nuclear energy and radiation safety (passed on 8 February 1995); On Human Protection from Impact of Ionizing Radiation (passed on 14 January 1998); On permissive activity in the area of nuclear energy utilization (passed on 11 January 2000). The regulatory authorities in Ukraine are the Ministry for Ecology and Natural Resources (Nuclear Regulatory Department) and the Ministry of Health (State sanitary-epidemiology supervision). According to the legislation, activities dealing with radiation sources are forbidden without an officially issued permit in Ukraine. Permitted activities with radiation sources are envisaged: licensing of production, storage and maintenance of radiation sources; licensing of the use of radiation sources; obligatory certification of radiation sources and transport

Radiation resistant, decontaminable and sealing jointing compounds for application in nuclear facilities

International Nuclear Information System (INIS)

Kunze, S.

1991-09-01

The sealing jointing compounds applied in practice and already examined for decontaminability will be presented here. Solvent-free sealing compounds, emulsifiable in water, with low molecular epoxy resins as binders, quite a number of curing versions, and little hygroscopic filler mixtures adapted in grain size have been tested with a view to ceramic tile jointing in nuclear facilities. The sealing compounds were examined before and after exposure to gamma irradiation (300 KGy energy dose) for decontaminability, color, gloss and resistance to decontaminants. Out of fourteeen compounds exhaustively investigated ten are very well decontaminable and four well decontaminable. After exposure to radiation no or only minor changes in color and gloss, respectively, were observed. Visible changes such as cracking, bubbles, etc. were not found and the resistance to decontaminants was neither affected. It has even been possible to replace in the well decontaminable sealing compounds developed until now part of the epoxy resin binder with elasticizing components such as Thiokol which is very important as a base material for sealing compounds in the construction industry, but difficult to decontaminate. (orig.) [de

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

Science.gov (United States)

Vaz, Pedro

2015-11-01

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

Management of disused sealed sources from nuclear gauges

International Nuclear Information System (INIS)

Reis, Luiz Carlos Alves; Silva, Fabio

2001-01-01

In Brazil there are about 600 Radioactive Facilities that operate 3300 nuclear gauges. The management goal for these sources is minimize the waste that must be stored and disposed, through reutilization or a more efficient method of disposal conditioning. A database is being implemented in order to facilitate the organization and retrieval of information about sources stored at CDTN. Examples of the information being included are: radionuclide, activity and date (e.g. 60 Co, 1 GBq, January 14th 1988); physical and chemical form of radionuclide; producer of the source; source type including dimensions and shape; source serial number; results of tests which have been done, for example leak tests; details of the equipment, i.e. dimensions, material, etc.; measured dose rates (at the surface and at I-m distance from it); whether the source was originally conditioned as special form radioactive material; working life of the equipment, etc. It is intended to reutilize only sealed sources containing certified special form radioactive material. Sources received at CDTN with this certification will be wipe tested in a hot-cell. A special Geiger Muller detector for measuring very low level radiation will be used to detect leakage at detection levels, even lower than the established leakage limit in the CNEN-NE-5.01 Standard. If the source does not exhibit leakage and the shutter operation and shielding of the nuclear gauge is in good condition, it will made available for reuse at a cost savings to the user over the purchase of a new source. Nuclear gauges whose sources do not meet these requirements will be dismantled and the sources efficiently conditioned. The CDTN guidelines for establishing a methodology for conditioning disused sources are: Dismantling the nuclear gauges in the hot-cell; Collecting the sources in an double-lead shielded cylindrical cavity below the hot-cell, until the limit of activity or level is reached; Transferring the internal shielding with the

Guide for the preparation of applications for licenses for the use of sealed sources in portable gauging devices

International Nuclear Information System (INIS)

1985-01-01

The purpose of this regulatory guide is to provide assistance to applicants and licensees in preparing applications for new licenses, license amendments, and license renewals for the use of sealed sources in portable gauging devices. An example of a portable gauging device is a moisture-density gauge that contains a gamma-emitting sealed source, cesium-137, and a sealed neutron source, americium-242-beryllium

Development of methodology for the characterization of radioactive sealed sources

International Nuclear Information System (INIS)

Ferreira, Robson de Jesus

2010-01-01

Sealed radioactive sources are widely used in many applications of nuclear technology in industry, medicine, research and others. The International Atomic Energy Agency (IAEA) estimates tens of millions sources in the world. In Brazil, the number is about 500 thousand sources, if the Americium-241 sources present in radioactive lightning rods and smoke detectors are included in the inventory. At the end of the useful life, most sources become disused, constitute a radioactive waste, and are then termed spent sealed radioactive sources (SSRS). In Brazil, this waste is collected by the research institutes of the Nuclear Commission of Nuclear Energy and kept under centralized storage, awaiting definition of the final disposal route. The Waste Management Laboratory (WML) at the Nuclear and Energy Research Institute is the main storage center, having received until July 2010 about 14.000 disused sources, not including the tens of thousands of lightning rod and smoke detector sources. A program is underway in the WML to replacing the original shielding by a standard disposal package and to determining the radioisotope content and activity of each one. The identification of the radionuclides and the measurement of activities will be carried out with a well type ionization chamber. This work aims to develop a methodology for measuring or to determine the activity SSRS stored in the WML accordance with its geometry and determine their uncertainties. (author)

Experience and Lessons Learned from Conditioning of Spent Sealed Sources in Singapore - 13107

Energy Technology Data Exchange (ETDEWEB)

Hong, Dae-Seok; Kang, Il-Sik; Jang, Kyung-Duk; Jang, Won-Hyuk [Korea Atomic Energy Research Institute, 1045 Daedeokdaero, Yuseong, Daejeon (Korea, Republic of); Hoo, Wee-Teck [National Environment Agency, 40 Scotts Road 228231 (Singapore)

2013-07-01

In 2010, IAEA requested KAERI (Korea Atomic Energy Research Institute) to support Singapore for conditioning spent sealed sources. Those that had been used for a lightning conductor, check source, or smoke detector, various sealed sources had been collected and stored by the NEA (National Environment Agency) in Singapore. Based on experiences for the conditioning of Ra-226 sources in some Asian countries since 2000, KAERI sent an expert team to Singapore for the safe management of spent sealed sources in 2011. As a result of the conditioning, about 575.21 mCi of Am-241, Ra-226, Co-60, and Sr-90 were safely conditioned in 3 concrete lining drums with the cooperation of the KAERI expert team, the IAEA supervisor, the NEA staff and local laborers in Singapore. Some lessons were learned during the operation: (1) preparations by a local authority are very helpful for an efficient operation, (2) a preliminary inspection by an expert team is helpful for the operation, (3) brief reports before and after daily operation are useful for communication, and (4) a training opportunity is required for the sustainability of the expert team. (authors)

Radiation stability of some sealing materials used in nuclear power plants

International Nuclear Information System (INIS)

Lukac, P.; Foeldesova, M.; Dillinger, P.

1987-01-01

The radiation stability was investigated of sealing strips by Wonisch, Silhoffer and Dehtochema. Samples of the strips were irradiated with various single doses at a dose rate 5.27 kGy.h -1 . Changes in mechanical properties were studied by measuring tensile strength, ductility, compressibility and resistance against aqueous decontamination solutions. The results of the measurement were compared with values for non-irradiated materials and were expressed in percentage. The experiments showed that the materials were stable within the given region of absorbed radiation doses. The highest stability for a dose of 0.25 MGy was shown by the sealing strip Asfaretan by Dehtochema which in many properties compares well with foreign-made materials and in some respects is even better. Its compressibility is, however, worse. The experimental results have shown that polymerization processes (cross-linking) prevail at doses of up to 0.33 MGy and that material degradation prevails above this level. (author)

Comparison of General Purpose Heat Source testing with the ANSI N43.6-1977 (R 1989) sealed source standard

International Nuclear Information System (INIS)

Grigsby, C.O.

1998-01-01

This analysis provides a comparison of the testing of Radioisotope Thermoelectric Generators (RTGs) and RTG components with the testing requirements of ANSI N43.6-1977 (R1989) ''Sealed Radioactive Sources, Categorization''. The purpose of this comparison is to demonstrate that the RTGs meet or exceed the requirements of the ANSI standard, and thus can be excluded from the radioactive inventory of the Chemistry and Metallurgy Research (CMR) building in Los Alamos per Attachment 1 of DOE STD 1027-92. The approach used in this analysis is as follows: (1) describe the ANSI sealed source classification methodology; (2) develop sealed source performance requirements for the RTG and/or RTG components based on criteria from the accident analysis for CMR; (3) compare the existing RTG or RTG component test data to the CMR requirements; and (4) determine the appropriate ANSI classification for the RTG and/or RTG components based on CMR performance requirements. The CMR requirements for treating RTGs as sealed sources are derived from the radiotoxicity of the isotope ( 238 P7) and amount (13 kg) of radioactive material contained in the RTG. The accident analysis for the CMR BIO identifies the bounding accidents as wing-wide fire, explosion and earthquake. These accident scenarios set the requirements for RTGs or RTG components stored within the CMR

Regulatory control of radiation sources and radioactive materials in Ireland

International Nuclear Information System (INIS)

McGarry, A.T.; Fenton, D.; O'Flaherty, T.

2001-01-01

The primary legislation governing safety in uses of ionizing radiation in Ireland is the Radiological Protection Act, 1991. This Act provided for the establishment in 1992 of the Radiological Protection Institute of Ireland, and gives the Institute the functions and powers which enable it to be the regulatory body for all matters relating to ionizing radiation. A Ministerial Order made under the Act in 2000 consolidates previous regulations and, in particular, provides for the implementation in Irish law of the 1996 European Union Directive which lays down basic safety standards for the protection of the health of workers and the general public against the dangers arising from ionizing radiation. Under the legislation, the custody, use and a number of other activities involving radioactive substances and irradiating apparatus require a licence issued by the Institute. Currently some 1260 licences are in force. Of these, some 850 are in respect of irradiating apparatus only and are issued principally to dentists and veterinary surgeons. The remaining licences involve sealed radiation sources and/or unsealed radioactive substances used in medicine, industry or education. A schedule attached to each licence fully lists the sealed sources to which the licence applies, and also the quantities of radioactive substances which may be acquired or held under the licence. It is an offence to dispose of, or otherwise relinquish possession of, any licensable material other than in accordance with terms and conditions of the licence. Disused sources are returned to the original supplier or, where this is not possible, stored under licence by the licensee who used them. Enforcement of the licensing provisions relies primarily on the programme of inspection of licensees, carried out by the Institute's inspectors. The Institute's Regulatory Service has a complement of four inspectors, one of whom is the Manager of the Service. The Manager reports to one of the Institute's Principal

The competent person in radiation protection: practical radiation protection for industry and research - unsealed sources

International Nuclear Information System (INIS)

Bruchet, H.

2009-01-01

The mission of the competent person in radiation protection has been broadly developed these last years to take an essential function in firm:study of working place, delimitation of regulated areas, monitoring of exposure, relations with authorities. The competent person in radiation protection must follow a training, defined by decree and shared in two parts: a theoretical part used as compulsory subjects and a practical part specific to the different sectors of activity (research, industry, medical centers, nuclear facilities) as well as the radiation use type. This volume corresponds to the practical module devoted to the industrial and research facilities concerned by the possession of management of sealed or unsealed sources. In accordance with the regulations stipulating that this module must allow to apply the theoretical knowledge to concrete situations in work. It includes eight chapters as following: radiation protection in industrial and research facilities, use of sources and associated risks, fitting out professional premises, evaluation of exposure, control of radiation protection; use of detection equipment and radioactive contamination and exposure measurement equipment, associated to methods and calculation tools; radioactive waste management; accidental or damaged situations management; methodology of working place analysis completed by the application to practical cases found in laboratories. (N.C.)

10 CFR 34.67 - Records of leak testing of sealed sources and devices containing depleted uranium.

Science.gov (United States)

2010-01-01

... 10 Energy 1 2010-01-01 2010-01-01 false Records of leak testing of sealed sources and devices containing depleted uranium. 34.67 Section 34.67 Energy NUCLEAR REGULATORY COMMISSION LICENSES FOR INDUSTRIAL... Requirements § 34.67 Records of leak testing of sealed sources and devices containing depleted uranium. Each...

Regulatory control for safe usage of ionizing radiation sources in Bangladesh

International Nuclear Information System (INIS)

Mollah, A.S.

2008-01-01

Full text: In Bangladesh, there is a widespread and continuos growth in the use of the ionizing radiation sources both radioactive materials and radiation generating equipment in the field of industry, medicine, agriculture, research, teaching etc. In industry, they are employed in production as well as quality control such as non-destructive testing (radiography), nucleonic gauging, radiotracer techniques and in radiation processing. Medical applications of ionizing radiation include X-ray radiography, X-ray fluoroscopy, CT scan, mammography, nuclear medicine, beam therapy and brachytherapy. Besides radioisotopes are also used for research applications, viz., scattering experiments, tracer studies, etc. In agriculture, the uptake of nutrients by soil, and parts of plants are studied using suitable radionuclides. In all the above applications radioisotopes in two forms namely sealed sources and open sources in different chemical forms are employed with source strengths varying from micro curies to mega curies. The benefits to man from the use of ionizing radiation and sources of radiation are accompanied by risks which may result from exposure of man to ionizing radiation. In order to have an effective control on the use of radiation sources and to ensure radiological safety of the user as well as the public, Government of Bangladesh has promulgated Nuclear Safety and Radiation Control (NSRC) rules 1997 under the NSRC Act 1993. The Bangladesh Atomic Energy commission (BAEC) is the competent authority for formulating rules and regulations for ensuring radiological safety. BAEC is legally responsible for developing and strengthening the necessary radiation protection infrastructure in the country through the effective enforcement and implementation of regulatory requirements, criteria, obligations, guiding, codes etc. in order to save man and the related environment from the deleterious effects of ionizing radiation. In Bangladesh, only those persons who have been

Environmental radiation control and quality management system in design and operation of sealed radioactive sources

International Nuclear Information System (INIS)

Hussein, A.Z.

2007-01-01

New environmental regulations and radiation safety standards are being implemented almost daily to ensure radiation safety, in particular for practices causing exposures to undue radiation doses. A particular emphasis of real challenge for organizations and users of radiation sources has to be for proper radiological safety assessment and is becoming cost effectively to be prepared for auditing. Special concern for the environment is of global . nature, and hence environmental auditing has been and will continue to be an essential practice for improving the environment and for meeting the relevant regulations and standards. In general, most facilities that deal with radioactive sources undertake strict safety measures in terms of personnel radiation protection, handling procedures and security. Hence, those measures should comply with the requirements of the environmental protection standards. Accordingly, a successful quality management system must balance realities of organization and personnel in achieving quality objectives. Organizational principles are found in the technical aspects of' quality management, such as, charting, requirements, measurements, procedures, ... , etc. Human principles are found in the communication side of quality management (e.g. meetings, ,decision making, ,teams, ... , etc). The quality management must understand and balance skills needed to blend them together. Large gamma irradiators present a high potential radiation hazard to the surrounding environment, since the amount of radioactivity is of the order of (P Bq) and a very high dose rates are produced during irradiation. Application of environmental radiation control deemed by regulatory authority and a proper quality management system by the utility would serve public health and safety

Sealed source and device design safety testing. Volume 4: Technical report on the findings of Task 4, Investigation of sealed source for paper mill digester

International Nuclear Information System (INIS)

Benac, D.J.; Iddings, F.A.

1995-10-01

This report covers the Task 4 activities for the Sealed Source and Device Safety testing program. SwRI was contracted to investigate a suspected leaking radioactive source that was installed in a gauge that was on a paper mill digester. The actual source that was leaking was not available, therefore, SwRI examined another source. SwRI concluded that the encapsulated source examined by SwRI was not leaking. However, the presence of Cs-137 on the interior and exterior of the outer encapsulation and hending tube suggests that contamination probably occurred when the source was first manufactured, then installed in the handling tube

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

International Nuclear Information System (INIS)

Vaz, Pedro

2015-01-01

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

Mechanical seals

CERN Document Server

Mayer, E

1977-01-01

Mechanical Seals, Third Edition is a source of practical information on the design and use of mechanical seals. Topics range from design fundamentals and test rigs to leakage, wear, friction and power, reliability, and special designs. This text is comprised of nine chapters; the first of which gives a general overview of seals, including various types of seals and their applications. Attention then turns to the fundamentals of seal design, with emphasis on six requirements that must be considered: sealing effectiveness, length of life, reliability, power consumption, space requirements, and c

Installation for producing sealed radioactive sources; Installation de fabrication de sources radioactives scellees

Energy Technology Data Exchange (ETDEWEB)

Fradin, J; Hayoun, C [Commissariat a l' Energie Atomique, 91 - Saclay (France). Centre d' Etudes Nucleaires

1969-07-01

This installation has been designed and built for producing sealed sources of fission elements: caesium 137, strontium 90, promethium 147, ruthenium 106 and cerium 144 in particular. The installation consists of sealed and protected cells, each being assigned to a particular production. The safety and the operational reliability of the equipment are the principal considerations which have governed this work. The report describes the installation and, in particular, the apparatus used as well as the various control devices. In conclusion, a review as presented of six years operation. (authors) [French] Cette installation a ete concue et realisee pour effectuer des fabrications de sources scellees d'elements de fission: caesium 137 - strontium 90 - promethium 147 - ruthenium 106 - cerium 144 en particulier. L'installation est composee de cellules etanches et protegees, chacune d'elles etant affectee a une fabrication particuliere. La securite et la surete de fonctionnement de l'ensemble sont parmi les elements principaux qui ont guide l'etude. Le rapport decrit l'installation et plus particulierement l'appareillage utilise ainsi que les divers controles et commandes. Le bilan de fonctionnement apres 6 ans d'exploitation sert de conclusion. (auteurs)

Installation for producing sealed radioactive sources; Installation de fabrication de sources radioactives scellees

Energy Technology Data Exchange (ETDEWEB)

Fradin, J.; Hayoun, C. [Commissariat a l' Energie Atomique, 91 - Saclay (France). Centre d' Etudes Nucleaires

1969-07-01

This installation has been designed and built for producing sealed sources of fission elements: caesium 137, strontium 90, promethium 147, ruthenium 106 and cerium 144 in particular. The installation consists of sealed and protected cells, each being assigned to a particular production. The safety and the operational reliability of the equipment are the principal considerations which have governed this work. The report describes the installation and, in particular, the apparatus used as well as the various control devices. In conclusion, a review as presented of six years operation. (authors) [French] Cette installation a ete concue et realisee pour effectuer des fabrications de sources scellees d'elements de fission: caesium 137 - strontium 90 - promethium 147 - ruthenium 106 - cerium 144 en particulier. L'installation est composee de cellules etanches et protegees, chacune d'elles etant affectee a une fabrication particuliere. La securite et la surete de fonctionnement de l'ensemble sont parmi les elements principaux qui ont guide l'etude. Le rapport decrit l'installation et plus particulierement l'appareillage utilise ainsi que les divers controles et commandes. Le bilan de fonctionnement apres 6 ans d'exploitation sert de conclusion. (auteurs)

Distribution of sealed sources in use or stored by user on-site in Republic of Bulgaria

International Nuclear Information System (INIS)

Simeonov, G.

2001-01-01

Full text: Distribution of the sealed sources (SS) in use or stored by user on-site in Republic of Bulgaria has been determined by using the categorization system proposed by Institut National des Radioelements (IRE), Belgium. The criteria used to categorize the SS were the handling and monitoring equipment needed for dismantling, checking and treatment of spent sealed sources (SSS) before storage and/or final disposal. The categorization system was proposed as a basis for estimation of the needs of equipment for the new treatment and storage facility for SSS in the site of Novi Han radioactive waste repository. The categorization used to evaluate the distribution of SS in use or stored by user on-site is shown in Table I. Sealed sources are widely used in Bulgaria for industrial, medical, domestic and scientific purposes. Presently, the list of registered users of sealed beta-gamma and neutron SS consists of 387 industrial users, 78 research and control users and 14 medical users. In addition there are 48 registered users of Pu-239 static eliminators and an estimated number shows about 1000 users of Pu-239, Am- 241 or Kr-85 sources in smoke detectors. Wide range of activities with SS is controlled by CUEAPP, as license is required for use and/or storage by user of every single source. An electronic data base of the licenses for use of atomic energy is operated by CUAEPP. The investigation covered the sealed sources registered in the data base. The number of sources in different categories, their use and typical activity have been determined. The same approach has been used separately for sealed sources in use, as well as for spent sources stored by user on-site. Special attention has been paid to high activity gamma-sources used in teletherapy and irradiators, as their activities were corrected for radioactive decay (reference date: March 2001); the exact location and conditions of use or storage of every such source were established. As a result of the

Quality assurance program plan for FRG sealed isotopic heat sources project (C-229)

International Nuclear Information System (INIS)

Tanke, J.M.

1997-01-01

This QAPP implements the Quality Assurance Program Plan for the FRG Sealed Isotopic Heat Sources Project (C-229). The heat source will be relocated from the 324 Building and placed in interim storage at the Central Waste Complex (CWC)

Sources management; La gestion des sources

Energy Technology Data Exchange (ETDEWEB)

Mansoux, H.; Gourmelon; Scanff, P.; Fournet, F. [Institut de Radioprotection et de Surete Nucleaire, 92 - Fontenay-aux-Roses (France); Murith, Ch. [Office Federal de la SantePublique (Switzerland); Saint-Paul, N. [NOVAR, 75 - Paris (France); Colson, P. [Electricite de France (EDF/DPN), 93 - Saint-Denis (France); Jouve, A.; Feron, F. [Direction Generale de al Surete Nucleaire et de la Radioprotection, 75 - Paris (France); Haranger, D. [Electricite de France (EDF), 75 - Paris (France); Mathieu, P. [Institut Pasteur, 75 - Paris (France); Paycha, F. [CHU Louis Mourier, Unitede Medecine Nucleaire Assistance Publique-Hopitaux de Paris, 92 - Colombes (France); Israel, S. [CEGELEC NDT et la gestion des sources radioactives (France); Auboiroux, B. [APAVE (France); Chartier, P. [DRIRE de Basse-Normandie, Div. Surete Nucleaire et Radioprotection, 14 - Caen (France)

2005-07-01

Organized by the section of technical protection of the French society of radiation protection ( S.F.R.P.), these two days had for objective to review the evolution of the rule relative to the sources of ionising radiations 'sealed and unsealed radioactive sources, electric generators'. They addressed all the actors concerned by the implementation of the new regulatory system in the different sectors of activities ( research, medicine and industry): Authorities, manufacturers, and suppliers of sources, holders and users, bodies involved in the approval of sources, carriers. (N.C.)

Storage of low-level radioactive waste and regulatory control of sealed sources in Finland

International Nuclear Information System (INIS)

Rahola, T.; Markkanen, M.

2006-01-01

This paper is concentrated on the non nuclear low-level radioactive waste. The cornerstone for maintaining radioactive sources under control in Finland is that all practices involving sources are subject to authorization and all licensing information, including information on each individual source, are entered into a register which is continuously updated based on applications and notifications received from the licenses. Experiences during the past twenty years have shown that source-specific records of sources combined with regular inspections at the places of use have prevented efficiency losing control over sealed radioactive sources. The current capacity in the interim storage for State owned waste is not adequate for all used sealed sources and other small user waste which are currently kept in the possession of the licensees. Thus, expansion of the storage capacity and other options for taking care of the small user waste is under consideration. (N.C.)

Diagnosis of Catalyst Cooler and Riser in RFCC using Sealed gamma-ray Source

International Nuclear Information System (INIS)

Kim, Jin Seop; Kim, Jong Bum; Jung, Sung Hee; Kim, Jae Ho

2005-12-01

With a quantitative growth of the petroleum industry, a lot of budget are spent for the maintenance and repairs of facilities related to the process annually. Among them, the RFCC(residual fluid catalytic cracking) is a highly value-added unit which converts gas oil and heavier streams to lighter, more valuable products such as propylene, gasoline by an injection of atmospheric residue into the fluided catalyst. In this study, field experiments were performed to analyze the reasons of an abnormal operation in the catalyst cooler and the catalyst riser belonged to the RFCC unit respectively and to estimate the amount of seriousness using sealed gamma-ray source( 60 Co). The catalyst cooler functions cooling for the regeneration of a catalyst, which will be used to a new media in the RFCC unit. The catalyst riser, while, plays an important part in transporting to next cyclotron steps by mixing of an oil, steam and a catalyst mechanically. The purposes of this study is what was the condition of catalyst flow pattern and whether the coke was produced in an inside process or not. Gamma radiation counts were measured by the detector(NaI) positioned outside the pipe-wall diametrically opposite to the gamma source with a regular space. From the results, the section different from the distribution pattern of nearby catalyst in a facility was found. And this became the definitive information to a process operator. Diagnosis technique using gamma radiation source is proved to be the effective and reliable method in providing information on the media distribution in a facility

Global threat reduction initiative efforts to address transportation challenges associated with the recovery of disused radioactive sealed sources - 10460

International Nuclear Information System (INIS)

Whitworth, Julie; Abeyta, Cristy L.; Griffin, Justin M.; Matzke, James L.; Pearson, Michael W.; Cuthbertson, Abigail; Rawl, Richard; Singley, Paul

2010-01-01

Proper disposition of disused radioactive sources is essential for their safe and secure management and necessary to preclude their use in malicious activities. Without affordable, timely transportation options, disused sealed sources remain in storage at hundreds of sites throughout the country and around the world. While secure storage is a temporary measure, the longer sources remain disused or unwanted the chances increase that they will become unsecured or abandoned. The Global Threat Reduction Initiative's Off-Site Source Recovery Project (GTRIlOSRP), recovers thousands of disused and unwanted sealed sources annually as part of GTRl's larger mission to reduce and protect high risk nuclear and radiological materials located at civilian sites worldwide. Faced with decreasing availability of certified transportation containers to support movement of disused and unwanted neutron- and beta/gamma-emitting radioactive sealed sources, GTRIlOSRP has initiated actions to ensure the continued success of the project in timely recovery and management of sealed radioactive sources. Efforts described in this paper to enhance transportation capabilities include: (sm b ullet) Addition of authorized content to existing and planned Type B containers to support the movement of non-special form and other Type B-quantity sealed sources; (sm b ullet) Procurement of vendor services for the design, development, testing and certification of a new Type B container to support transportation of irradiators, teletherapy heads or sources removed from these devices using remote handling capabilities such as the IAEA portable hot cell facility; (sm b ullet) Expansion of shielded Type A container inventory for transportation of gamma-emitting sources in activity ranges requiring use of shielding for conformity with transportation requirements; (sm b ullet) Approval of the S300 Type A fissile container for transport of Pu-239 sealed sources internationally; (sm b ullet) Technology transfer of

Procedure to carry out leakage test in beta radiation sealed sources emitters of {sup 90}Sr/{sup 90}Y; Procedimiento para realizar prueba de fuga en fuentes selladas de radiacion beta emisoras de {sup 90}Sr/{sup 90}Y

Energy Technology Data Exchange (ETDEWEB)

Alvarez R, J. T., E-mail: trinidad.alvarez@inin.gob.m [ININ, Departamento de Metrologia de Radiaciones Ionizantes, Laboratorio Secundario de Calibracion Dosimetrica, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

2010-09-15

In the alpha-beta room of the Secondary Laboratory of Dosimetric Calibration of the Metrology Department of Ionizing Radiations ophthalmic applicators are calibrated in absorbed dose terms in water D{sub w}; these applicators, basically are emitter sealed sources of pure beta radiation of {sup 90}Sr / {sup 90}Y. Concretely, the laboratory quality system indicates to use the established procedure for the calibration of these sources, which establishes the requirement of to carry out a leakage test, before to calibrate the source. However, in the Laboratory leakage test certificates sent by specialized companies in radiological protection services have been received, in which are used gamma spectrometry equipment s for beta radiation leakage tests, since it is not reliable to detect pure beta radiation with a scintillating detector with NaI crystal, (because it could detect the braking radiation produced in the detector). Therefore the Laboratory has had to verify the results of the tests with a correct technique, with the purpose of determining the presence of sources with their altered integrity and radioactive material leakage. The objective of this work is to describe a technique for beta activity measurement - of the standard ISO 7503, part 1 (1988) - and its application with a detector Gm plane (type pankage) in the realization of leakage tests in emitter sources of pure beta radiation, inside the mark of quality assurance indicated by the report ICRU 76. (Author)

Disposal of disused sealed sources and approach for safety assessment of near surface disposal facilities (national practice of Ukraine)

International Nuclear Information System (INIS)

Alekseeva, Z.; Letuchy, A.; Tkachenko, N.V.

2003-01-01

The main sources of wastes are 13 units of nuclear power plants under operation at 4 NPP sites (operational wastes and spent sealed sources), uranium-mining industry, area of Chernobyl exclusion zone contaminated as a result of ChNPP accident, and over 8000 small users of sources of ionising radiation in different fields of scientific, medical and industrial applications. The management of spent sources is carried out basing on the technology from the early sixties. In accordance with this scheme accepted sources are disposed of either in the near surface concrete vaults or in borehole facilities of typical design. Radioisotope devices and gamma units are placed into near surface vaults and sealed sources in capsules into borehole repositories respectively. Isotope content of radwaste in the repositories is multifarious including Co-60, Cs-137, Sr-90, Ir-192, Tl-204, Po-210, Ra-226, Pu-239, Am-241, H-3, Cf-252. A new programme for waste management has been adopted. It envisions the modifying of the 'Radon' facilities for long-term storage safety assessment and relocation of respective types of waste in 'Vector' repositories.Vector Complex will be built in the site which is located within the exclusion zone 10Km SW of the Chernobyl NPP. In Vector Complex two types of disposal facilities are designed to be in operation: 1) Near surface repositories for short lived LLRW and ILRW disposal in reinforced concrete containers. Repositories will be provided with multi layer waterproofing barriers - concrete slab on layer composed of mixture of sand and clay. Every layer of radwaste is supposed to be filled with 1cm clay layer following disposal; 2) Repositories for disposal of bulky radioactive waste without cans into concrete vaults. Approaches to safety assessment are discussed. Safety criteria for waste disposal in near surface repositories are established in Radiation Protection Standards (NRBU-97) and Addendum 'Radiation protection against sources of potential exposure

FRG sealed isotopic heat sources project (C-229) project management plan

International Nuclear Information System (INIS)

Metcalf, I.L.

1997-01-01

This Project Management Plan defines the cost, scope, schedule, organizational responsibilities, and work breakdown structure for the removal of the Federal Republic of Germany (FRG) Sealed Isotopic Heat Sources from the 324 Building and placed in interim storage at the Central Waste Complex (CWC)

Cover gas seals. 11 - FFTF-LMFBR seal-test program, January-March 1974

International Nuclear Information System (INIS)

Kurzeka, W.; Oliva, R.; Welch, F.

1974-01-01

The objectives of this program are to: (1) conduct static and dynamic tests to demonstrate or determine the mechanical performance of full-size (cross section) FFTF fuel transfer machine and reactor vessel head seals intended for use in a sodium vapor - inert gas environment, (2) demonstrate that these FFTF seals or new seal configuration provide acceptable fission product and cover gas retention capabilities at LMFBR Clinch River Plant operating environmental conditions other than radiation, and (3) develop improved seals and seal technology for the LMFBR Clinch River Plant to support the national objective to reduce all atmospheric contaminations to low levels

Structural and Shielding Safety of a Transport Package for Radioisotope Sealed Source Assembly

Energy Technology Data Exchange (ETDEWEB)

Seo, Kiseog; Cho, Ilje; Kim, Donghak [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

2006-07-01

As some kinds of radioisotope (RI) sealed source are produced by HANARO research reactor, a demand of RI transport package is increasing gradually. Foreign countries, which produce the various RIs, have the intrinsic model of the RI transport package. It is necessary to develop a RI and its transport package simultaneously. It is difficult to design a shielding part for this transport package because the passage for this source assembly should be provided from the center of shielding part to the outside of the package. In order to endure the accident conditions such as a 9 m drop and puncture, this transport package consists of the guide tubes, a gamma shield and a shock absorber. This paper describe that a shielding and structural safety of RI sealed source transport package are evaluated under the accident conditions.

Structural and Shielding Safety of a Transport Package for Radioisotope Sealed Source Assembly

International Nuclear Information System (INIS)

Seo, Kiseog; Cho, Ilje; Kim, Donghak

2006-01-01

As some kinds of radioisotope (RI) sealed source are produced by HANARO research reactor, a demand of RI transport package is increasing gradually. Foreign countries, which produce the various RIs, have the intrinsic model of the RI transport package. It is necessary to develop a RI and its transport package simultaneously. It is difficult to design a shielding part for this transport package because the passage for this source assembly should be provided from the center of shielding part to the outside of the package. In order to endure the accident conditions such as a 9 m drop and puncture, this transport package consists of the guide tubes, a gamma shield and a shock absorber. This paper describe that a shielding and structural safety of RI sealed source transport package are evaluated under the accident conditions

Stabilization of radionuclides applied in radiation sources

International Nuclear Information System (INIS)

Mielcarski, M.

1989-01-01

An attempt of comprehensive treatment of problems connected with the production of sealed radiation sources is made. In the introductory part of this work the basic information and definitions are contained. The classification systems currently applied are discussed. Attention was paid to the main fields of application. The methods of stabilization of radionuclides used for preparing radiation sources are discussed. The results of own investigations are presented, comprising the adsorption of some radionuclides on anodic Al 2 O 3 layers, stabilization in glazes and enamels, and the preparation of radioactive ceramics. In the adsorption investigations, these problems were considered as predominant which could form the basis for technological solutions. The results obtained allowed to establish the most favourable conditions of performing the process of stabilization by the use of this technique. In the case of radioactive enamels, the effect of glass composition on the yield of ionization has been investigated. Lowering of the content of radioactive component with simultaneous preserving the useful ionization ability was considered as being important. The mechanism of the observed increase of ionization caused by some inactive glass components is discussed. As concerns radioactive ceramics, a simplified method for preparing the ceramic core of cesium-137 sources is presented. This synthesis is based on the thermal transformation of moulded zeolite pellets into radioactive pollucite. Practical usefulness of different methods for the stabilization is discussed with emphasis given to those elaborated and applied in Poland. 131 refs., 37 figs., 20 tabs. (author)

Testing of neutron-irradiated ceramic-to-metal seals

International Nuclear Information System (INIS)

Brown, R.D.; Clinard, F.W. Jr.; Lopez, M.R.; Martinez, H.; Romero, T.J.; Cook, J.H.; Barr, H.N.; Hittman, F.

1990-01-01

This paper reports on ceramic-to-metal seals prepared by sputtering a titanium metallizing layer onto ceramic disks and then brazing to metal tubes. The ceramics used were alumina, MACOR, spinel, AlON, and a mixture of Al 2 O 3 and Si 3 N 4 . Except for the MACOR, which was brazed to a titanium tube, the ceramics were brazed to niobium tubes. The seals were leak tested and then sent to Los Alamos National Laboratory, where they were irradiated using the spallation neutron source at the Los Alamos Meson Physics Facility. Following irradiation for ∼ 90 days to a fluence of 2.8 x 10 23 n/m 2 , the samples were moved to hot cells and again leak tested. Only the MACOR samples showed any measurable leaks. One set of samples was then pressurized to 6.9 MPa (1000 psi) and subsequently leak tested. No leaks were found. Bursting the seals required hydrostatic pressures of at least 34 MPa (5000 psi). The high seal strength and few leaks indicate that ceramic-to-metal seals can resist radiation-induced degradation

UY 102 standard use of sealed sources in radiation source implants: approve for the Industry Energy and Mining Ministry 28/6/2002 Resolution

International Nuclear Information System (INIS)

2002-01-01

Establish minimal requires for radiological safety applied to use of the solid radio actives sources with therapeutic purposes in application radiation source implants in surface area and intra cavities

Shielding design of disposal container for disused sealed radioactive source

Energy Technology Data Exchange (ETDEWEB)

Kim, Suk Hoon; Kim, Ju Youl [FNC Technology Co., Yongin (Korea, Republic of)

2017-06-15

Disused Sealed Radioactive Sources (DSRSs), which are stored temporally in the centralized storage facility of Korea Radioactive Waste Agency (KORAD), will be disposed of in the low- and intermediate-level radioactive waste disposal facility located in Wolsong. Accordingly, the future plan on DSRS disposal should be established as soon as possible in connection with the construction and operation plan of disposal facility. In this study, as part of developing the systematic management plan, the radiation shielding analysis for three types of disposal container was performed for all kinds of radionuclides (excluding mixed sources) contained in DSRSs generated from domestic area using MicroShield and MCNP5 codes in consideration of the preliminary post-closure safety assessment result for disposal options, source-specific characteristics, and etc. In accordance with the analysis result, thickness of inner container for general disposal container and dimensions (i.e. diameter and height) of inner capsule for two types of special disposal container were determined as 3 mm, OD40×H120 mm (for type 1), and OD100× H240 mm (for type 2), respectively. These values were reflected in the conceptual design of DSRS disposal container, and the structural integrity of each container was confrmed through the structural analysis carried out separately from this study. Given the shielding and structural analysis results, the conceptual design derived from this study sufficiently fulfills the technical standards in force and the design performance level. And consequently, it is judged that the safe management for DSRSs to be disposed of is achieved by utilizing the disposal container with the conceptual design devised.

Shielding design of disposal container for disused sealed radioactive source

International Nuclear Information System (INIS)

Kim, Suk Hoon; Kim, Ju Youl

2017-01-01

Disused Sealed Radioactive Sources (DSRSs), which are stored temporally in the centralized storage facility of Korea Radioactive Waste Agency (KORAD), will be disposed of in the low- and intermediate-level radioactive waste disposal facility located in Wolsong. Accordingly, the future plan on DSRS disposal should be established as soon as possible in connection with the construction and operation plan of disposal facility. In this study, as part of developing the systematic management plan, the radiation shielding analysis for three types of disposal container was performed for all kinds of radionuclides (excluding mixed sources) contained in DSRSs generated from domestic area using MicroShield and MCNP5 codes in consideration of the preliminary post-closure safety assessment result for disposal options, source-specific characteristics, and etc. In accordance with the analysis result, thickness of inner container for general disposal container and dimensions (i.e. diameter and height) of inner capsule for two types of special disposal container were determined as 3 mm, OD40×H120 mm (for type 1), and OD100× H240 mm (for type 2), respectively. These values were reflected in the conceptual design of DSRS disposal container, and the structural integrity of each container was confrmed through the structural analysis carried out separately from this study. Given the shielding and structural analysis results, the conceptual design derived from this study sufficiently fulfills the technical standards in force and the design performance level. And consequently, it is judged that the safe management for DSRSs to be disposed of is achieved by utilizing the disposal container with the conceptual design devised

Sources management

International Nuclear Information System (INIS)

Mansoux, H.; Gourmelon; Scanff, P.; Fournet, F.; Murith, Ch.; Saint-Paul, N.; Colson, P.; Jouve, A.; Feron, F.; Haranger, D.; Mathieu, P.; Paycha, F.; Israel, S.; Auboiroux, B.; Chartier, P.

2005-01-01

Organized by the section of technical protection of the French society of radiation protection ( S.F.R.P.), these two days had for objective to review the evolution of the rule relative to the sources of ionising radiations 'sealed and unsealed radioactive sources, electric generators'. They addressed all the actors concerned by the implementation of the new regulatory system in the different sectors of activities ( research, medicine and industry): Authorities, manufacturers, and suppliers of sources, holders and users, bodies involved in the approval of sources, carriers. (N.C.)

Handling of radioactive sources in Ecuador

International Nuclear Information System (INIS)

Benitez, Manuel

2000-01-01

This document describes the following aspects: sealed and unsealed radioactive sources, radiation detectors, personnel and area monitoring, surface pollution, radioactive wastes control and radioactive sources transferring. (The author)

The management and disposal of sealed sources in France

International Nuclear Information System (INIS)

Drogou, A.

2005-01-01

The utilisation of sealed sources is very widespread in France, both in the medical and industrial fields. The rules for the management and retrieval of the sources are defined in the Decree of 4 April 2002. The principle of the retrieval of the sources is reliant on the supplier who is obliged to take back these sources. Financial guarantee systems have consequently been established to provide compensation for any failure by the supplier to take back the sources. The problems today in France are the absence of a disposal route and the management of the orphan sources. These have been integrated into the drawing up of the National Waste Management Plan (PNGDR) issued by the Minister for the Environment. Certain ideas and principles for the disposal of the sources have already been presented: Development of the principles of justification and recycling, development of disposal routes, development of a retrieval system for orphan sources; the importance of the establishment of financial guarantees for all the sources, the importance of consistency between the European regulations in order to have a simple return to the supplier in the case of imported sources. (author)

UHV seal studies for the advanced photon source storage ring vacuum system

International Nuclear Information System (INIS)

Gonczy, J.D.; Ferry, R.J.; Niemann, R.C.; Roop, B.

1991-01-01

The Advanced Photon Source (APS) Storage Ring Vacuum Chambers (SRVC) are constructed of aluminum. The chamber design incorporates aluminum alloy 2219-T87 Conflat flanges welded to an aluminum alloy 6063-T5 extruded chamber body. Vacuum connections to the aluminum Conflat chamber flanges are by means of 304 stainless steel Conflat flanges. To evaluate the Conflat seal assemblies relative to vacuum bake cycles, a Conflat Bake Test Assembly (CBTA) was constructed, and thermal cycling tests were performed between room temperature and 150 degrees C on both stainless steel to aluminum Conflat assemblies and aluminum to aluminum Conflat assemblies. A Helicoflex Bake Test Assembly (HBTA) was similarly constructed to evaluate Helicoflex seals. Both Conflat and Helicoflex seals were studied in a SRVC Sector String Test arrangement of five SRVC sections. The CBTA, HBTA and SRVC tests and their results are reported. 3 refs., 2 figs., 2 tabs

Ionizing radiation, radiation sources, radiation exposure, radiation effects. Pt. 2

International Nuclear Information System (INIS)

Schultz, E.

1985-01-01

Part 2 deals with radiation exposure due to artificial radiation sources. The article describes X-ray diagnosis complete with an analysis of major methods, nuclear-medical diagnosis, percutaneous radiation therapy, isotope therapy, radiation from industrial generation of nucler energy and other sources of ionizing radiation. In conclusion, the authors attempt to asses total dose, genetically significant dose and various hazards of total radiation exposure by means of a summation of all radiation impacts. (orig./WU) [de

Management of spent sealed radioactive sources in the European Union

International Nuclear Information System (INIS)

Cecille, L.; Taylor, D.

2000-01-01

For several years, the European Commission (EC) has been active in the field of spent sealed radioactive sources (SSRS) to improve management schemes and to prepare Euratom Directives that will impact on national legislation and regulatory schemes in European Member States (MS). The main safety issues related to the management of SSRS are described and recommendations made are presented. Additional projects are outlined. (author)

Radioactive sealed sources: Reasonable accountability, exemption, and licensing activity thresholds -- A technical basis

International Nuclear Information System (INIS)

Lee, D.W.; Shingleton, K.L.

1996-01-01

Perhaps owing to their small size and portability, some radiation accidents/incidents have involved radioactive sealed sources (RSSs). As a result, programs for the control and accountability of RSSs have come to be recommended and emplaced that essentially require RSSs to be controlled in a manner different from bulk, unsealed radioactive material. Crucially determining the total number of RSSs for which manpower-intensive radiation protection surveillance is provided is the individual RSS activity above which such surveillance is required and below which such effort is not considered cost effective. Individual RSS activity thresholds are typically determined through scenarios which impart a chosen internal or external limiting dose to Reference Man under specified exposure conditions. The resultant RSS threshold activity levels have meaning commensurate with the assumed scenario exposure parameters, i.e., if they are realistic and technically based. A review of how the Department of Energy (DOE), the International Atomic Energy Agency (IAEA), and the Nuclear Regulatory Commission (NRC) have determined their respective accountability, exemption, and licensing threshold activity values is provided. Finally, a fully explained method using references readily available to practicing health physicists is developed using realistic, technically-based calculation parameters by which RSS threshold activities may be locally generated

Reducing the risk from radioactive sources

International Nuclear Information System (INIS)

MacKenzie, C.

2006-01-01

Each year the IAEA receives reports of serious injuries or deaths due to misuse or accidents involving sealed radioactive sources. Sealed radioactive sources are used widely in medicine, industry, and agriculture - by doctors to treat cancer, by radiographers to check welds in pipelines, or by specialists to irradiate food to prevent it from spoiling, for example. If these sources are lost or improperly discarded, a serious accident may result. In addition, the security of sealed sources has become a growing concern, particularly the potential that such a source could be used as a radioactive dispersal device or 'dirty bomb'. Preventing the loss or theft of sealed radioactive sources reduces both the risk of accidents and the risk that such sources could become an instrument of misuse. In most countries, radioactive materials and activities that produce radiation are regulated. Those working with sealed radioactive sources are required not just to have proper credentials, but also the needed training and support to deal with unexpected circumstances that may arise when a source is used. Despite these measures, accidents involving sealed sources continue to be reported to the IAEA. Among its many activities to improve the safety and security of sealed sources, the IAEA has been investigating the root causes of major accidents since the 1980s and publishing the findings so that others can learn from them. This information needs to be in the hands of those whose actions and decisions can reduce accidents by preventing a lost source from making it's way into scrap metal. The IAEA has also developed an international catalogue of sealed radioactive sources, and provides assistance to countries to safely contain sources no longer in use. To raise awareness, a Sealed Radioactive Sources Toolkit was issued that focuses on the long-term issues in safely and securely managing radioactive sealed sources. The target audiences are government agencies, radioactive sealed source

A vacuum-sealed, gigawatt-class, repetitively pulsed high-power microwave source

Science.gov (United States)

Xun, Tao; Fan, Yu-wei; Yang, Han-wu; Zhang, Zi-cheng; Chen, Dong-qun; Zhang, Jian-de

2017-06-01

A compact L-band sealed-tube magnetically insulated transmission line oscillator (MILO) has been developed that does not require bulky external vacuum pump for repetitive operations. This device with a ceramic insulated vacuum interface, a carbon fiber array cathode, and non-evaporable getters has a base vacuum pressure in the low 10-6 Pa range. A dynamic 3-D Monte-Carlo model for the molecular flow movement and collision was setup for the MILO chamber. The pulse desorption, gas evolution, and pressure distribution were exactly simulated. In the 5 Hz repetition rate experiments, using a 600 kV diode voltage and 48 kA beam current, the average radiated microwave power for 25 shots is about 3.4 GW in 45 ns pulse duration. The maximum equilibrium pressure is below 4.0 × 10-2 Pa, and no pulse shortening limitations are observed during the repetitive test in the sealed-tube condition.

Spent sealed radium sources conditioning in Latin America

International Nuclear Information System (INIS)

Mourao, R.P.

1999-01-01

The management of spent sealed sources is considered by the International Atomic Energy Agency (IAEA) one of the greatest challenges faced by nuclear authorities today, especially in developing countries. One of the Agency's initiatives to tackle this problem is the Spent Radium Sources Conditioning Project, a worldwide project relying on the regional co-operation between countries. A team from the Brazilian nuclear research institute Centro de Desenvolvimento da Tecnologia Nuclear (CDTN) was chosen as the expert team to carry out the operations in Latin America; since December 1996 radium sources have been safely conditioned in Uruguay, Nicaragua, Guatemala, Ecuador and Paraguay. A Quality Assurance Program was established, encompassing the qualification of the capsule welding process, written operational procedures referring to all major steps of the operation, calibration of monitors and information retrievability. A 200L carbon steel drum-based packaging concept was used to condition the sources, its cavity being designed to receive the lead shield device containing stainless steel capsules with the radium sources. As a result of these operations, a total amount of 2,897 mg of needles, tubes, medical applicators, standard sources for calibration, lightning rods, secondary wastes and contaminated objects were stored in proper conditions and are now under control of the nuclear authorities of the visited countries

Spent sealed radium sources conditioning in Latin America

International Nuclear Information System (INIS)

Mourao, Rogerio Pimenta

1999-01-01

The management of spent sealed sources is considered by the IAEA one of the greatest challenges faced by nuclear authorities today, especially in developing countries. One of the Agency's initiatives to tackle this problem is the 'Spent Radium Sources Conditioning Project', a worldwide project relying on the regional cooperation between countries. A CDTN team was chooses as the expert team to carry out the operations in Latin America; since Dec 96 radium sources have been safely conditioned in Uruguay, Nicaragua, Guatemala and Ecuador. A Quality Assurance Program was established, encompassing the qualification of the capsule welding process, written operational procedures referring to all major steps of the operation, calibration of monitors and information retrievability. A 200L carbon steel drum-based packaging concept was used to condition the sources, its cavity being designed to receive the lead shield device containing stainless steel capsules with the radium sources. As a result of these operations, a total amount of 2,629 mg (approx. 98 GBq) of needles, tubes, medical applicators, standard sources for calibration, lightning rods, secondary wastes (generated during the operations) and contaminated objects were stored in proper conditions and are now under control, of the nuclear authorities of the visited countries. (author)

Ionizing radiation sources: very diversified means, multiple applications and a changing regulatory environment. Conference proceedings

International Nuclear Information System (INIS)

2011-11-01

This document brings together the available presentations given at the conference organised by the French society of radiation protection about ionizing radiation source means, applications and regulatory environment. Twenty eight presentations (slides) are compiled in this document and deal with: 1 - Overview of sources - some quantitative data from the national inventory of ionizing radiation sources (Yann Billarand, IRSN); 2 - Overview of sources (Jerome Fradin, ASN); 3 - Regulatory framework (Sylvie Rodde, ASN); 4 - Alternatives to Iridium radiography - the case of pressure devices at the manufacturing stage (Henri Walaszek, Cetim; Bruno Kowalski, Welding Institute); 5 - Dosimetric stakes of medical scanner examinations (Jean-Louis Greffe, Charleroi hospital of Medical University); 6 - The removal of ionic smoke detectors (Bruno Charpentier, ASN); 7 - Joint-activity and reciprocal liabilities - Organisation of labour risk prevention in case of companies joint-activity (Paulo Pinto, DGT); 8 - Consideration of gamma-graphic testing in the organization of a unit outage activities (Jean-Gabriel Leonard, EDF); 9 - Radiological risk control at a closed and independent work field (Stephane Sartelet, Areva); 10 - Incidents and accidents status and typology (Pascale Scanff, IRSN); 11 - Regional overview of radiation protection significant events (Philippe Menechal, ASN); 12 - Incident leading to a tritium contamination in and urban area - consequences and experience feedback (Laurence Fusil, CEA); 13 - Experience feedback - loss of sealing of a calibration source (Philippe Mougnard, Areva); 14 - Blocking incident of a 60 Co source (Bruno Delille, Salvarem); 15 - Triggering of gantry's alarm: status of findings (Philippe Prat, Syctom); 16 - Non-medical electric devices: regulatory changes (Sophie Dagois, IRSN; Jerome Fradin, ASN); 17 - Evaluation of the dose equivalent rate in pulsed fields: method proposed by the IRSN and implementation test (Laurent Donadille, IRSN

Vacuum seals design and testing for a linear accelerator of the National Spallation Neutron Source

Energy Technology Data Exchange (ETDEWEB)

Z. Chen; C. Gautier; F. Hemez; N. K. Bultman

2000-02-01

Vacuum seals are very important to ensure that the Spallation Neutron Source (SNS) Linac has an optimum vacuum system. The vacuum joints between flanges must have reliable seals to minimize the leak rate and meet vacuum and electrical requirements. In addition, it is desirable to simplify the installation and thereby also simplify the maintenance required. This report summarizes an investigation of the metal vacuum seals that include the metal C-seal, Energized Spring seal, Helcoflex Copper Delta seal, Aluminum Delta seal, delta seal with limiting ring, and the prototype of the copper diamond seals. The report also contains the material certifications, design, finite element analysis, and testing for all of these seals. It is a valuable reference for any vacuum system design. To evaluate the suitability of several types of metal seals for use in the SNS Linac and to determine the torque applied on the bolts, a series of vacuum leak rate tests on the metal seals have been completed at Los Alamos Laboratory. A copper plated flange, using the same type of delta seal that was used for testing with the stainless steel flange, has also been studied and tested. A vacuum seal is desired that requires significantly less loading than a standard ConFlat flange with a copper gasket for the coupling cavity assembly. To save the intersegment space the authors use thinner flanges in the design. The leak rate of the thin ConFlat flange with a copper gasket is a baseline for the vacuum test on all seals and thin flanges. A finite element analysis of a long coupling cavity flange with a copper delta seal has been performed in order to confirm the design of the long coupling cavity flange and the welded area of a cavity body with the flange. This analysis is also necessary to predict a potential deformation of the cavity under the combined force of atmospheric pressure and the seating load of the seal. Modeling of this assembly has been achieved using both HKS/Abaqus and COSMOS

Vacuum seals design and testing for a linear accelerator of the National Spallation Neutron Source

International Nuclear Information System (INIS)

Chen, Z.; Gautier, C.; Hemez, F.; Bultman, N.K.

2000-01-01

Vacuum seals are very important to ensure that the Spallation Neutron Source (SNS) Linac has an optimum vacuum system. The vacuum joints between flanges must have reliable seals to minimize the leak rate and meet vacuum and electrical requirements. In addition, it is desirable to simplify the installation and thereby also simplify the maintenance required. This report summarizes an investigation of the metal vacuum seals that include the metal C-seal, Energized Spring seal, Helcoflex Copper Delta seal, Aluminum Delta seal, delta seal with limiting ring, and the prototype of the copper diamond seals. The report also contains the material certifications, design, finite element analysis, and testing for all of these seals. It is a valuable reference for any vacuum system design. To evaluate the suitability of several types of metal seals for use in the SNS Linac and to determine the torque applied on the bolts, a series of vacuum leak rate tests on the metal seals have been completed at Los Alamos Laboratory. A copper plated flange, using the same type of delta seal that was used for testing with the stainless steel flange, has also been studied and tested. A vacuum seal is desired that requires significantly less loading than a standard ConFlat flange with a copper gasket for the coupling cavity assembly. To save the intersegment space the authors use thinner flanges in the design. The leak rate of the thin ConFlat flange with a copper gasket is a baseline for the vacuum test on all seals and thin flanges. A finite element analysis of a long coupling cavity flange with a copper delta seal has been performed in order to confirm the design of the long coupling cavity flange and the welded area of a cavity body with the flange. This analysis is also necessary to predict a potential deformation of the cavity under the combined force of atmospheric pressure and the seating load of the seal. Modeling of this assembly has been achieved using both HKS/Abaqus and COSMOS

Special Analysis for the Disposal of the Materials and Energy Corporation Sealed Sources at the Area 5 Radioactive Waste Management Site

Energy Technology Data Exchange (ETDEWEB)

Shott, Gregory [National Security Technologies, LLC. (NSTec), Mercury, NV (United States)

2017-05-15

This special analysis (SA) evaluates whether the Materials and Energy Corporation (M&EC) Sealed Source waste stream (PERM000000036, Revision 0) is suitable for shallow land burial (SLB) at the Area 5 Radioactive Waste Management Site (RWMS) on the Nevada National Security Site (NNSS). Disposal of the M&EC Sealed Source waste meets all U.S. Department of Energy (DOE) Manual DOE M 435.1-1, “Radioactive Waste Management Manual,” Chapter IV, Section P performance objectives (DOE 1999). The M&EC Sealed Source waste stream is recommended for acceptance without conditions.

The radioisotopes and radiations program

International Nuclear Information System (INIS)

1982-01-01

This program of the National Atomic Energy Commission of Argentina refers to the application and production of radionuclides, their compounds and sealed sources. The applications are carried out in the medical, agricultural, cattle raising and industrial areas and in other engineering branches. The sub-program corresponding to the production of radioactive materials includes the production of radioisotopes and of sealed sources, and an engineering service for radioactive materials production and handling facilities. The sub-program of applications is performed through several groups or laboratories in charge of the biological and technological applications, intensive radiation sources, radiation dosimetry and training of personnel or of potential users of radioactive material. Furthermore, several aspects about technology transfer, technical assistance, manpower training courses and scholarships are analyzed. Finally, some legal aspects about the use of radioisotopes and radiations in Argentina are pointed out. (M.E.L.) [es

The technique on handling radiation

International Nuclear Information System (INIS)

1997-11-01

This book describes measurement of radiation and handling radiation. The first part deals with measurement of radiation. The contents of this part are characteristic on measurement technique of radiation, radiation detector, measurement of energy spectrum, measurement of radioactivity, measurement for a level of radiation and county's statistics on radiation. The second parts explains handling radiation with treating of sealed radioisotope, treating unsealed source and radiation shield.

Pillow seal system at the BigRIPS separator

Energy Technology Data Exchange (ETDEWEB)

Tanaka, K., E-mail: ktanaka@riken.jp; Inabe, N.; Yoshida, K.; Kusaka, K.; Kubo, T.

2013-12-15

Highlights: • Pillow seal system has been installed for a high-intensity RI-beam facility at RIKEN. • It is aimed at facilitating remote maintenance under high residual radiation. • Local radiation shields are integrated with one of the pillow seals. • Pillow seals have been aligned to the beam axis within 1mm accuracy. • A leakage rate of 10{sup –9} Pa m{sup 3}/s has been achieved with our pillow seal system. -- Abstract: We have designed and installed a pillow seal system for the BigRIPS fragment separator at the RIKEN Radioactive Isotope Beam Factory (RIBF) to facilitate remote maintenance in a radioactive environment. The pillow seal system is a device to connect a vacuum chamber and a beam tube. It allows quick attachment and detachment of vacuum connections in the BigRIPS separator and consists of a double diaphragm with a differential pumping system. The leakage rate achieved with this system is as low as 10{sup –9} Pa m{sup 3}/s. We have also designed and installed a local radiation-shielding system, integrated with the pillow seal system, to protect the superconducting magnets and to reduce the heat load on the cryogenic system. We present an overview of the pillow seal and the local shielding systems.

Soil Monitor: an open source web application for real-time soil sealing monitoring and assessment

Science.gov (United States)

Langella, Giuliano; Basile, Angelo; Giannecchini, Simone; Iamarino, Michela; Munafò, Michele; Terribile, Fabio

2016-04-01

Soil sealing is one of the most important causes of land degradation and desertification. In Europe, soil covered by impermeable materials has increased by about 80% from the Second World War till nowadays, while population has only grown by one third. There is an increasing concern at the high political levels about the need to attenuate imperviousness itself and its effects on soil functions. European Commission promulgated a roadmap (COM(2011) 571) by which the net land take would be zero by 2050. Furthermore, European Commission also published a report in 2011 providing best practices and guidelines for limiting soil sealing and imperviousness. In this scenario, we developed an open source and an open source based Soil Sealing Geospatial Cyber Infrastructure (SS-GCI) named as "Soil Monitor". This tool merges a webGIS with parallel geospatial computation in a fast and dynamic fashion in order to provide real-time assessments of soil sealing at high spatial resolution (20 meters and below) over the whole Italy. Common open source webGIS packages are used to implement both the data management and visualization infrastructures, such as GeoServer and MapStore. The high-speed geospatial computation is ensured by a GPU parallelism using the CUDA (Computing Unified Device Architecture) framework by NVIDIA®. This kind of parallelism required the writing - from scratch - all codes needed to fulfil the geospatial computation built behind the soil sealing toolbox. The combination of GPU computing with webGIS infrastructures is relatively novel and required particular attention at the Java-CUDA programming interface. As a result, Soil Monitor is smart because it can perform very high time-consuming calculations (querying for instance an Italian administrative region as area of interest) in less than one minute. The web application is embedded in a web browser and nothing must be installed before using it. Potentially everybody can use it, but the main targets are the

Final report of the project Encapsulated Sources

International Nuclear Information System (INIS)

Kops, J.A.M.M.; Kicken, P.J.H.

2003-11-01

Literature dealing with risks and quality assurance of sealed radioactive sources, as welt as internationally used exemption levels (radiation exposure below which regulatory control is considered to be not needed) has been studied. The achieved views are compared with the Dutch practice by means of interviews with some users and suppliers of sealed sources. It appears that the risks of sealed sources occur mainly in the period after use. Often, disposal is postponed, which may result into loss of radiological management. Due to negligence or theft, disused sources can disappear in municipal waste or scrap, causing unwanted exposure of members of the public. Internationally, also fear is growing for misuse of radioactive sources by terrorists for the production of dirty bombs. In ISO 2919 adequate quality criteria and corresponding tests are described. Mostly, sealed sources have a quality certificate in accordance with ISO 2919. However, suppliers nor users are aware of any quality assurance during the total supply chain. Because the supply chain is complex and international, it is recommended to stimulate a European approach to achieve a quality assurance system. Guidelines, based on internationally used exemption levels, are proposed for unlicensed use of sealed sources with radio-activity levels above the release levels given in the Ionising Radiation Regulations of June 2001 (Besluit stralingsbescherming). The recommended levels are coupled with the level of quality assurance in the supply chain. This approach will stimulate suppliers to improve the quality assurance. As a result, a reduction of administrative costs can be coupled to an improvement of radiological conditions [nl

On the evaluation of rectangular plane-extended sources and their associated radiation fields

International Nuclear Information System (INIS)

Oner, Feda

2007-01-01

The objective of this paper is to provide an efficient and reliable analytical procedure for the evaluation of rectangular plane-extended sources and their associated radiation fields. Integrals with integer and non-integer values appear in the evaluation of the radiation field distribution. The latter results from a homogeneous rectangular plane target bombarded by hollow-cylindrical ion beams, the elementary areas anisotropically emitting in non-dispersive media, and fast neutrons produced in non-dispersive media by sealed-off neutron generating tubes (NGT) in an axi-symmetric situation [Hubbell, J.H., Bach, R.L., Lamkin, J.C., 1960. Radiation from a rectangular source. J. Res. NBS 64C (2), 121-137; Hubbell, J.H., 1963a. A power series buildup factor formulation. Application to rectangular and offaxis disk source problems. J. Res. NBS 67C, 291-306, Hubbell, J.H., 1963b. Dose fields from plane sources using point-source data. Nucleonics 21 (8), 144-148; Timus et al., 2005a. Plane rectengular tritium target response to excitation by uniform distributed normal accelerated deuteron beam. Appl. Radiat. Isot. 63, 823-839; Timus et al., 2005b. Analytical characterization of radiation fields generated by certain witch-type distributed axi-symmetrical ion beams. Arab J. Nucl. Sci. Appl. 38(I) 253-264]. In these references, the resulting expressions are represented as infinite linear combinations of basic J q (a, b, z) integrals. With the help of relation for J q (a, b, z), we can evaluate the high terms of energy expressions, which have been proposed in the above-mentioned references. The extensive test calculations show that the proposed algorithm in this work is the most efficient one in practical computations

Development of sealed radioactive sources immobilized in epoxy resin for verification of detectors used in nuclear medicine

Energy Technology Data Exchange (ETDEWEB)

Tiezzi, Rodrigo; Rostelato, Maria Elisa C.M.; Nagatomi, Helio R.; Zeituni, Calos A.; Benega, Marcos A.G.; Souza, Daiane B. de; Costa, Osvaldo L. da; Souza, Carla D.; Rodrigues, Bruna T.; Souza, Anderson S. de; Peleias Junior, Fernando S.; Santos, Rafael Melo dos; Melo, Emerson Ronaldo de, E-mail: rktiezzi@gmail.com [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil); Karan Junior, Dib [Universidade de Sao Paulo (USP), Sao Paulo, SP (Brazil)

2015-07-01

The radioactive sealed sources are used in verification ionization chamber detectors, which measure the activity of radioisotopes used in several areas, such as in nuclear medicine. The measurement of the activity of radioisotopes must be made with accuracy, because it is administered to a patient. To ensure the proper functioning of the ionization chamber detectors, standardized tests are set by the International Atomic Energy Agency (IAEA) and the National Nuclear Energy Commission using sealed radioactive sources of Barium-133, Cesium-137 and Cobalt-57. The tests assess the accuracy, precision, reproducibility and linearity of response of the equipment. The focus of this work was the study and the development of these radioactive sources with standard Barium-133, Cesium-137 and Cobalt-57,using a polymer, in case commercial epoxy resin of diglycidyl ether of bisphenol A (DGEBA) and a curing agent based on modified polyamine diethylenetriamine (DETA), to immobilize the radioactive material. The polymeric matrix has the main function of fix and immobilize the radioactive contents not allowing them to leak within the technical limits required by the standards of radiological protection in the category of characteristics of a sealed source and additionally have the ability to retain the emanation of any gases that may be formed during the manufacture process and the useful life of this artifact. The manufacturing process of a sealed source standard consists of the potting ,into bottle standardized geometry, in fixed volume of a quantity of a polymeric matrix within which is added and dispersed homogeneously to need and exact amount in activity of the radioactive materials standards. Accordingly, a study was conducted for the choice of epoxy resin, analyzing its characteristics and properties. Studies and tests were performed, examining the maximum solubility of the resin in water (acidic solution, simulating the conditions of radioactive solution), loss of mechanical

Declaration and authorization forms for the fabrication, distribution or use of radioactive sources or electric generators of ionizing radiation

International Nuclear Information System (INIS)

2010-01-01

This document gathers all the forms to be completed when declaring or when asking for an authorization for the fabrication, retailing or use of radioactive sources or electric equipment generating ionizing radiation. These forms can concern all domains (use of sealed radioactive sources, possession and use of a particle accelerator or of radionuclides, import or export of radionuclides or of products containing radionuclides), or the use of such materials or equipment in the medical sector, or the fabrication and use in industry or research, or in user's guides for radioactive sources

Tuned sources of submillimetre radiation

International Nuclear Information System (INIS)

Berezhnyj, V.L.

1981-01-01

The main present directions of development of sources of frequency coherent tuned radiation of electromagnetic waves in the submillimeter range: nonlinear mixing of different frequencies; semiconductor lasers; molecular lasers with optical pumping; relativistic electron beams in a magnetic field as submillimeter radiation sources; submillimeter radiation sources on the basis of SHF classical electrovacuum devices - are considered. The designs of generator systems and their specifications are presented. The main parameters of electromagnetic radiation of different sources, such as: power, stability, frequency, tuning range - are presented. The methods of improving sources and electromagnetic radiation parameters are proposed. The examples of possible applications of submillimeter radiation in different spheres of science and technology are given [ru

Radionuclides in seals and porpoises in the coastal waters around the UK

International Nuclear Information System (INIS)

Watson, W.S.; Sumner, D.J.; Baker, J.R.; Kennedy, S.; Reid, R.; Robinson, I.

1999-01-01

It has been suggested that marine predators be assessed for biologically relevant contamination levels because of their trophic position. Accordingly, in studying radioactive contamination in the marine environment around the UK, tissues from seals and porpoises have been chosen. Liver and muscle tissue from dead seals and porpoises found stranded around the UK coast have been analysed for the following radionuclides: 134Cs, 137Cs, 238Pu, 239Pu+ 240 Pu. Multifactor analysis of variance indicated that, for radiocaesium, there was no significant difference for harbour seals, grey seals or porpoises in terms of species or gender; however, the tissue activity concentration increased with body weight and decreased with distance from Sellafield, the major nuclear reprocessing plant in the UK. The levels of radiocaesium in muscle were higher than those in liver, while there appeared to be a concentration factor of approximately 3-4 for muscle radiocaesium when compared to radiocaesium levels reported for fish, the main food source of the marine mammals under study. Approximate radiation dose calculations indicated that the average dose from radiocaesium was less than 10% of the dose from the naturally occurring radioisotope of potassium, 40K. The highest tissue activity concentration for plutonium of 0.037 Bq/kg (239Pu+ 240 Pu) was detected in a grey seal stranded at Rathlin Island in Northern Ireland. Calculation of approximate radiation doses from plutonium contamination showed that, as with radiocaesium, the average dose was small compared with that from 40K. In summary, the radiocaesium contamination in seals and porpoises decreased with distance from Sellafield indicating that the BNF plc processing plant was the major source of the contamination. The marine mammals concentrated radiocaesium from their environment by a factor of 300 relative to the concentration in seawater indicating the value of using marine mammal tissue to measure radiocaesium contamination in

Standard review plan for applications for sealed source and device evaluations and registrations

International Nuclear Information System (INIS)

1996-11-01

The purpose of this document is to provide the reviewer of a request for a sealed source or device safety evaluation with the information and materials necessary to make a determination that the product is acceptable for licensing purposes. It provides the reviewer with a listing of the applicable regulations and industry standards, policies affecting evaluation and registration, certain administrative procedures to be followed, and information on how to perform the evaluation and write the registration certificate. Standard review plans are prepared for the guidance of the Office of Nuclear Material Safety and Safeguards staff responsible for the review of a sealed source or device application. This document is made available to the public as part of the Commission's policy to inform the nuclear industry and the general public of regulatory procedures and policies. Standard review plans are not substitutes for regulatory guides or the Commission's regulations and compliance with them is not required

Standard review plan for applications for sealed source and device evaluations and registrations

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-11-01

The purpose of this document is to provide the reviewer of a request for a sealed source or device safety evaluation with the information and materials necessary to make a determination that the product is acceptable for licensing purposes. It provides the reviewer with a listing of the applicable regulations and industry standards, policies affecting evaluation and registration, certain administrative procedures to be followed, and information on how to perform the evaluation and write the registration certificate. Standard review plans are prepared for the guidance of the Office of Nuclear Material Safety and Safeguards staff responsible for the review of a sealed source or device application. This document is made available to the public as part of the Commission`s policy to inform the nuclear industry and the general public of regulatory procedures and policies. Standard review plans are not substitutes for regulatory guides or the Commission`s regulations and compliance with them is not required.

Radiological Characterization Technical Report on Californium-252 Sealed Source Transuranic Debris Waste for the Off-Site Source Recovery Project at Los Alamos National Laboratory

Energy Technology Data Exchange (ETDEWEB)

Feldman, Alexander [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2014-04-24

This document describes the development and approach for the radiological characterization of Cf-252 sealed sources for shipment to the Waste Isolation Pilot Plant. The report combines information on the nuclear material content of each individual source (mass or activity and date of manufacture) with information and data on the radionuclide distributions within the originating nuclear material. This approach allows for complete and accurate characterization of the waste container without the need to take additional measurements. The radionuclide uncertainties, developed from acceptable knowledge (AK) information regarding the source material, are applied to the summed activities in the drum. The AK information used in the characterization of Cf-252 sealed sources has been qualified by the peer review process, which has been reviewed and accepted by the Environmental Protection Agency.

Identification of radioisotopes in bulks with disused sealed sources using a high performance portable spectrometer

International Nuclear Information System (INIS)

Zapata, Luis; Mallaupoma, Mario

2013-01-01

Sealed radioactive sources are widely used in many industrial applications, and after completing its useful life must be managed as radioactive wastes. One of the most common problems of disused sealed radioactive sources is that many times they lack proper identification and their certificates of manufacture. In that context, it is necessary to identify them, prior to any other management step. There are a number of techniques which can be used; however they are sometimes complex. This technical paper shows a simple way for its identification using the InSpector 1000 monitor which allows to know their energy spectra. These modern instruments and detectors have been obtained thanks to the Project Global Threat Reduction Initiative (Programa de Reduccion de Amenazas) between IPEN and the US DOE. (authors).

Temporary fire sealing of penetrations on TFTR

International Nuclear Information System (INIS)

Hondorp, H.L.

1981-02-01

The radiation shielding provided for TFTR for D-D and D-T operation will be penetrated by numerous electrical and mechanical services. Eventually, these penetrations will have to be sealed to provide the required fire resistance, tritium sealability, pressure integrity and radiation attenuation. For the initial hydrogen operation, however, fire sealing of the penetrations in the walls and floor is the primary concern. This report provides a discussion of the required and desirable properties of a temporary seal which can be used to seal these penetrations for the hydrogen operation and then subsequently be removed and replaced as required for the D-D and D-T operations. Several candidate designs are discussed and evaluated and recommendations are made for specific applications

Factors affecting the repeatability of gamma camera calibration for quantitative imaging applications using a sealed source

International Nuclear Information System (INIS)

Anizan, N; Wahl, R L; Frey, E C; Wang, H; Zhou, X C

2015-01-01

Several applications in nuclear medicine require absolute activity quantification of single photon emission computed tomography images. Obtaining a repeatable calibration factor that converts voxel values to activity units is essential for these applications. Because source preparation and measurement of the source activity using a radionuclide activity meter are potential sources of variability, this work investigated instrumentation and acquisition factors affecting repeatability using planar acquisition of sealed sources. The calibration factor was calculated for different acquisition and geometry conditions to evaluate the effect of the source size, lateral position of the source in the camera field-of-view (FOV), source-to-camera distance (SCD), and variability over time using sealed Ba-133 sources. A small region of interest (ROI) based on the source dimensions and collimator resolution was investigated to decrease the background effect. A statistical analysis with a mixed-effects model was used to evaluate quantitatively the effect of each variable on the global calibration factor variability. A variation of 1 cm in the measurement of the SCD from the assumed distance of 17 cm led to a variation of 1–2% in the calibration factor measurement using a small disc source (0.4 cm diameter) and less than 1% with a larger rod source (2.9 cm diameter). The lateral position of the source in the FOV and the variability over time had small impacts on calibration factor variability. The residual error component was well estimated by Poisson noise. Repeatability of better than 1% in a calibration factor measurement using a planar acquisition of a sealed source can be reasonably achieved. The best reproducibility was obtained with the largest source with a count rate much higher than the average background in the ROI, and when the SCD was positioned within 5 mm of the desired position. In this case, calibration source variability was limited by the quantum

10 years and 20,000 sources: the offsite source recovery project

Energy Technology Data Exchange (ETDEWEB)

Whitworth, Julia R [Los Alamos National Laboratory; Abeyta, Cristy L [Los Alamos National Laboratory; Pearson, Michael W [Los Alamos National Laboratory

2009-01-01

The Global Threat Reduction Initiative's (GTRI) Offsite Source Recovery Project (OSRP) has been recovering excess and unwanted sealed sources for ten years. In January 2009, GTRI announced that the project had recovered 20,000 sealed radioactive sources. This project grew out of early efforts at Los Alamos National Laboratory (LANL) to recover and disposition excess Plutonium-239 (Pu-239) sealed sources that were distributed in the 1960s and 1970s under the Atoms for Peace Program. Sealed source recovery was initially considered a waste management activity, as evidenced by its initial organization under the Department of Energy's (DOE's) Environmental Management (EM) program. After the terrorist attacks of 2001, however, the interagency community began to recognize the threat posed by excess and unwanted radiological material, particularly those that could not be disposed at the end of their useful life. After being transferred to the National Nuclear Security Administration (NNSA) to be part of GTRI, OSRP's mission was expanded to include not only material that would be classified as Greater-than-Class-C (GTCC) when it became waste, but also any other materials that might be a 'national security consideration.' This paper discusses OSRP's history, recovery operations, expansion to accept high-activity beta-gamma-emitting sealed sources and devices and foreign-possessed sources, and more recent efforts such as cooperative projects with the Council on Radiation Control Program Directors (CRCPD) and involvement in GTRI's Search and Secure project. Current challenges and future work will also be discussed.

Incidents with hazardous radiation sources

International Nuclear Information System (INIS)

Schoenhacker, Stefan

2016-01-01

Incidents with hazardous radiation sources can occur in any country, even those without nuclear facilities. Preparedness for such incidents is supposed to fulfill globally agreed minimum standards. Incidents are categorized in incidents with licensed handling of radiation sources as for material testing, transport accidents of hazardous radiation sources, incidents with radionuclide batteries, incidents with satellites containing radioactive inventory, incidents wit not licensed handling of illegally acquired hazardous radiation sources. The emergency planning in Austria includes a differentiation according to the consequences: incidents with release of radioactive materials resulting in restricted contamination, incidents with release of radioactive materials resulting in local contamination, and incidents with the hazard of e@nhanced exposure due to the radiation source.

Environmental assessment for the relocation and storage of isotopic heat sources, Hanford Site, Richland, Washington

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-06-01

As part of a bilateral agreement between the Federal Minister for Research and Technology of the Federal Republic of Germany (FRG) and the DOE, Pacific Northwest National Laboratory (PNNL) developed processes for the treatment and immobilization of high-level radioactive waste. One element of this bilateral agreement was the production of sealed isotopic heat sources. During the mid-1980s, 30 sealed isotopic heat sources were manufactured. The sources contain a total of approximately 8.3 million curies consisting predominantly of cesium-137 and strontium-90 with trace amounts of transuranic contamination. Currently, the sources are stored in A-Cell of the 324 Building. Intense radiation fields from the sources are causing the cell windows and equipment to deteriorate. Originally, it was not intended to store the isotopic heat sources for this length of time in A-cell. The 34 isotopic heat sources are classified as remote handled transuranic wastes. Thirty-one of the isotopic heat sources are sealed, and seals on the three remaining isotopic heat sources have not been verified. However, a decision has been made to place the remaining three isotopic heat sources in the CASTOR cask(s). The Washington State Department of Health (WDOH) has concurred that isotopic heat sources with verified seals or those placed into CASTOR cask(s) can be considered sealed (no potential to emit radioactive air emissions) and are exempt from WAC Chapter 246-247, Radiation Protection-Air Emissions.

Environmental assessment for the relocation and storage of isotopic heat sources, Hanford Site, Richland, Washington

International Nuclear Information System (INIS)

1997-06-01

As part of a bilateral agreement between the Federal Minister for Research and Technology of the Federal Republic of Germany (FRG) and the DOE, Pacific Northwest National Laboratory (PNNL) developed processes for the treatment and immobilization of high-level radioactive waste. One element of this bilateral agreement was the production of sealed isotopic heat sources. During the mid-1980s, 30 sealed isotopic heat sources were manufactured. The sources contain a total of approximately 8.3 million curies consisting predominantly of cesium-137 and strontium-90 with trace amounts of transuranic contamination. Currently, the sources are stored in A-Cell of the 324 Building. Intense radiation fields from the sources are causing the cell windows and equipment to deteriorate. Originally, it was not intended to store the isotopic heat sources for this length of time in A-cell. The 34 isotopic heat sources are classified as remote handled transuranic wastes. Thirty-one of the isotopic heat sources are sealed, and seals on the three remaining isotopic heat sources have not been verified. However, a decision has been made to place the remaining three isotopic heat sources in the CASTOR cask(s). The Washington State Department of Health (WDOH) has concurred that isotopic heat sources with verified seals or those placed into CASTOR cask(s) can be considered sealed (no potential to emit radioactive air emissions) and are exempt from WAC Chapter 246-247, Radiation Protection-Air Emissions

Radiation protection procedures and dose to the staff in brachytherapy with permanent implant of the sources

International Nuclear Information System (INIS)

Tosi, G.; Cattani, F.

2002-01-01

The treatment of intra capsular prostate cancers with the permanent implantation of low energy sealed radioactive sources (''103 Pd-''125I) offers the same probability of curing the tumours as surgery and external-beam radiotherapy with a minimum incidence of unwanted side-effects. The first attempts of using sealed sources for treating prostate cancers go back to 1917, when Barringer reported the results obtained with the implant of ''236Ra needles. Beginning from that period the interest for prostate brachytherapy has shown a fluctuating trend, due especially to the technological possibilities and to the status of the alternative treatment modalities (surgery, external radiotherapy). The main reason of the substantial failure of brachytherapy as compared to the two other treatment modalities had two main causes: the energy, too high ( E≅ 840 keV), of γ-radiation emitted by ''226 Ra in equilibrium with its decay products and the lack of imaging techniques able to visualize with sufficient accuracy both the prostate and the arrangement, inside it, of the radioactive sources. The employ of low energy γ-emitting radionuclides began in 1974, when Whitmore et al. working at the Sloan Kettering Memorial Cancer Hospital of New York suggested the use of ''125 I sealed sources for the realisation of interstitial permanent implants. Also this attempt, though reducing the side effects typical of the surgical intervention (incontinence, impotence), did non give the expected results in terms of local control of the disease and, as a consequence, of the survival's length. This partial failure was attributed to the fact that, in most cases the dose distribution inside the target volume was not homogeneous, due to the inadequacy of the available imaging techniques used for checking the real position of the sources, during their manual insertion in the tissues. In the last ten years,however, great progresses have been made in the US i maging techniques, in the manufacture of

Regulation for radiation protection in applications of radiation sources

International Nuclear Information System (INIS)

Sonawane, Avinash U.

2016-01-01

Applications of ionising radiation in multifarious field are increasing in the country for the societal benefits. The national regulatory body ensures safety and security of radiation sources by enforcing provisions in the national law and other relevant rules issued under the principle law. In addition, the enforcement of detailed requirements contained in practice specific safety codes and standard and issuance of safety directives brings effectiveness in ensuring safe handling and secure management of radiation sources. The regulatory requirements for control over radiation sources throughout their life-cycle have evolved over the years from experience gained. Nevertheless, some of the regulatory activities which require special attention have been identified such as the development of regulation to deal with advance emerging radiation technology in applications of radiation in medicine and industry; sustaining continuity in ensuring human resource development programme; inspections of category 3 and 4 disused sources and their safe disposal; measures for controlling transboundary movement of radiation sources. The regulatory measures have been contemplated and are being enforced to deal with the above issues in an effective manner. The complete involvement of the management of radiation facilities, radiation workers and their commitment in establishing and maintaining safety and security culture is essential to handle the radiation sources safely and efficiently at all times

Synchrotron radiation sources

Energy Technology Data Exchange (ETDEWEB)

van Steenbergen, A.

1979-01-01

As a result of the exponential growth of the utilization of synchrotron radiation for research in the domain of the material sciences, atomic and molecular physics, biology and technology, a major construction activity has been generated towards new dedicated electron storage rings, designed optimally for synchrotron radiation applications, also, expansion programs are underway at the existing facilities, such as DORIS, SPEAR, and VEPP. In this report the basic properties of synchrotron radiation will be discussed, a short overview will be given of the existing and new facilities, some aspects of the optimization of a structure for a synchrotron radiation source will be discussed and the addition of wigglers and undulators for spectrum enhancement will be described. Finally, some parameters of an optimized synchrotron radiation source will be given.

Study and methodology development for quality control in the production process of iodine-125 radioactive sealed sources applied to brachytherapy

International Nuclear Information System (INIS)

Moura, Joao Augusto

2009-01-01

Today cancer is the second cause of death by disease in several countries, including Brazil. Excluding skin cancer, prostate cancer is the most incident in the population. Prostate tumor can be treated by several ways, including brachytherapy, which consists in introducing sealed radioactive sources (Iodine - 125 seeds) inside the tumor. The target region of treatment receives a high radiation dose, but healthy neighbor tissues receive a significantly reduced radiation dose. The seed is made of a welding sealed titanium capsule, 0.8 mm external diameter and 4.5 mm length, enclosing a 0.5 mm diameter silver wire with Iodine-125 adsorbed. After welded, the seeds have to be submitted to a leak test to prevent any radioactive material release. The aims of this work were: (a) the study of the different leakage test methods applied to radioactive seeds and recommended by the ISO 997820, (b) the choice of the appropriate method and (c) the flowchart determination of the process to be used during the seeds production. The essays exceeded the standards with the use of ultra-sound during immersion and the corresponding benefits to leakage detection. Best results were obtained with the immersion in distilled water at 20 degree C for 24 hours and distilled water at 70 degree C for 30 minutes. These methods will be used during seed production. The process flowchart has all the phases of the leakage tests according to the sequence determined in the experiments. (author)

Management of disused high-activity sealed radioactive sources: Opting for removal from the national territory

Energy Technology Data Exchange (ETDEWEB)

Mourão, Rogério Pimenta, E-mail: mouraor@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

2017-07-01

Since 2007 Brazil has been using the removal from its territory as a strategy for the management of sealed sources. Three campaigns have been carried out so far, each aiming at specific source types or categories. In the first of these campaigns in 2007, 126 neutron sources of American origin were repatriated to the USA, followed in 2010 by around 900 low activity sources (Categories 3 to 5, according to the IAEA classification system). Both operations were conducted by teams of the American institute Los Alamos National Laboratory. A third campaign, focused on high activity sources – essentially Cobalt-60 sources for teletherapy – was carried out between 2016 and 2017 and resulted in 81 spent high activity radioactive sources of American- and Canadian-origin been sent to Germany and the USA. This operation was carried out by a team of South Africa using a dedicated Mobile Hot Cell. The benefits to Brazil resulting from these operations are clear: increase in safety and security; availability of new precious storage space; less effort dedicated to the disused sealed sources storage; less space in the future borehole facility; financial gains in the selling or reuse of steel, lead and depleted uranium from the original shields. An overexposure incident occurred during the operation, in which a worker was exposed to a dose above the annual statutory limit. (author)

Safe handling of radiation sources

International Nuclear Information System (INIS)

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

2004-01-01

This chapter discussed the subjects related to the safe handling of radiation sources: type of radiation sources, method of use: transport within premises, transport outside premises; Disposal of Gamma Sources

Development of a ceramic tamper indicating seal: SRNL contributions

International Nuclear Information System (INIS)

Krementz, Dan; Brinkman, Kyle S.; Martinez-Rodriguez, Michael J.; Mendez-Torres, Adrian E.; Weeks, George E.

2013-01-01

Savannah River National Laboratory (SRNL) and Sandia National Laboratories (SNL) are collaborating on development of a Ceramic Seal, also sometimes designated the Intrinsically Tamper Indicating Ceramic Seal (ITICS), which is a tamper indicating seal for international safeguards applications. The Ceramic Seal is designed to be a replacement for metal loop seals that are currently used by the IAEA and other safeguards organizations. The Ceramic Seal has numerous features that enhance the security of the seal, including a frangible ceramic body, protective and tamper indicating coatings, an intrinsic unique identifier using Laser Surface Authentication, electronics incorporated into the seal that provide cryptographic seal authentication, and user-friendly seal wire capture. A second generation prototype of the seal is currently under development whose seal body is of Low Temperature Co-fired Ceramic (LTCC) construction. SRNL has developed the mechanical design of the seal in an iterative process incorporating comments from the SNL vulnerability review team. SRNL is developing fluorescent tamper indicating coatings, with recent development focusing on optimizing the durability of the coatings and working with a vendor to develop a method to apply coatings on a 3-D surface. SRNL performed a study on the effects of radiation on the electronics of the seal and possible radiation shielding techniques to minimize the effects. SRNL is also investigating implementation of Laser Surface Authentication (LSA) as a means of unique identification of each seal and the effects of the surface coatings on the LSA signature.

DEVELOPMENT OF A CERAMIC TAMPER INDICATING SEAL: SRNL CONTRIBUTIONS

Energy Technology Data Exchange (ETDEWEB)

Krementz, D.; Brinkman, K.; Martinez-Rodriguez, M.; Mendez-Torres, A.; Weeks, G.

2013-06-03

Savannah River National Laboratory (SRNL) and Sandia National Laboratories (SNL) are collaborating on development of a Ceramic Seal, also sometimes designated the Intrinsically Tamper Indicating Ceramic Seal (ITICS), which is a tamper indicating seal for international safeguards applications. The Ceramic Seal is designed to be a replacement for metal loop seals that are currently used by the IAEA and other safeguards organizations. The Ceramic Seal has numerous features that enhance the security of the seal, including a frangible ceramic body, protective and tamper indicating coatings, an intrinsic unique identifier using Laser Surface Authentication, electronics incorporated into the seal that provide cryptographic seal authentication, and user-friendly seal wire capture. A second generation prototype of the seal is currently under development whose seal body is of Low Temperature Co-fired Ceramic (LTCC) construction. SRNL has developed the mechanical design of the seal in an iterative process incorporating comments from the SNL vulnerability review team. SRNL is developing fluorescent tamper indicating coatings, with recent development focusing on optimizing the durability of the coatings and working with a vendor to develop a method to apply coatings on a 3-D surface. SRNL performed a study on the effects of radiation on the electronics of the seal and possible radiation shielding techniques to minimize the effects. SRNL is also investigating implementation of Laser Surface Authentication (LSA) as a means of unique identification of each seal and the effects of the surface coatings on the LSA signature.

Radioactivity determination of sealed pure beta-sources by surface dose measurements and Monte Carlo simulations

Energy Technology Data Exchange (ETDEWEB)

Choi, Chang Heon [Interdisciplinary Program in Radiation Applied Life Science, Seoul National University College of Medicine, Seoul (Korea, Republic of); Jung, Seongmoon [Program in Biomedical Radiation Sciences, Department of Transdisciplinary Studies, Graduate School of Convergence Science and Technology, Seoul National University, Seoul (Korea, Republic of); Choi, Kanghyuk; Son, Kwang-Jae; Lee, Jun Sig [Hanaro Applications Research, Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Ye, Sung-Joon, E-mail: sye@snu.ac.kr [Interdisciplinary Program in Radiation Applied Life Science, Seoul National University College of Medicine, Seoul (Korea, Republic of); Program in Biomedical Radiation Sciences, Department of Transdisciplinary Studies, Graduate School of Convergence Science and Technology, Seoul National University, Seoul (Korea, Republic of); Center for Convergence Research on Robotics, Advance Institutes of Convergence Technology, Seoul National University, Suwon (Korea, Republic of)

2016-04-21

This study aims to determine the activity of a sealed pure beta-source by measuring the surface dose rate using an extrapolation chamber. A conversion factor (cGy s{sup −1} Bq{sup −1}), which was defined as the ratio of surface dose rate to activity, can be calculated by Monte Carlo simulations of the extrapolation chamber measurement. To validate this hypothesis the certified activities of two standard pure beta-sources of Sr/Y-90 and Si/P-32 were compared with those determined by this method. In addition, a sealed test source of Sr/Y-90 was manufactured by the HANARO reactor group of KAERI (Korea Atomic Energy Research Institute) and used to further validate this method. The measured surface dose rates of the Sr/Y-90 and Si/P-32 standard sources were 4.615×10{sup −5} cGy s{sup −1} and 2.259×10{sup −5} cGy s{sup −1}, respectively. The calculated conversion factors of the two sources were 1.213×10{sup −8} cGy s{sup −1} Bq{sup −1} and 1.071×10{sup −8} cGy s{sup −1} Bq{sup −1}, respectively. Therefore, the activity of the standard Sr/Y-90 source was determined to be 3.995 kBq, which was 2.0% less than the certified value (4.077 kBq). For Si/P-32 the determined activity was 2.102 kBq, which was 6.6% larger than the certified activity (1.971 kBq). The activity of the Sr/Y-90 test source was determined to be 4.166 kBq, while the apparent activity reported by KAERI was 5.803 kBq. This large difference might be due to evaporation and diffusion of the source liquid during preparation and uncertainty in the amount of weighed aliquot of source liquid. The overall uncertainty involved in this method was determined to be 7.3%. We demonstrated that the activity of a sealed pure beta-source could be conveniently determined by complementary combination of measuring the surface dose rate and Monte Carlo simulations.

U Y 105 standard use of non sealed radioactive sources in nuclear medicine: approve for Industry energy and Mining Ministry 28/6/2002 Resolution

International Nuclear Information System (INIS)

2002-01-01

Establish minimal requirements radiological safety for use non sealed radioactive sources in nuclear medicine.The present standard is used in operation or nuclear medicine practices using non sealed radioactive sources with diagnostic and therapeutic purposes in vivo and in vitro

Ionizing radiations

International Nuclear Information System (INIS)

2009-01-01

After having recalled some fundamental notions and measurement units related to ionizing radiations, this document describes various aspects of natural and occupational exposures: exposure modes and sources, exposure levels, biological effects, health impacts. Then, it presents prevention principles aimed at, in an occupational context of use of radiation sources (nuclear industry excluded), reducing and managing these exposures: risk assessment, implementation of safety from the front end. Some practical cases illustrate the radiation protection approach. The legal and regulatory framework is presented: general notions, worker exposure, measures specific to some worker categories (pregnant and breast feeding women, young workers, temporary workers). A last part describes what is to be done in case of incident or accident (dissemination of radioactive substances from unsealed sources, anomaly occurring when using a generator or a sealed source, post-accident situation)

Sources of pulsed radiation

International Nuclear Information System (INIS)

Sauer, M.C. Jr.

1981-01-01

Characteristics of various sources of pulsed radiation are examined from the viewpoint of their importance to the radiation chemist, and some examples of uses of such sources are mentioned. A summary is given of the application of methods of physical dosimetry to pulsed sources, and the calibration of convenient chemical dosimeters by physical dosimetry is outlined. 7 figures, 1 table

Ionizing-radiation warning - Supplementary symbol

International Nuclear Information System (INIS)

2007-01-01

This International Standard specifies the symbol to warn of the presence of a dangerous level of ionizing radiation from a high-level sealed radioactive source that can cause death or serious injury if handled carelessly. This symbol is not intended to replace the basic ionizing radiation symbol [ISO 361, ISO 7010:2003, Table 1 (Reference number W003)], but to supplement it by providing further information on the danger associated with the source and the necessity for untrained or uninformed members of the public to stay away from it. This symbol is recommended for use with International Atomic Energy Agency (IAEA) Category 1, 2, and 3 sealed radioactive sources. These sources are defined by the IAEA as having the ability to cause death or serious injuries. The paper informs about scope, shape, proportions and colour of the symbol, and application of the symbol. An annex provides the technical specifications of the symbol

Development of sealed radioactive sources immobilized in epoxy resin for verification of detectors used in nuclear medicine

International Nuclear Information System (INIS)

Tiezzi, Rodrigo

2016-01-01

The radioactive sealed sources are used in verification ionization chamber detectors, which measure the activity of radioisotopes used in several areas, such as in nuclear medicine. The measurement of the activity of radioisotopes must be made with accuracy, because it is administered to a patient. To ensure the proper functioning of the ionization chamber detectors, standardized tests are set by the International Atomic Energy Agency (IAEA) and the National Nuclear Energy Commission using sealed radioactive sources of Barium-133, Cesium-137 and Cobalt-57. The tests assess the accuracy, precision, reproducibility and linearity of response of the equipment. The focus of this work was the study and the development of these radioactive sources with standard Barium-133 and Cesium-137,using a polymer, in case commercial epoxy resin of diglycidyl ether of bisphenol A (DGEBA) and a curing agent based on modified polyamine diethylenetriamine (DETA), to immobilize the radioactive material. The polymeric matrix has the main function of fix and immobilize the radioactive contents not allowing them to leak within the technical limits required by the standards of radiological protection in the category of characteristics of a sealed source and additionally have the ability to retain the emanation of any gases that may be formed during the manufacture process and the useful life of this artifact. The manufacturing process of a sealed source standard consists of the potting ,into bottle standardized geometry, in fixed volume of a quantity of a polymeric matrix within which is added and dispersed homogeneously to need and exact amount in activity of the radioactive materials standards. Accordingly, a study was conducted for the choice of epoxy resin, analyzing its characteristics and properties. Studies and tests were performed, examining the maximum miscibility of the resin with the water (acidic solution, simulating the conditions of radioactive solution), loss of mechanical and

Order of 25 March 1981 concerning the approval of special form radioactive materials in sealed sources

International Nuclear Information System (INIS)

1981-01-01

This order determines the models of sealed sources which constitute special form radioactive materials within the meaning of the Order of 24 November 1977 concerning the characteristics of such materials. (NEA) [fr

11-FFTF-LMFBR seal-test program, January-March 1976

International Nuclear Information System (INIS)

Steele, O.P. III; Horton, P.; Shimazaki, T.

1976-01-01

Current activities include providing CRBRP design information based on tests of the IVHM Inflatable Seal to CRBRP conditions, testing the CRBRP dip seal configuration to determine its performance characteristics, and delineating the effects of sodium and radiation environments on the efficiencies of various seal materials

Synchroton Radiation Sources

International Nuclear Information System (INIS)

Hulbert, S.L.; Williams, G.P.

1998-01-01

Synchrotron radiation is a very bright, broadband, polarized, pulsed source of light extending from the infrared to the x-ray region. It is an extremely important source of Vacuum Ultraviolet radiation. Brightness is defined as flux per unit area per unit solid angle and is normally a more important quantity than flux alone particularly in throughput limited applications which include those in which monochromators are used. It is well known from classical theory of electricity and magnetism that accelerating charges emit electromagnetic radiation. In the case of synchrotron radiation, relativistic electrons are accelerated in a circular orbit and emit electromagnetic radiation in a broad spectral range. The visible portion of this spectrum was first observed on April 24, 1947 at General Electric's Schenectady facility by Floyd Haber, a machinist working with the synchrotron team, although the first theoretical predictions were by Lienard in the latter part of the 1800's. An excellent early history with references was presented by Blewett and a history covering the development of the utilization of synchrotron radiation was presented by Hartman. Synchrotron radiation covers the entire electromagnetic spectrum from the infrared region through the visible, ultraviolet, and into the x-ray region up to energies of many 10's of kilovolts. If the charged particles are of low mass, such as electrons, and if they are traveling relativistically, the emitted radiation is very intense and highly collimated, with opening angles of the order of 1 milliradian. In electron storage rings there are three possible sources of synchrotron radiation; dipole (bending) magnets; wigglers, which act like a sequence of bending magnets with alternating polarities; and undulators, which are also multi-period alternating magnet systems but in which the beam deflections are small resulting in coherent interference of the emitted light

Special Analysis for the Disposal of the Neutron Products Incorporated Sealed Source Waste Stream at the Area 5 Radioactive Waste Management Site, Nevada National Security Site, Nye County, Nevada

Energy Technology Data Exchange (ETDEWEB)

None, None

2014-08-31

The purpose of this special analysis (SA) is to determine if the Neutron Products Incorporated (NPI) Sealed Sources waste stream (DRTK000000056, Revision 0) is suitable for disposal by shallow land burial (SLB) at the Area 5 Radioactive Waste Management Site (RWMS). The NPI Sealed Sources waste stream consists of 850 60Co sealed sources (Duratek [DRTK] 2013). The NPI Sealed Sources waste stream requires a special analysis (SA) because the waste stream 60Co activity concentration exceeds the Nevada National Security Site (NNSS) Waste Acceptance Criteria (WAC) Action Levels.

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)

Active Infrared Thermography for Seal Contamination Detection in Heat-Sealed Food Packaging

Directory of Open Access Journals (Sweden)

Karlien D’huys

2016-11-01

Full Text Available Packaging protects food products from environmental influences, assuring quality and safety throughout shelf life if properly performed. Packaging quality depends on the quality of the packaging material and of the closure or seal. A common problem possibly jeopardizing seal quality is the presence of seal contamination, which can cause a decreased seal strength, an increased packaging failure risk and leak formation. Therefore, early detection and removal of seal contaminated packages from the production chain is crucial. In this work, a pulsed-type active thermography method using the heated seal bars as an excitation source was studied for detecting seal contamination. Thermal image sequences of contaminated seals were recorded shortly after sealing. The detection performances of six thermal image processing methods, based on a single frame, a fit of the cooling profiles, thermal signal reconstruction, pulsed phase thermography, principal component thermography and a matched filter, were compared. High resolution digital images served as a reference to quantify seal contamination, and processed thermal images were mapped to these references. The lowest detection limit (equivalent diameter 0.60 mm was obtained for the method based on a fit of the cooling profiles. Moreover, the detection performance of this method did not depend strongly on the time after sealing at which recording of the thermal images was started, making it a robust and generally applicable method.

Radiation survey of aircraft and heavy machinery scrap

International Nuclear Information System (INIS)

Idriss, Hajo; Salih, Isam; Gumaa, Elsadig; Yassin, Abbas; Yousif, E.H.; Abdel Hamid, Saad Eldeen M.; Sam, A.K.

2012-01-01

This study was conducted primarily to survey aircraft and heavy machinery at 30 locations within Khartoum State using handheld radiation survey meters to detect and identify any radiation sources that might be present and to estimate radiation dose levels. The survey has resulted in detection of 16 sealed sources of 90 Sr and one of 226 Ra in aircraft scrap. Of course, 90 Sr sources are used in military aircraft as temperature sensors while 226 Ra is used for indicating fuel levels. These sources were found intact without spreading radioactivity contamination; however, none was detected in heavy machine scrap. The levels of radiation dose measured at 0.1 m from the source fall within the range of 25.1–40.2 μSv/h with an average value of 33.52±4.06 μSv/h. These orphan sources have been separated from the scrap, tested for possible leakage, conditioned and stored in waste management facility. The result of this study has revealed without doubt that the scrap constitute a serious source of public exposure and highlights the importance of legislation making radiation monitoring of scrap in the country mandatory before it is sold to metal industry for reprocessing. - Highlights: ► Sealed radioactive sources ( 90 Sr and 226 Ra) were detected in aircraft scrap. ► No source was detected in heavy machine scrap. ► Radiation dose measured at 0.1 m from the source can be used to estimate exposure to public. ► Monitoring of scrap was found to be useful for protection (from orphan sources).

Sealed ion accelerator tubes (survey)

International Nuclear Information System (INIS)

Voitsik, L.R.

1985-01-01

The first publications on developing commercial models of small-scale sealed accelerator tubes in which neutrons are generated appeared in the foreign press in 1954 to 1957; they were very brief and were advertising-oriented. The tubes were designed for neutron logging of oil wells instead of ampule neutron sources (Po + Be, Ra + Be). Later, instruments of this type began to be called neutron tubes from the resulting neutron radiation that they gave off. In Soviet Union a neutron tube was developed in 1958 in connection with the development of the pulsed neutron-neutron method of studying the geological profile of oil wells. At that time the tube developed was intended, in the view of its inventors, to replace standard isotope sources with constant neutron yield. A fairly detailed survey of neutron tubes was made in the studies. 8 refs., 8 figs

Exposure doses of nurses in the radiation therapy using sealed small radiation sources

Energy Technology Data Exchange (ETDEWEB)

Hatori, N; Yamakawa, K; Eda, T; Habu, T; Endo, H [Gunma Cancer Center Hospital (Japan)

1979-11-01

In radiation for malignant tumor, interstitial irradiation and/or intracavitary irradiations are performed in addition to external irradiation. The former two treatments are well applied for the tumors at head and neck region, especially carcinoma of the tongue and for that in gynecological tumor like carcinoma of the cervix. However, nurses are supposed to be irradiated during the treatment, as they help the handling of radiation sourses to insert or to pierce them directly into diseased parts. In this paper, we measured the relationship between working time of nurses for the treatment and exposure doses of nurses, using a thermoluminescence dosimeter, the exposure doses were approximately proportional to the working time, and 3-6 mR working time for a treatment in the cases of the diseases head and neck, and 4 mR working time for a treatment in the cases of gynecological diseases.

Exposure doses of nurses in the radiation therapy using sealed small radiation sources

International Nuclear Information System (INIS)

Hatori, Noboru; Yamakawa, Katsumi; Eda, Tetsuo; Habu, Takashi; Endo, Hiroshi

1979-01-01

In radiation for malignant tumor, interstitial irradiation and/or intracavitary irradiations are performed in addition to external irradiation. The former two treatments are well applied for the tumors at head and neck region, especially carcinoma of the tongue and for that in gynecological tumor like carcinoma of the cervix. However, nurses are supposed to be irradiated during the treatment, as they help the handling of radiation sourses to insert or to pierce them directly into diseased parts. In this paper, we measured the relationship between working time of nurses for the treatment and exposure doses of nurses, using a thermoluminescence dosimeter, the exposure doses were approximately proportional to the working time, and 3-6 mR working time for a treatment in the cases of the diseases head and neck, and 4 mR working time for a treatment in the cases of gynecological diseases. (author)

Radiation sources, radiation environment and risk level at Dubna

International Nuclear Information System (INIS)

Komochkov, M.M.

1991-01-01

The overall information about ionizing radiation sources, which form radiation environment and risk at Dubna, is introduced. Systematization of the measurement results is performed on the basis of the effective dose and losses of life expectancy. The contribution of different sources to total harm of Dubna inhabitants has been revealed. JINR sources carry in ∼ 4% from the total effective dose of natural and medicine radiation sources; the harm from them is much less than the harm from cigarette smoking. 18 refs.; 2 tabs

Conditioning of spent radiation sources in developing countries

International Nuclear Information System (INIS)

1990-01-01

This video presents the safe handling and conditioning of radioactive spent sealed sources when technological resources are limited and specialized equipment is not available. The process is divided into three phases which are demonstrated in detail: 1) Planning, including training; 2) Conditioning, which is the actual incorporation of the spent sources; and 3) Follow-up, which includes radiological control, documentation and safe storage

Radiation studies in the antiproton source

International Nuclear Information System (INIS)

Church, M.

1990-01-01

Experiment E760 has a lead glass (Pb-G) calorimeter situated in the antiproton source tunnel in the accumulator ring at location A50. This location is exposed to radiation from several sources during antiproton stacking operations. A series of radiation studies has been performed over the last two years to determine the sources of this radiation and as a result, some shielding has been installed in the antiproton source in order to protect the lead glass from radiation damage

Leakage test evaluation used for qualification of iodine-125 seeds sealing

International Nuclear Information System (INIS)

Feher, Anselmo; Rostelato, Maria E.C.M.; Zeituni, Carlos A.; Calvo, Wilson A.P.; Somessari, Samir L.; Moura, Joao A.; Moura, Eduardo S.; Souza, Carla D.; Rela, Paulo R.

2009-01-01

The prostate cancer is a problem of public health in Brazil, and the second cause of cancer deaths in men, exceeded only by lung cancer. Among the possible treatments available for prostate cancer is brachytherapy, in which small seeds containing Iodine-125 radioisotope are implanted in the prostate. The seed consists of a sealed titanium tube measuring 0.8 mm external diameter and 4.5 mm in length, containing a central silver wire with adsorbed Iodine-125. The tube sealing is made with titanium at the ends, using electric arc welding or laser process. This sealing must be leakage-resistant and free of cracks, therefore avoiding the Iodine-125 to deposit in the silver wire to escape and spread into the human body. To ensure this problem does not occur, rigorous leakage tests, in accordance with the standard Radiation protection - Sealed Radioactive Sources - leakage Test Methods - ISO 9978, should be applied. The aim of this study is to determine, implement and evaluate the leakage test to be used in the Iodine-125 seeds production, in order to qualify the sealing procedure. The standard ISO 9978 presents a list of tests to be carried out according to the type of source. The preferential methods for brachytherapy sources are soaking and helium. To assess the seeds leakage, the method of immersion test at room temperature was applied. The seeds are considered leakage-free if the detected activity does not exceed the 185 Bq (5 nCi). An Iodine standard was prepared and its value determined in a sodium iodide detector. A liquid scintillation counter was calibrated with the standard for seeds leakage tests. Forty-eight seeds were welded for these tests. (author)

Seals and sealing handbook

CERN Document Server

Flitney, Robert K

2014-01-01

Seals and Sealing Handbook, 6th Edition provides comprehensive coverage of sealing technology, bringing together information on all aspects of this area to enable you to make the right sealing choice. This includes detailed coverage on the seals applicable to static, rotary and reciprocating applications, the best materials to use in your sealing systems, and the legislature and regulations that may impact your sealing choices. Updated in line with current trends this updated reference provides the theory necessary for you to select the most appropriate seals for the job and with its 'Failur

Effective Regulatory Control of Radioactive Sources in Taiwan

International Nuclear Information System (INIS)

Liu, W.; Yuan, C.; Fan, S.; Su, S.

2004-01-01

Since the incident of radioactively contaminated buildings first surfaced in Taiwan in 1992, efforts have been made by AEC (Atomic Energy Council) of Taiwan to prevent recurrence of similar incidents involving radioactive materials and to achieve effective regulatory control over radioactive sources. The most important milestone is when AEC began to enforce IRPA he Ionizing Radiation Protection Act with the promulgation of 18 relevant regulations on Feb. 1, 2003. In order to enhance accountability of radioactive material and equipment capable of producing ionizing radiation, AEC develops and begins implementing a RPCS Radiation Protection Control System which is a powerful tool in controlling radiation safety and security. In addition, AEC develops a monthly registration program via internet, an o n-line reporting system f or owners/operators of radioactive sources, to improve monitoring of sealed sources (in-use and not-in-use). The registration requirement applies to 469 licensees possessing about 3,000 sealed sources in Taiwan. Because of the threat of orphan sources, AEC has made great efforts in preventing their contamination of construction steel material by establishing and enforcing the RPMMPIRCB Regulation for Preventive Measures and Management Plans for Incident of Radioactively Contaminated Buildings. To comply with this regulation, all 19 of Taiwan's steel factories with melting furnace have installed portal-type radiation detection system to monitor incoming scrap metal. (Author)

Categorization of radiation sources

International Nuclear Information System (INIS)

Antonova, M.

2000-01-01

Through one-parameter (factor) analysis it is proved a hypothesis that the value of a radiation source (RS) activity of an application correlates with the category (the rank) given to it by the IAEA categorization although it is based on other parameters of the RS applications (practices like devices with radiation sources in industry, science, medicine and agriculture). The principles of the new IAEA categorization, taking into account the potential harm the sources may cause and the necessary regulatory control, are described. (author)

Natural sources of ionizing radiations

International Nuclear Information System (INIS)

Marej, A.N.

1984-01-01

Natural sources of ionizing radiations are described in detail. The sources are subdivided into sources of extraterrestrial origin (cosmic radiation) and sources of terrestrial origin. Data on the concentration of different nuclides in rocks, various soils, ground waters, atmospheric air, tissues of plants and animals, various food stuffs are presented. The content of natural radionuclides in environmental objects, related to human activities, is discussed

Seal analysis technology for reactor pressure vessel

International Nuclear Information System (INIS)

Zheng Liangang; Zhang Liping; Yang Yu; Zang Fenggang

2009-01-01

There is the coolant with radiation, high temperature and high pressure in the reactor pressure vessel (RPV). It is closely correlated to RPV sealing capability whether the whole nuclear system work well or not. The aim of this paper is to study the seal analysis method and technology, such as the pre-tensioning of the bolt, elastoplastic contact and coupled technology of thermal and structure. The 3 D elastoplastic seal analysis method really and generally consider the loads and model the contact problem with friction between the contact plates. This method is easier than the specialized seal program and used widely. And it is more really than the 2 D seal analysis method. This 3 D elastoplastic seal analysis method has been successfully used in the design and analysis of RPV. (authors)

Endurance test report of rubber sealing materials for the containment vessel

International Nuclear Information System (INIS)

Yamamoto, R.; Watanabe, K.; Hanashima, K.

2015-01-01

In the event of a nuclear power plant accident such as a core meltdown and a cooling system failure, the containment contains radioactive materials released from the reactor pressure vessel to reduce the activity of the radioactive materials and the effects of radiation in the vicinity of the plant. Since high sealing performance and high pressure resistance are required of the containment, a silicone or EPDM rubber gasket with high heat and radiation resistance is used for the sealing of the sealing boundary of the containment. In recent years, it has been shown that a large amount of steam is released into the containment in the case of a severe accident. Consequently, radiation resistance at high temperature as well as steam resistance is required of the rubber gasket placed at the sealing boundary. However, the steam resistance of silicone rubber is not necessarily as good as that of EPDM rubber. Therefore, it is necessary to evaluate the sealing characteristics of rubber gaskets in such a degrading environment in a severe accident. O. Kato et al. [1] conducted a study on the degradation status of rubber gaskets and their application limits at high temperature. However, few studies have evaluated rubber gaskets in high-temperature radiation and steam environments. In this study, we degraded silicone rubber and EPDM rubber used for the containment in the high-temperature radiation and steam environments expected to occur in a severe accident and evaluated the useful life of the rubber as a sealing material by estimating the change in its performance as a sealing material from the change in permanent compressive strain in the rubber. (author)

Characterization of sealed radioactive sources. Uncertainty analysis to improve detection methods

International Nuclear Information System (INIS)

Cummings, D.G.; Sommers, J.D.; Adamic, M.L.; Jimenez, M.; Giglio, J.J.; Carney, K.P.

2009-01-01

A radioactive 137 Cs source has been analyzed for the radioactive parent 137 Cs and stable decay daughter 137 Ba. The ratio of the daughter to parent atoms is used to estimate the date when Cs was purified prior to source encapsulation (an 'age' since purification). The isotopes were analyzed by inductively coupled plasma mass spectrometry (ICP-MS) after chemical separation. In addition, Ba was analyzed by isotope dilution ICP-MS (ID-ICP-MS). A detailed error analysis of the mass spectrometric work has been undertaken to identify areas of improvement, as well as quantifying the effect the errors have on the 'age' determined. This paper reports an uncertainty analysis to identifying areas of improvement and alternative techniques that may reduce the uncertainties. In particular, work on isotope dilution using ICP-MS for the 'age' determination of sealed sources is presented. The results will be compared to the original work done using external standards to calibrate the ICP-MS instrument. (author)

Control of radiation sources in Japan

International Nuclear Information System (INIS)

Maki, S.

2001-01-01

The report refers to the regulations for radioactive material in force in Japan, and to the organizations with responsibilities for regulating radiation sources. An outline of the law regulating the use of radiation sources and radioactive materials is provided, including its scope, types of radiation sources under control, exemptions and the system of notification, authorization and inspection. The experience of Japan with orphan sources is presented in three different cases, and the measures carried out to store the orphan sources in safe conditions. (author)

30 CFR 75.337 - Construction and repair of seals.

Science.gov (United States)

2010-07-01

... sealed areas. (b) Prior to sealing, the mine operator shall— (1) Remove insulated cables, batteries, and other potential electric ignition sources from the area to be sealed when constructing seals, unless it... after April 18, 2008, the seal at the lowest elevation shall have a corrosion-resistant, non-metallic...

Searching for Orphan radiation sources

International Nuclear Information System (INIS)

Bystrov, Evgenij; Antonau, Uladzimir; Gurinovich, Uladzimir; Kazhamiakin, Valery; Petrov, Vitaly; Shulhovich, Heorhi; Tischenko, Siarhei

2008-01-01

Full text: The problem of orphan sources cannot be left unaddressed due high probability of accidental exposure and use of sources for terrorism. Search of objects of this kind is complex particularly when search territory is large. This requires devices capable of detecting sources, identifying their radionuclide composition, and correlating scan results to geographical coordinates and displaying results on a map. Spectral radiation scanner AT6101C can fulfill the objective of search for gamma and neutron radiation sources, radionuclide composition identification, correlation results to geographical coordinates and displaying results on a map. The scanner consists of gamma radiation scintillation detection unit based on NaI(Tl) crystal, neutron detection unit based on two He 3 counters, GPS receiver and portable ruggedized computer. Built-in and application software automates entire scan process, saving all results to memory for further analysis with visual representation of results as spectral information diagrams, count rate profile and gamma radiation dose rates on a geographical map. The scanner informs operator with voice messages on detection of radiation sources, identification result and other events. Scanner detection units and accessories are packed in a backpack. Weighing 7 kg, the scanner is human portable and can be used for scan inside cars. The scanner can also be used for radiation mapping and inspections. (author)

Radiation protection rules for the technical application of sealed radioactive sources

International Nuclear Information System (INIS)

1982-10-01

The standard is limited to operation containers and radiation equipment in which the radiation is made useful according to one or both of the following techniques for the application purpose: 1) by opening an aperture on the operation container without driving out the emitter (working position of the emitter in the operation container). 2) By driving out the emitter from the operation container within solid or flexible guide pipes (working position of the emitter outside the operation container). The regulations are not valid furthermore for operation containers and equipment which are to take up emitters with activities greater than 185 ps (5,000 Ci). (orig./HP) [de

Experience with synchrotron radiation sources

International Nuclear Information System (INIS)

Krinsky, S.

1987-01-01

The development of synchrotron radiation sources is discussed, emphasizing characteristics important for x-ray microscopy. Bending magnets, wigglers and undulators are considered as sources of radiation. Operating experience at the national Synchrotron Light Source on the VUV and XRAY storage rings is reviewed, with particular consideration given to achieved current and lifetime, transverse bunch dimensions, and orbit stability. 6 refs., 3 figs

The sources of radiation exposure

International Nuclear Information System (INIS)

Bennett, B.G.

1992-01-01

Radiation protection of workers and of members of the public requires an assessment of the various sources of exposure, their variations in time or under specific conditions or circumstances, and the possibilities for control or limitation. The United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR) has evaluated the various components of natural and man-made sources in some detail. Natural exposures form the largest component of radiation exposure of man. Variability in exposures depends on elevation, the concentrations of radionuclides in soil, food and water, the composition of building materials and the susceptibility of indoor spaces to radon build-up. Man-made sources have included exposures to fallout from atmospheric nuclear testing and discharged from nuclear fuel cycle installations in routine operations or in accidents. The other main source of radiation exposures of individuals is in medical diagnostic examinations and therapeutic treatments. (author)

Current approaches on the management of disused sealed sources in Bulgaria

International Nuclear Information System (INIS)

Benitez-Navarro, J. C.; Canizares, J.; Asuar, O.; Tapia, J.; Demireva, E.; Yordanova, O.; Stefanova, I.; Karadzhov, S.

2005-01-01

The main options for the safe management of existing Disused Sealed Radioactive Sources (DSRS) in Bulgaria are discussed. The specific installations for handling and conditioning of all type of DSRS are being designed. The necessary equipment and materials for all conditioning operations have been defined. As the final disposal route for the radioactive wastes in Bulgaria is not defined yet, the proposed conditioning process for the DSRS ensures that end-point disposal of DSRS is not jeopardized by actions taken at present. All the DSRS would be packaged in secure, safe, monitorable and retrievable manner for interim storage

Sources of radiation exposure - an overview

International Nuclear Information System (INIS)

Mason, G.C.

1990-01-01

Sources of radiation exposure are reviewed from the perspective of mining and milling of radioactive ores in Australia. The major sources of occupational and public exposure are identified and described, and exposures from mining and milling operations are discussed in the context of natural radiation sources and other sources arising from human activities. Most radiation exposure of humans comes from natural sources. About 80% of the world average of the effective dose equivalents received by individual people arises from natural radiation, with a further 15-20% coming from medical exposures*. Exposures results from human activities, such as mining and milling of radioactive ores, nuclear power generation, fallout from nuclear weapons testing and non-medical use of radioisotopes and X-rays, add less than 1% to the total. 9 refs., 4 tabs., 10 figs

Virtual Gamma Ray Radiation Sources through Neutron Radiative Capture

Energy Technology Data Exchange (ETDEWEB)

Scott Wilde, Raymond Keegan

2008-07-01

The countrate response of a gamma spectrometry system from a neutron radiation source behind a plane of moderating material doped with a nuclide of a large radiative neutron capture cross-section exhibits a countrate response analogous to a gamma radiation source at the same position from the detector. Using a planar, surface area of the neutron moderating material exposed to the neutron radiation produces a larger area under the prompt gamma ray peak in the detector than a smaller area of dimensions relative to the active volume of the gamma detection system.

Inventory of Used, Disused, Waste and Disposed Sources in Kenya

Energy Technology Data Exchange (ETDEWEB)

Kiti, S; Keter, J [Radiation Protection Board (RPBI), Kisumu (Kenya); Kinyua, R [Jomo Kenyatta University of Agriculture and Technology (JKUAT), Thika (Kenya)

2010-09-15

Kenya is committed to the peaceful applications of sealed and unsealed radioactive sources in medicine, industry, agriculture and training and research in order to achieve socioeconomic development. There are 4 nuclear medicine centers, 3 industrial radiotherapy facilities, 2 gamma irradiator facilities, one linear accelerator, 2 high dose radiation (HDR) Brachytherapy units, 5 industrial radiography units and many training and research facilities in the country that posses radioactive sources. The Kenya Radiation Protection Board is a Regulatory body established under Cap 243 of the Laws of Kenya cited as the Radiation Protection Act which provides for the protection of the public and radiation workers from dangers arising from materials capable of producing ionizing radiation. The mission of the Board is to accelerate, regulate and expand the contribution of nuclear and irradiation technology to the Kenyan economy through promotion of nuclear and radiation safety culture. The use of radioactive material requires an adequate established inventory. The objective of this project is to establish and maintain a national inventory of sealed and unsealed radioactive sources in Kenya. A national inventory was done by sending a questionnaire and personal communication as well thorough countrywide inspection surveys by Radiation Protection Officers from the regulatory body where lead pot containers were carried in case of disposal of a disused source or spent source. Advanced survey meters and automes radiation meters were used for radiation safety work, alarm meters were used to detect the threshold and source identifiers were used to identify unknown sources and their activities. A total of 130 radioactive sources (34 used, 20 disused, 39 waste and 37 disposed) including their JPEG images were identified and a national inventory established. Co-60 recorded the highest activity of 11,000 Ci followed by Cs-137 with 400 Ci and Ir-192 with 40 Ci. An updated inventory for the

76 FR 6692 - Radiation Sources on Army Land

Science.gov (United States)

2011-02-08

... possession of ionizing radiation sources by non-Army entities (including their civilian contractors) on an... Radiation Permit (ARP) from the garrison commander to use, store, or possess ionizing radiation sources on an Army installation. For the purpose of this rule, ``ionizing radiation source'' means any source...

Radiation measurement practice for understanding statistical fluctuation of radiation count using natural radiation sources

International Nuclear Information System (INIS)

Kawano, Takao

2014-01-01

It is known that radiation is detected at random and the radiation counts fluctuate statistically. In the present study, a radiation measurement experiment was performed to understand the randomness and statistical fluctuation of radiation counts. In the measurement, three natural radiation sources were used. The sources were fabricated from potassium chloride chemicals, chemical fertilizers and kelps. These materials contain naturally occurring potassium-40 that is a radionuclide. From high schools, junior high schools and elementary schools, nine teachers participated to the radiation measurement experiment. Each participant measured the 1-min integration counts of radiation five times using GM survey meters, and 45 sets of data were obtained for the respective natural radiation sources. It was found that the frequency of occurrence of radiation counts was distributed according to a Gaussian distribution curve, although the obtained 45 data sets of radiation counts superficially looked to be fluctuating meaninglessly. (author)

Inflatable door seals - reduced maintenance and longer service-life

International Nuclear Information System (INIS)

Kuran, S.; Wensel, R.; Lazic, M.

1995-01-01

Inflatable door seals, designed more than a quarter of a century ago, have given good service in Canadian and overseas CANDU reactors. These thin-walled elastomeric seals have been exposed to many thousands of cycles of inflation and deflation, various types of aging (temperature, radiation and time), ozone degradation, abrasion, pinching, stiction, cracking and installation damage. The fact that they have operated successfully as part of the reactor building containment structure - subjected to the same pressures and temperatures as those for the thick reinforced concrete walls and steel doors highlights the achievement of these thin rubber seals. However, in the last decade, the rubber industry has developed new compounds that are more resistant to radiation, temperature, and time-dependent aging. Components manufactured from such compounds are less prone to hardening, stress cracking and permanent set; thereby saving on replacement costs, inventory and overall maintenance. This paper discusses development and testing of recent material and design changes to inflatable seals, and addresses various practical issues faced by the operations engineers and maintainers using these seals. (author)

Doses from Medical Radiation Sources

Science.gov (United States)

... Medical Radiation Sources Michael G. Stabin, PhD, CHP Introduction Radiation exposures from diagnostic medical examinations are generally ... of exposure annually to natural background radiation. Plain Film X Rays Single Radiographs Effective Dose, mSv Skull ( ...

The regulatory control of radiation sources in Turkey

International Nuclear Information System (INIS)

Uslu, I.; Birol, E.

2001-01-01

In Turkey, the national competent authority for regulating activities involving radioactive sources is the Turkish Atomic Energy Authority, which implements the responsibility for the safety and security of radiation sources through its Radiation Health and Safety Department. The report describes the organization of the regulatory infrastructure for radiation safety in Turkey and, after a brief explanation of the current legal framework for such purpose, it refers to how the management of radiation sources is carried out and to the new provisions regarding radiation sources, including inspections of licensees and training on source safety. Finally, the report provides information on the Ikitelli radiological accident in Turkey and the current public concern about radiation sources after it happened. (author)

Ionizing radiation sources: very diversified means, multiple applications and a changing regulatory environment. Conference proceedings; Les sources de rayonnements ionisants: des moyens tres diversifies, des applications multiples et une reglementation en evolution. Recueil des presentations

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-11-15

This document brings together the available presentations given at the conference organised by the French society of radiation protection about ionizing radiation source means, applications and regulatory environment. Twenty eight presentations (slides) are compiled in this document and deal with: 1 - Overview of sources - some quantitative data from the national inventory of ionizing radiation sources (Yann Billarand, IRSN); 2 - Overview of sources (Jerome Fradin, ASN); 3 - Regulatory framework (Sylvie Rodde, ASN); 4 - Alternatives to Iridium radiography - the case of pressure devices at the manufacturing stage (Henri Walaszek, Cetim; Bruno Kowalski, Welding Institute); 5 - Dosimetric stakes of medical scanner examinations (Jean-Louis Greffe, Charleroi hospital of Medical University); 6 - The removal of ionic smoke detectors (Bruno Charpentier, ASN); 7 - Joint-activity and reciprocal liabilities - Organisation of labour risk prevention in case of companies joint-activity (Paulo Pinto, DGT); 8 - Consideration of gamma-graphic testing in the organization of a unit outage activities (Jean-Gabriel Leonard, EDF); 9 - Radiological risk control at a closed and independent work field (Stephane Sartelet, Areva); 10 - Incidents and accidents status and typology (Pascale Scanff, IRSN); 11 - Regional overview of radiation protection significant events (Philippe Menechal, ASN); 12 - Incident leading to a tritium contamination in and urban area - consequences and experience feedback (Laurence Fusil, CEA); 13 - Experience feedback - loss of sealing of a calibration source (Philippe Mougnard, Areva); 14 - Blocking incident of a {sup 60}Co source (Bruno Delille, Salvarem); 15 - Triggering of gantry's alarm: status of findings (Philippe Prat, Syctom); 16 - Non-medical electric devices: regulatory changes (Sophie Dagois, IRSN; Jerome Fradin, ASN); 17 - Evaluation of the dose equivalent rate in pulsed fields: method proposed by the IRSN and implementation test (Laurent Donadille

Code of practice for the safe use of ionizing radiation in secondary schools (1986)

International Nuclear Information System (INIS)

1987-01-01

The code of practice is intended for schools and indicates the basic philosophy behind the current approach to the control of hazards associated with the use of ionizing radiation. The purpose of this code is to provide guidance on safe and proper practices in the use of radiation. It covers modes of radiation exposure, shielding, dose limits, responsibility, general rules, x-ray generators, general control of radioactive sources, sealed sources and unsealed sources

Proposal of conditioning of the not-in-use sealed sources which are stored in the Radioactive Wastes Treatment Facility

International Nuclear Information System (INIS)

Jova, L.; Garcia, N.; Benitez, J.C.; Salgado, M.; Hernandez, A.

1996-01-01

There is a considerable number of sealed sources which are no longer in use at the radioactive wastes treatment facility. In the present work a methodology is proposed for the final conditioning of these sources, based on their immobilization in a cement matrix. This cementation is accomplished within a 200-liter tank

New sources of radiation

International Nuclear Information System (INIS)

Schimmerling, W.

1979-09-01

An attempt is made to select examples of radiation sources whose application may make new or unconventional demands on radiation protection and dosimetry. A substantial body of knowledge about high energy facilities exists and, partly for this reason, the great high energy accelerators are mentioned only briefly

Apparatus for radiation source depth determination in a material

International Nuclear Information System (INIS)

Campbell, P.J.

1979-01-01

An apparatus is disclosed for determining the depth of a radiation source within a body of material utilizing a radiation source holder moving the radiation source within the body. A plurality of switches have contacts that are fixed in relation to the movement of the radiation source within the material. Trigger means activates a particular switch at a preselected depth of the radiation source. Means for indicating the activation of a switch would thus produce a signal as a representative of the depth of the radiation source

High energy particle accelerators as radiation Sources

Energy Technology Data Exchange (ETDEWEB)

Abdelaziz, M E [National Center for Nuclear Safety and Radiation Vontrol, Atomic Energy Authority, Cairo (Egypt)

1997-12-31

Small accelerators in the energy range of few million electron volts are usually used as radiation sources for various applications, like radiotherapy, food irradiation, radiation sterilization and in other industrial applications. High energy accelerators with energies reaching billions of electron volts also find wide field of applications as radiation sources. Synchrotrons with high energy range have unique features as radiation sources. This review presents a synopsis of cyclic accelerators with description of phase stability principle of high energy accelerators with emphasis on synchrotrons. Properties of synchrotron radiation are given together with their applications in basic and applied research. 13 figs.,1 tab.

Development of the doubly sealed Ir192 sources for industrial applications

International Nuclear Information System (INIS)

Munoz, C.; Sabio Calvett, Manuel; Bianchi, Daniel R.; Banchik, Abraham D.; Mender, Alberto; Gonzalez, Alfredo J.

2003-01-01

A Program for Developing Double Sealed Irradiation Sources for industrial and medical applications is in progress at the Argentine Atomic Energy Commission. The present work describes the mechanical and metallurgical procedures for designing and welding dummy capsules of the two types that are required for making double sealed Ir 192 industrial sources with the designation ISO/98/C43515 according to ISO 2919 and leak tight according to ISO/98/9978 standards. That is part of a Project with INVAP company. Four different models, including the typical international model, were designed, machined and TIG-welded. Both the internal and external capsules and the end caps were made from AISI 316L stainless steel. Two types of welding station were made. In the first one the 'end cap' was welded to the capsule keeping the torch and the capsule fixed (stationary process), while in the second type the capsule rotates around its own axes during the process (out of cell dynamic semiautomatic controlled process). The welding parameters for the second welding process were selected from the different parameters used to process 120 'international type' capsules. All the processed units were subject to a visual inspection, 85% of them were considered acceptable, while the rest were rejected because of having, at naked eyes and/or under magnification glasses, different types of welding defects. Metallographic examination of the microstructure at the welding seam and the matrix were made in welded unit selected at random from different lots of all processed units in order to determine the penetration of the weld and the microstructure of the weld seam. Present results are encouraging enough to consider to start with the next step, where the capsules are process inside a 'hot cell' and with a Ir 192 foil inside the inner capsule to reproduce actual fabrication conditions. (author)

Photon acceleration-based radiation sources

International Nuclear Information System (INIS)

Hoffman, J. R.; Muggli, P.; Katsouleas, T.; Mori, W. B.; Joshi, C.

1999-01-01

The acceleration and deceleration of photons in a plasma provides the means for a series of new radiation sources. Previous work on a DC to AC Radiation Converter (DARC source) has shown variable acceleration of photons having zero frequency (i.e., an electrostatic field) to between 6 and 100 GHz (1-3). These sources all had poor guiding characteristics resulting in poor power coupling from the source to the load. Continuing research has identified a novel way to integrate the DARC source into a waveguide. The so called ''pin structure'' uses stainless steel pins inserted through the narrow side of an X band waveguide to form the electrostatic field pattern (k≠0, ω=0). The pins are spaced such that the absorption band resulting from this additional periodic structure is outside of the X band range (8-12 GHz), in which the normal waveguide characteristics are left unchanged. The power of this X band source is predicted theoretically to scale quadratically with the pin bias voltage as -800 W/(kV) 2 and have a pulse width of -1 ns. Cold tests and experimental results are presented. Applications for a high power, short pulse radiation source extends to the areas of landmine detection, improved radar resolution, and experimental investigations of molecular systems

Radiation protection and the safety of radiation sources

International Nuclear Information System (INIS)

1996-01-01

These Safety Fundamentals cover the protection of human beings against ionizing radiation (gamma and X rays and alpha, beta and other particles that can induce ionization as they interact with biological materials), referred to herein subsequently as radiation, and the safety of sources that produce ionizing radiation. The Fundamentals do not apply to non-ionizing radiation such as microwave, ultraviolet, visible and infrared radiation. They do not apply either to the control of non-radiological aspects of health and safety. They are, however, part of the overall framework of health and safety

MODIFIED APPROACH FOR SITE SELECTION OF UNWANTED RADIOACTIVE SEALED SOURCES DISPOSAL IN ARID COUNTRIES (CASE STUDY - EGYPT)

International Nuclear Information System (INIS)

ABDEL AZIZ, M.A.H.; COCHRAN, J.R.

2008-01-01

The aim of this study is to present a systematic methodology for siting of radioactive sealed sources disposal in arid countries and demonstrate the use of this methodology in Egypt. Availing from the experience gained from the greater confinement disposal (GCD) boreholes in Nevada, USA, the IAEA's approach for siting of near disposal was modified to fit the siting of the borehole disposal which suits the unwanted radioactive sealed sources. The modifications are represented by dividing the surveyed area into three phases; the exclusion phase in which the areas that meet exclusion criteria should be excluded, the site selection phase in which some potential sites that meet the primary criteria should be candidate and the preference stage in which the preference between the potential candidate sites should be carried out based on secondary criteria to select one or two sites at most. In Egypt, a considerable amount of unwanted radioactive sealed sources wastes have accumulated due to the peaceful uses of radio-isotopes.Taking into account the regional aspects and combining of the proposed developed methodology with geographic information system (GIS), the Nile Delta and its valley, the Sinai Peninsula and areas of historical heritage value are excluded from our concern as potential areas for radioactive waste disposal. Using the primary search criteria, some potential sites south Kharga, the Great Sand Sea, Gilf El-Kebear and the central part of the eastern desert have been identified as candidate areas meeting the primary criteria of site selection. More detailed studies should be conducted taking into account the secondary criteria to prefer among the above sites and select one or two sites at most

Algorithms for the process management of sealed source brachytherapy

International Nuclear Information System (INIS)

Engler, M.J.; Ulin, K.; Sternick, E.S.

1996-01-01

Incidents and misadministrations suggest that brachytherapy may benefit form clarification of the quality management program and other mandates of the US Nuclear Regulatory Commission. To that end, flowcharts of step by step subprocesses were developed and formatted with dedicated software. The overall process was similarly organized in a complex flowchart termed a general process map. Procedural and structural indicators associated with each flowchart and map were critiqued and pre-existing documentation was revised. open-quotes Step-regulation tablesclose quotes were created to refer steps and subprocesses to Nuclear Regulatory Commission rules and recommendations in their sequences of applicability. Brachytherapy algorithms were specified as programmable, recursive processes, including therapeutic dose determination and monitoring doses to the public. These algorithms are embodied in flowcharts and step-regulation tables. A general algorithm is suggested as a template form which other facilities may derive tools to facilitate process management of sealed source brachytherapy. 11 refs., 9 figs., 2 tabs

Detection and measurement of ionizing radiation by the Radioactive Waste Management Centre

International Nuclear Information System (INIS)

Mudra, Josef

2013-01-01

The following topics are dealt with: Basic properties of radionuclides and selection of suitable detectors; radiation characteristics of sealed sources (radiation detection, dose rate measurement, surface contamination measurement, gamma spectroscopy); non-destructive analysis (segment gamma scanner, digital radiography); destructive analysis; radiation monitoring of humans and workplaces; and dosimetric monitoring of workplace surroundings and discharges. (orig.)

Ionizing radiation sources. Ionizing radiation interaction with matter

International Nuclear Information System (INIS)

Popits, R.

1976-01-01

Fundamentals of nuclear physics are reviewed under the headings: obtaining of X-rays and their properties; modes of radioactive decay of natural or man-made radionuclides; radioactive neutron sources; nuclear fission as basis for devising nuclear reactors and weapons; thermonuclear reactions; cosmic radiation. Basic aspects of ionizing radiation interactions with matter are considered with regard to charged particles, photon radiation, and neutrons. (A.B.)

75 FR 19302 - Radiation Sources on Army Land

Science.gov (United States)

2010-04-14

... possession of ionizing radiation sources by non-Army agencies (including their civilian contractors) on an... radiation sources on Army land. The Army requires Non-Army agencies (including their civilian contractors... ionizing radiation sources on an Army Installation. For the purpose of this proposed rule, ``ionizing...

Radiation Source Replacement Workshop

Energy Technology Data Exchange (ETDEWEB)

Griffin, Jeffrey W.; Moran, Traci L.; Bond, Leonard J.

2010-12-01

This report summarizes a Radiation Source Replacement Workshop in Houston Texas on October 27-28, 2010, which provided a forum for industry and researchers to exchange information and to discuss the issues relating to replacement of AmBe, and potentially other isotope sources used in well logging.

Development of regulatory technologies of key issues of radiation sources in the medical and industrial fields

International Nuclear Information System (INIS)

Lee, Jae Seong; Kim, Byung Soo; Ku, Bon Chul

2006-08-01

The aim of this research is to provide with rational bases to address the key issues raising up during the expansion of RI/RG usage in the medical and industrial fields, thus eventually contribute to enhancing the effectiveness of national regulatory systems. Related key issues that are introduced in the medical and industrial fields are analyzed and some outcomes are produced. The following results are attained. - Estimation Methodology Development of Regulatory Effects for the Use of Radioactive Substances, - Survey on Domestic Status of Nuclear Materials and Review on Domestic/Foreign Regulatory System for Nuclear Materials Regulation, - Comparative Analysis of KSTAR and Fusion Facilities of Advanced Countries, - Radiological Characteristics of Proton Therapy and Analysis of Foreign Cases and Systems, - Detection and Safety Analysis of Leak Radiation of High Energy Medical Generators, - Survey and Analysis on Usage and Requirements of Sealed Sources, - Incidents/Accidents Reporting System for RI-related Facilities, - Development of Audio-Visual Education Materials for Radiation Workers, - Development of Major Safety Procedures for Portable RIs, - Expansion of Existing DB for Radiation Devices including New Domestic Ones, - Survey of Foreign Status of Quality Maintenance System for Radiation equipment

Report of the Study Group on Safety of RI and Radiation Uses

International Nuclear Information System (INIS)

Yamazaki, Fumio

1977-01-01

To grasp the present state of RI and radiation usages, a survey by questionnaire was made on the enterprises using small sealed radiation sources, the enterprises carrying out nondestructive tests with large radiation sources and the medical institutions utilizing RIs and radiation. The results of the study aiming at establishing the reasonable and adequate measures of safety management are described together with the survey results. The items studied are the legal regulations, facilities, education and training of workers, and radioactive waste management. (Mori, K.)

Management of Spent Sealed Radioactive Sources in Bulgaria, Latvia, Lithuania, Romania and Slovakia

International Nuclear Information System (INIS)

Angus, M.; Cowley, M.; Moreton, T.; Wells, D.

2003-01-01

This study has been performed to consider the situation relating to the regulation and management of spent sealed radioactive sources (SSRS) in five of the Central and Eastern European (C and EE) countries that are being considered for admission to the EU, namely, Bulgaria, Latvia, Lithuania, Romania and Slovakia. Two previous studies have considered the situation in the current EU member states(1) and in the Czech Republic, Estonia, Hungary, Poland and Slovenia(2). The general aim of this study has been to acquire a thorough understanding of the management of SSRS in the five countries, in order to recommend improvements in management schemes and to establish whether the application of common disposal criteria would be advantageous. This report is structured in the following manner; following the Introduction (Section 1), there is a description of the current and proposed regulatory requirements in the EU, together with a summarised comparison of the regulatory systems in the five countries with EU standards (Section 2). Sections 3 to 7 are dedicated to each of the five countries. Each of these sections is similarly sub-divided to enable country-by-country and topic-by-topic comparison. In each of Sections 3 to 7 there is an overview, description of the sealed source inventory, regulations, current management practices, retrieval of unregistered (sometimes known as lost or orphan sources) SSRS, conclusions and a description of possible future technical assistance projects. In addition, there is a description in each of Sections 3 to 7 of the management of 226 Ra sources, which is receiving special attention in many countries (Table I provides a summary and comparison of the management of 226 Ra in the five countries).both country-specific and generic recommendations. A common concern in the five countries and many other countries, including the EU member states, is the problem of accidental inclusion of SSRS in consignments of scrap metal. The detection of

Detection of seal contamination in heat-sealed food packaging based on active infrared thermography

Science.gov (United States)

D'huys, Karlien; Saeys, Wouter; De Ketelaere, Bart

2015-05-01

In the food industry packaging is often applied to protect the product from the environment, assuring quality and safety throughout shelf life if properly performed. Packaging quality depends on the material used and the closure (seal). The material is selected based on the specific needs of the food product to be wrapped. However, proper closure of the package is often harder to achieve. One problem possibly jeopardizing seal quality is the presence of food particles between the seal. Seal contamination can cause a decreased seal strength and thus an increased packaging failure risk. It can also trigger the formation of microchannels through which air and microorganisms can enter and spoil the enclosed food. Therefore, early detection and removal of seal-contaminated packages from the production chain is essential. In this work, a pulsed-type active thermography method using the heat of the sealing bars as an excitation source was studied for detecting seal contamination. The cooling profile of contaminated seals was recorded. The detection performance of four processing methods (based on a single frame, a fit of the cooling profile, pulsed phase thermography and a matched filter) was compared. High resolution digital images served as a reference to quantify contamination. The lowest detection limit (equivalent diameter of 0.63 mm) and the lowest processing time (0.42 s per sample) were obtained for the method based on a single frame. Presumably, practical limitations in the recording stage prevented the added value of active thermography to be fully reflected in this application.

New legislative regulations for ensuring radiation protection using ionizing radiation sources in medicine

International Nuclear Information System (INIS)

Boehm, K.

2018-01-01

European Commission Directive No. 2013/59 / EURATOM laying down basic safety requirements for the provision of radiation protection regulates the provision of radiation protection for workers with radiation sources and residents in all areas of use of ionizing radiation sources. This Directive also addresses radiation protection in the use of ionizing radiation sources in medicine. The European Commission Directive regulates the requirements for radiation protection but also extends to its scope and provisions on the use of medical radiation sources (so-called m edical exposure ) in the scope of further legislation in the field of health care, which has to be amended and modified or possibly issued new. It was necessary in the preparation of the new act on radiation protection to amend simultaneously Act no. 576/2004 on the provision of health care and services related to provision of health care and Act no. 578/2004 on Health care Providers, Health care Professionals and Organizations in Health Care and to prepare a series of implementing regulations not only to the Law on Radiation Protection but also to the Laws governing the Provision of Health Care. The paper presents changes to existing legislation on radiation protection in medical radiation and new requirements for the construction and operation of health workplaces with radiation sources, the protection of the health of patients, the requirements for instrumentation used for medical radiation and radiological instrumentation tests. (authors)

Declaration and authorization forms for the fabrication, distribution or use of radioactive sources or electric generators of ionizing radiation; Formulaires de declaration et d'autorisation de fabrication, de distribution ou d'utilisation de sources radioactives ou de generateurs electriques de rayonnements ionisants

Energy Technology Data Exchange (ETDEWEB)

NONE

2010-07-01

This document gathers all the forms to be completed when declaring or when asking for an authorization for the fabrication, retailing or use of radioactive sources or electric equipment generating ionizing radiation. These forms can concern all domains (use of sealed radioactive sources, possession and use of a particle accelerator or of radionuclides, import or export of radionuclides or of products containing radionuclides), or the use of such materials or equipment in the medical sector, or the fabrication and use in industry or research, or in user's guides for radioactive sources

Spray sealing: A breakthrough in integral fuel tank sealing technology

Science.gov (United States)

Richardson, Martin D.; Zadarnowski, J. H.

1989-11-01

In a continuing effort to increase readiness, a new approach to sealing integral fuel tanks is being developed. The technique seals potential leak sources by spraying elastomeric materials inside the tank cavity. Laboratory evaluations project an increase in aircraft supportability and reliability, an improved maintainability, decreasing acquisition and life cycle costs. Increased usable fuel volume and lower weight than conventional bladders improve performance. Concept feasibility was demonstrated on sub-scale aircraft fuel tanks. Materials were selected by testing sprayable elastomers in a fuel tank environment. Chemical stability, mechanical properties, and dynamic durability of the elastomer are being evaluated at the laboratory level and in sub-scale and full scale aircraft component fatigue tests. The self sealing capability of sprayable materials is also under development. Ballistic tests show an improved aircraft survivability, due in part to the elastomer's mechanical properties and its ability to damp vibrations. New application equipment, system removal, and repair methods are being investigated.

Radiation attenuation gauge with magnetically coupled source

International Nuclear Information System (INIS)

Wallace, S.A.

1978-01-01

Disclosed is a radiation attenuation gauge for measuring thickness and density of a material which includes, in combination, a source of gamma radiation contained within a housing of magnetic or ferromagnetic material, and a means for measuring the intensity of gamma radiation. The measuring means has an aperture and magnetic means disposed adjacent to the aperture for attracting and holding the housed source in position before the aperture. The material to be measured is placed between the source and the measuring means

Radiation protection in the application of ionizing radiation in industry

International Nuclear Information System (INIS)

Mohamad Yusof Mohamad Ali

1987-01-01

There is a substantial increase in the use of ionizing radiation in industry throughout the country especially in the last five years or so. With this growth in the number of users and activity of sources used, and together with the introduction of the new Atomic Energy Licensing Act (AELA) in 1984, the question of radiation safety and protection of workers and members of the public in general, can no longer be taken lightly. It has to be dealt with effectively. In this paper, a general discussion and clarification on certain practical aspects of radiation protection as recommended by the International Atomic Energy Agency (IAEA) is presented. Amongst the topics chosen are those on area monitoring, personnel monitoring, leak testing of sealed sources and training of personnel. Also presented in the paper is a brief discussion about UTN's experience in giving out radiation protection services to various agencies throughout the country. (author)

Ionization detector with improved radiation source

International Nuclear Information System (INIS)

Solomon, E.F.

1977-01-01

The detector comprises a chamber having at least one radiation source disposed therein. The chamber includes spaced collector plates which form a part of a detection circuit for sensing changes in the ionization current in the chamber. The radiation source in one embodiment is in the form of a wound wire or ribbon suitably supported in the chamber and preferably a source of beta particles. The chamber may also include an adjustable electrode and the source may function as an adjustable current source by forming the wire or ribbon in an eliptical shape and rotating the structure. In another embodiment the source has a random shape and is homogeneously disposed in the chamber. 13 claims, 5 drawing figures

Seals and sealing handbook

CERN Document Server

Flitney, Robert K

2007-01-01

Wherever machinery operates there will be seals of some kind ensuring that the machine remains lubricated, the fluid being pumped does not leak, or the gas does not enter the atmosphere. Seals are ubiquitous, in industry, the home, transport and many other places. This 5th edition of a long-established title covers all types of seal by application: static, rotary, reciprocating etc. The book bears little resemblance to its predecessors, and Robert Flitney has re-planned and re-written every aspect of the subject. No engineer, designer or manufacturer of seals can afford to be without this uniq

Security of radioactive sources in radiation facilities

International Nuclear Information System (INIS)

2011-03-01

Safety codes and safety standards are formulated on the basis of internationally accepted safety criteria for design, construction and operation of specific equipment, systems, structures and components of nuclear and radiation facilities. Safety codes establish the objectives and set requirements that shall be fulfilled to provide adequate assurance for safety. Safety guides and guidelines elaborate various requirements and furnish approaches for their implementation. Safety manuals deal with specific topics and contain detailed scientific and technical information on the subject. These documents are prepared by experts in the relevant fields and are extensively reviewed by advisory committees of the Board before they are published. The documents are revised when necessary, in the light of experience and feedback from users as well as new developments in the field. In India, radiation sources are being widely used for societal benefits in industry, medical practices, research, training and agriculture. It has been reported from all over the world that unsecured radioactive sources caused serious radiological accidents involving radiation injuries and fatalities. Particular concern was expressed regarding radioactive sources that have become orphaned (not under regulatory control) or vulnerable (under weak regulatory control and about to be orphaned). There is a concern about safety and security of radioactive sources and hence the need of stringent regulatory control over the handling of the sources and their security. In view of this, this guide is prepared which gives provisions necessary to safeguard radiation installations against theft of radioactive sources and other malevolent acts that may result in radiological consequences. It is, therefore, required that the radiation sources are used safely and managed securely by only authorised personnel. This guide is intended to be used by users of radiation sources in developing the necessary security plan for

Radiation effects on light sources and detectors

International Nuclear Information System (INIS)

Barnes, C.E.

1985-01-01

The rapidly expanding field of optoelectronics includes a wide variety of both military and non-military applications in which the systems must meet radiation exposure requirements. Herein, we review the work on radiation effects on sources and detectors for such optoelectronic systems. For sources the principal problem is permanent damage-induced light output degradation, while for detectors it is ionizing radiation-induced photocurrents

Natural radiation sources fabricated from potassic chemical fertilizers and application to radiation education

International Nuclear Information System (INIS)

Kawano, Takao

2010-01-01

Potassic chemical fertilizers contain potassium, a small part of which is potassium-40. Since potassium-40 is a naturally occurring radioisotope, potassic chemical fertilizers are often used for demonstrations of the existence of natural radioisotopes and radiation. To fabricate radiation sources as educational tools, the compression and formation method developed by our previous study was applied to 13 brands of commercially available chemical fertilizers containing different amounts of potassium. The suitability (size, weight, and solidness) of thus fabricated sources was examined and 12 of them were selected as easy-to-use radiation sources at radiation educational courses. The radiation strength (radiation count rate measured by a GM survey meter) and potassium content of the 12 sources were examined. It was found that the count rate was wholly proportional to the percentage of potassium, and a new educational application was proposed and discussed for understanding that the substance emitting radiation must be the potassium present in the raw fertilizers. (author)

Separation of radiation from two sources from their known radiated sum field

DEFF Research Database (Denmark)

Laitinen, Tommi; Pivnenko, Sergey

2011-01-01

This paper presents a technique for complete and exact separation of the radiated fields of two sources (at the same frequency) from the knowledge of their radiated sum field. The two sources can be arbitrary but it must be possible to enclose the sources inside their own non-intersecting minimum...

Radiation protection programme for nuclear gauges

International Nuclear Information System (INIS)

Muzongomerwa, A.

2014-04-01

Ionizing radiation including the use of nuclear gauges can be very hazardous to humans and steps must be taken to minimize the risks so as to prevent deterministic effects and limiting chances for stochastic effects. The availability of a Radiation Protection Programme and its effective implementation ensures appropriate safety and security provisions for sealed radiation sources and promotes a safety culture within a facility that utilizes these sources. This study aims at establishing a guide on the radiation protection programme in nuclear gauges that comply with national requirements derived from current international recommendations. Elements that form part of a radiation protection programme are covered in detail as well as recommendations. The overall objective is to protect people (operators and the public) and the environment from the harmful effects of these sources if they are not properly controlled. Nuclear gauges for well logging and X-ray based gauges are outside the scope of this study. (au)

Assessment of the properties of disused sealed radioactive sources for disposal in a borehole facility

International Nuclear Information System (INIS)

Adjepong, K.

2015-01-01

Radioactive wastes arise from applications in which radioactive materials are used. Medicine, industries and agriculture are examples of areas where radioactive materials are used. Most of the radioactive materials used in nuclear applications are in the form of sealed radioactive sources (SRS). After a number of usages, the SRS may no longer be useful enough for its original purpose and will be considered as a disused sealed radioactive source (DSRS). DSRS are potentially dangerous to human health and the environment, and therefore important to manage them safely. Currently in Ghana, DSRS are collected and stored awaiting a final disposal option. There are ongoing plans to implement the Borehole Disposal of Disused Sealed Sources (BOSS) system in Ghana as a final disposal option. There are, however, concerns about the number of DSRS disposal packages that can safely be disposed in a narrow borehole underground in a long term without posing any harm to people and the environment. It is therefore necessary to assess the properties of DSRS that need to be placed into the borehole to determine the safety of this disposal option. For this study, 160 DSRS were selected from the DSRS inventory. The present activity, volume, A/D ratio and thermal output of all the DSRS were determined. The SIMBOD database tool was used to determine the number of capsules and disposal packages that will be required with respect to the DSRS registered into it. Also, verification measurements to confirm the DSRS inventory data were conducted. The assessment have shown that DSRS used in this study would require a total of seven (7) capsules. The estimated total activity of the disposal packages were below the waste acceptance criteria and the thermal output for each disposal package were also below the 50W limit. One borehole with an estimated length of 57 m will be safe to dispose the DSRS used in this study. The verification measurements confirmed the confirmed the DSRS inventory data. It

The ultimate solution. Disposal of disused sealed radioactive sources (DSRS)

International Nuclear Information System (INIS)

Heard, R.G.

2011-01-01

The borehole disposal concept (BDC) was first presented to ICEM by Potier, J-M in 2005. This paper repeats the basics introduced by Potier and relates further developments. It also documents the history of the development of the BDC. For countries with no access to existing or planned geological disposal facilities for radioactive wastes, the only options for managing high activity or long-lived disused radioactive sources are to store them indefinitely, return them to the supplier or find an alternative method of disposal. Disused sealed radioactive sources (DSRS) pose an unacceptable radiological and security risk if not properly managed. Out of control sources have already led to many high-profile incidents or accidents. One needs only to remember the recent accident in India that occurred earlier this year. Countries without solutions in place need to consider the future management of DSRSs urgently. An on-going problem in developing countries is what to do with sources that cannot be returned to the suppliers, sources for which there is no further use, sources that have not been maintained in a working condition and sources that are no longer suitable for their intended purpose. Disposal in boreholes is intended to be simple and effective, meeting the same high standards of long-term radiological safety as any other type of radioactive waste disposal. It is believed that the BDC can be readily deployed with simple, cost-effective technologies. These are appropriate both to the relatively small amounts and activities of the wastes and the resources that can realistically be found in developing countries. The South African Nuclear Energy Corporation Ltd (Necsa) has carried out project development and demonstration activities since 1996. The project looked into the technical feasibility, safety and economic viability of BDC under the social, economic, environmental and infrastructural conditions currently prevalent in Africa. Implementation is near at hand with

Safety Regulations for Ionizing Radiations. Vietnam Standard (TCVN 4397-87)

International Nuclear Information System (INIS)

1987-01-01

The regulations were prepared for purpose of providing basic requirements of ionizing radiation protection and giving guide for design criteria of radiation installations in Vietnam. The allowable maximum levels for personnel categories are established. Regulated are methods for handling sealed and unsealed sources of radiation, transfer and transport of radioactive materials. Defined requirements and operating conditions that must be met. Determined are procedures and actions of decontamination. (N.H.A)

POP load and vitamins as potential biomarkers in the Baltic seals

Energy Technology Data Exchange (ETDEWEB)

Routti, H.; Nyman, M.; Helle, E. [Finnish Game and Fisheries Research Inst., Helsinki (Finland); Backman, C. [National Veterinary and Food Research Inst. (Finland); Koistinen, J. [Div. of Environmental Health, National Public Health Inst. (Finland)

2004-09-15

Exceptionally high levels of polychlorinated biphenyls (PCB) and 1,1,1.trichloro- 2,2-bis[p-chlorophenyl]ethane (DDT) and its metabolites were reported in the Baltic seals in the late 1960s and early 1970s. PCB levels in ringed seals, in particular, are still high enough to threaten the well being of the animals. The observed difference in contaminant pattern between ringed and grey seals in the Baltic has not been explained, but could be partly due to species-specific food sources. Several pathological and biochemical changes observed in the Baltic seals correlate with the individual POP loads. Of the observed biochemical changes, elevated cytochrome P4501A (CYP1A) levels, decreased liver vitamin A stores and increased vitamin E levels in blubber or plasma, have been proposed as possible biomarkers of contaminant load in Baltic seals. However, as the vitamin A and E status of marine mammals also reflects the nutritional vitamin level, the lower vitamin A and elevated vitamin E levels observed in the Baltic seals could be a reflection of the levels of these vitamins in their food sources. The aim of this study was to investigate the contaminant load in the Baltic seals and to evaluate the utility level of potential exposure and effect biomarkers. Seals from less contaminated areas were used as reference material (Svalbard and Sable Island, Canada). In the present study, POP and vitamin levels were also studied in seal prey species in order to study the transfer of these compounds to grey and ringed seals from their main food sources.

Regulated control of practices and radiation sources

International Nuclear Information System (INIS)

1992-01-01

Excepting the radiation caused by the natural background radiation, the Executive Secretariat for Nuclear Affairs (SEAN) does not authorize any source no practice within the national territory that may imply exposure of a person to ionizing radiation unless this use is ruled. This document establishes the basic criteria to set up such system as well as to exclude or exempt practices and sources from this regulated control

Radiotracer and Sealed Source Applications in Sediment Transport Studies

International Nuclear Information System (INIS)

2014-01-01

The investigation of sediment transport in seas and rivers is crucial for civil engineering and littoral protection and management. Coastlines and seabeds are dynamic regions, with sediments undergoing periods of erosion, transport, sedimentation and consolidation. The main causes for erosion in beaches include storms and human actions such as the construction of seawalls, jetties and the dredging of stream mouths. Each of these human actions disrupts the natural flow of sand. Current policies and practices are accelerating the beach erosion process. However, there are viable options available to mitigate this damage and to provide for sustainable coastlines. Radioactive methods can help in investigating sediment dynamics, providing important parameters for better designing, maintaining and optimizing civil engineering structures. Radioisotopes as tracers and sealed sources have been useful and often irreplaceable tools for sediment transport studies. The training course material is based on lecture notes and practical works delivered by many experts in IAEA supported activities. Lectures and case studies were reviewed by a number of specialists in this field

Future Synchrotron Radiation Sources

CERN Document Server

Winick, Herman

2003-01-01

Sources of synchrotron radiation (also called synchrotron light) and their associated research facilities have experienced a spectacular growth in number, performance, and breadth of application in the past two to three decades. In 1978 there were eleven electron storage rings used as light sources. Three of these were small rings, all below 500 mega-electron volts (MeV), dedicated to this purpose; the others, with energy up to 5 giga-electron volts (GeV), were used parasitically during the operation of the ring for high energy physics research. In addition, at that time synchrotron radiation from nine cyclic electron synchrotrons, with energy up to 5 GeV, was also used parasitically. At present no cyclic synchrotrons are used, while about 50 electron storage rings are in operation around the world as fully dedicated light sources for basic and applied research in a wide variety of fields. Among these fields are structural molecular biology, molecular environmental science, materials, analytic chemistry, micr...

Radiation sources and methods for producing them

International Nuclear Information System (INIS)

Malson, H.A.; Moyer, S.E.; Honious, H.B.; Janzow, E.F.

1979-01-01

The radiation sources contain a substrate with an electrically conducting, non-radioactive metal surface, a layer of a metal isotope of the scandium group as well as a percentage of non-radioactive binding metal being coated on the surface by means of an electroplating method. Besides examples for β sources ( 147 Pm), γ sources ( 241 Am), and neutron sources ( 252 Cf) there is described an α-radiation source ( 241 Am, 244 Cu, 238 Pu) for smoke detectors. There are given extensive tables and a bibliography. (DG) [de

Radiation safety in welding and testing

International Nuclear Information System (INIS)

King, B.E.; Malaxos, M.; Hartley, B.M.

1985-01-01

There are a number of ways of achieving radiation safety in the workplace. The first is by engineering radiation safety into the equipment, providing shielded rooms and safety interlocks. The second is by following safe working procedures. The National Health and Medical Research Council's Code of practice for the control and safe handling of sealed radioactive sources used in industrial radiography (1968) sets out the standards which must be met by equipment to be used in industrial radiography

Radiation protection on nuclear medicine services

International Nuclear Information System (INIS)

Anon

2000-01-01

Nuclear medicine is a sector of the medicine that studies and applies radionuclide in diagnosis and therapy. Nuclear medicine is a very specific area of the medicine, making use of non-sealed radioactive sources which are prescribed to the patient orally or are injected. Special procedures in radiation protection are required in nuclear medicine to manipulate these kind of sources and to produce technetium-99m through molybdenum generator. The present paper addresses the them radiation protection in a Nuclear Medicine Department (NMD), showing the main requirements of the CNEN- National Commission of Nuclear Energy and the Public Health. Radiation protection procedures adopted in assembling a NMD, as well the daily techniques for monitoring and for individual dosimetry are discussed. Past and present analyses in a level of radiation protection are presented. (author)

X radiation sources based on accelerators

International Nuclear Information System (INIS)

Couprie, M.E.; Filhol, J.M.

2008-01-01

Light sources based on accelerators aim at producing very high brilliance coherent radiation, tunable from the infrared to X-ray range, with picosecond or femtosecond light pulses. The first synchrotron light sources were built around storage rings in which a large number of relativistic electrons produce 'synchrotron radiation' when their trajectory is subjected to a magnetic field, either in bending magnets or in specific insertion devices (undulators), made of an alternating series of magnets, allowing the number of curvatures to be increased and the radiation to be reinforced. These 'synchrotron radiation' storage rings are now used worldwide (there are more than thirty), and they simultaneously distribute their radiation to several tens of users around the storage ring. The most effective installations in term of brilliance are the so-called third generation synchrotron radiation light sources. The radiation produced presents pulse durations of the order of a few tens of ps, at a high rate (of the order of MHz); it is tunable over a large range, depending on the magnetic field and the electron beam energy and its polarisation is adjustable (in the V-UV-soft-X range). Generally, a very precise spectral selection is made by the users with a monochromator. The single pass linear accelerators can produce very short electron bunches (around 100 fs). The beam of very high electronic density is sent into successive undulator modules, reinforcing the radiation's longitudinal coherence, produced according to a Free Electron Laser (FEL) scheme by the interaction between the electron bunch and a light wave. The very high peak brilliance justifies their designation as fourth generation sources. The number of users is smaller because an electron pulse produces a radiation burst towards only one beamline. Energy Recovery Linacs (ERL) let the beam pass several times in the accelerator structures either to recover the energy or to accelerate the electrons during several turns

Radiation therapy sources, equipment and installations

International Nuclear Information System (INIS)

2011-03-01

The safety code for Telegamma Therapy Equipment and Installations, (AERB/SC/MED-1) and safety code for Brachytherapy Sources, Equipment and Installations, (AERB/SC/MED-3) were issued by AERB in 1986 and 1988 respectively. These codes specified mandatory requirements for radiation therapy facilities, covering the entire spectrum of operations ranging from the setting up of a facility to its ultimate decommissioning, including procedures to be followed during emergency situations. The codes also stipulated requirements of personnel and their responsibilities. With the advent of new techniques and equipment such as 3D-conformal radiation therapy, intensity modulated radiation therapy, image guided radiation therapy, treatment planning system, stereotactic radiosurgery, stereotactic radiotherapy, portal imaging, integrated brachytherapy and endovascular brachytherapy during the last two decades, AERB desires that these codes be revised and merged into a single code titled Radiation Therapy Sources, Equipment, and Installations

Incidents with hazardous radiation sources; Zwischenfaelle mit gefaehrlichen Strahlenquellen

Energy Technology Data Exchange (ETDEWEB)

Schoenhacker, Stefan [Bundesministerium fuer Inneres, Traiskirchen (Austria). Abt. 1/9 - Zivilschutzschule

2016-07-01

Incidents with hazardous radiation sources can occur in any country, even those without nuclear facilities. Preparedness for such incidents is supposed to fulfill globally agreed minimum standards. Incidents are categorized in incidents with licensed handling of radiation sources as for material testing, transport accidents of hazardous radiation sources, incidents with radionuclide batteries, incidents with satellites containing radioactive inventory, incidents wit not licensed handling of illegally acquired hazardous radiation sources. The emergency planning in Austria includes a differentiation according to the consequences: incidents with release of radioactive materials resulting in restricted contamination, incidents with release of radioactive materials resulting in local contamination, and incidents with the hazard of e@nhanced exposure due to the radiation source.

Automation system for quality control in manufacture of iodine-125 sealed sources used in brachytherapy

International Nuclear Information System (INIS)

Somessari, Samir L.; Feher, Anselmo; Sprenger, Francisco E.; Rostellato, Maria E.C.M.; Moura, Joao A.; Costa, Osvaldo L.; Calvo, Wilson A.P.

2011-01-01

The objective of this work is to develop an automation system for Quality Control in the production of Iodine-125 sealed sources, after undergoing the process of laser beam welding. These sources, also known as Iodine-125 seeds are used, successfully, in the treatment of cancer by brachytherapy, with low-dose rates. Each small seed is composed of a welded titanium capsule with 0.8 mm diameter and 4.5 mm in length, containing Iodine-125 adsorbed on an internal silver wire. The seeds are implanted in the human prostate to irradiate the tumor and treat the cancerous cells. The technology to automate the quality control system in the manufacture of Iodine-125 seeds consists in developing and associate mechanical parts, electronic components and pneumatic circuits to control machines and processes. The automation technology for Iodine-125 seed production developed in this work employs programmable logic controller, step motors, drivers of control, electrical-electronic interfaces, photoelectric sensors, interfaces of communication and software development. Industrial automation plays an important role in the production of Iodine-125 seeds, with higher productivity and high standard of quality, facilitating the implementation and operation of processes with good manufacturing practices. Nowadays, the Radiation Technology Center at IPEN-CNEN/SP imports and distributes 36,000 Iodine-125 seeds per year for clinics and hospitals in the whole country. However, the Brazilian potential market is of 8,000 Iodine-125 seeds per month. Therefore, the local production of these radioactive seeds has become a priority for the Institute, aiming to reduce the price and increase the supply to the population in Brazil. (author)

Automation system for quality control in manufacture of iodine-125 sealed sources used in brachytherapy

Energy Technology Data Exchange (ETDEWEB)

Somessari, Samir L.; Feher, Anselmo; Sprenger, Francisco E.; Rostellato, Maria E.C.M.; Moura, Joao A.; Costa, Osvaldo L.; Calvo, Wilson A.P., E-mail: somessar@ipen.b, E-mail: afeher@ipen.b, E-mail: sprenger@ipen.b, E-mail: elisaros@ipen.b, E-mail: olcosta@ipen.b, E-mail: wapcalvo@ipen.b [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

2011-07-01

The objective of this work is to develop an automation system for Quality Control in the production of Iodine-125 sealed sources, after undergoing the process of laser beam welding. These sources, also known as Iodine-125 seeds are used, successfully, in the treatment of cancer by brachytherapy, with low-dose rates. Each small seed is composed of a welded titanium capsule with 0.8 mm diameter and 4.5 mm in length, containing Iodine-125 adsorbed on an internal silver wire. The seeds are implanted in the human prostate to irradiate the tumor and treat the cancerous cells. The technology to automate the quality control system in the manufacture of Iodine-125 seeds consists in developing and associate mechanical parts, electronic components and pneumatic circuits to control machines and processes. The automation technology for Iodine-125 seed production developed in this work employs programmable logic controller, step motors, drivers of control, electrical-electronic interfaces, photoelectric sensors, interfaces of communication and software development. Industrial automation plays an important role in the production of Iodine-125 seeds, with higher productivity and high standard of quality, facilitating the implementation and operation of processes with good manufacturing practices. Nowadays, the Radiation Technology Center at IPEN-CNEN/SP imports and distributes 36,000 Iodine-125 seeds per year for clinics and hospitals in the whole country. However, the Brazilian potential market is of 8,000 Iodine-125 seeds per month. Therefore, the local production of these radioactive seeds has become a priority for the Institute, aiming to reduce the price and increase the supply to the population in Brazil. (author)

Training in radiation protection and the safe use of radiation sources

International Nuclear Information System (INIS)

2001-01-01

The need for education and training in the various disciplines of radiation protection has long been recognized by the IAEA, the International Labour Organization (ILO), the United Nations Educational, Scientific and Cultural Organization, the World Health Organization and the Pan American Health Organization (PAHO). This need has been partially met through the many training courses undertaken by these organizations, either individually or in collaboration. The IAEA has assisted developing Member States in the training of specialists in radiation protection and safety through its organized educational and specialized training courses, workshops, seminars, fellowships and scientific visits. Training is an important means of promoting safety culture and enhancing the level of competence of personnel involved in radiation protection activities, and has acquired a place in the IAEA's programme accordingly. For example, the IAEA Post-graduate Educational Course in Radiation Protection and the Safe Use of Radiation Sources is regularly offered in countries around the world, and has been provided in Arabic, English, French, Spanish and Russian. The training provided by the IAEA is primarily aimed at regulators, professionals working in radiation protection and those responsible for the development of training programmes in their own countries. The importance of adequate and appropriate training for all those working with ionizing radiation has been highlighted by the results of the IAEA's investigations of radiological accidents. A significant contributory factor in a number of the accidents has been a lack of adequate training, which gave rise to errors with serious consequences. This report provides assistance in organizing training and complying with the requirements on training of the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources (BSS). The previous version of this report. Technical Reports

Upgrading inflatable door seals

International Nuclear Information System (INIS)

Sykes, T.M.; Metcalfe, R.; Welch, L.A.; Josefowich, J.M.

1997-01-01

Inflatable door seals are used for airlocks in CANDU stations. They have been a significant source of unreliability and maintenance cost. A program is underway to improve their performance and reliability, backed by environmental qualification testing. Only commercial products and suppliers existed in 1993. For historical reasons, these 'existing products' did not use the most durable material then available. In hindsight, neither had they been adapted nor optimized to combat conditions often experienced in the plants-sagging doors, damaged sealing surfaces, and many thousands of openings and closings per year. Initial attempts to involve the two existing suppliers in efforts to upgrade these seals were unsuccessful. Another suitable supplier had therefore to be found, and a 'new,' COG-owned seal developed; this was completed in 1997. This paper summarizes its testing, along with that of the two existing products. Resistance to aging has been improved significantly. Testing has shown that an accident can be safely withstood after 10 years of service or 40,000 openings-closings, whichever comes first. AECL's Fluid Sealing Technology Unit (FSTU) has invested in the special moulds, test fixtures and other necessary tooling and documentation required to begin commercial manufacture of this new quality product. Accordingly, as with FSTU's other nuclear products such as pump seals, the long-term supply of door seals to CANDU plants is now protected from many external uncertainties-e.g., commercial products being discontinued, materials being changed, companies going out of business. Manufacturing to AECL's detailed specifications is being subcontracted to the new supplier. FSTU is performing the quality surveillance, inspection, testing, and customer service activities concomitant with direct responsibility for supply to the plants. (author)

Regulatory aspects of radiation sources safety in Albania

International Nuclear Information System (INIS)

Dollani, K.; Kushe, R.

1998-01-01

In this paper are presented the regulatory aspects of the radiation sources safety in Albania, based in the new Radiological Protection Act and Regulations. The radiation protection infrastructures and procedures are described as well as their functioning for the implementation of relevant activities such as licensing and regular inspection, personal dose monitoring, emergency preparedness which are developed in the frame of the IAEA Technical Co-operation Programme. The issue of the security of radiation sources is dealt in close relation with the preparation and use of the inventory of all radiation sources in the country. A special attention is paid to the identification and location of lost sources for their finding and secure storage. (author)

Indirect detection of radiation sources through direct detection of radiolysis products

Science.gov (United States)

Farmer, Joseph C [Tracy, CA; Fischer, Larry E [Los Gatos, CA; Felter, Thomas E [Livermore, CA

2010-04-20

A system for indirectly detecting a radiation source by directly detecting radiolytic products. The radiation source emits radiation and the radiation produces the radiolytic products. A fluid is positioned to receive the radiation from the radiation source. When the fluid is irradiated, radiolytic products are produced. By directly detecting the radiolytic products, the radiation source is detected.

Synchrotron radiation sources: general features and vacuum system

International Nuclear Information System (INIS)

Craievich, A.F.

1985-01-01

In the last years the electron or positron storage rings, which were until 1970 only used for high energy physics experiments, begun to be built in several countries exclusively as electromagnetic radiation source (synchrotron radiation). The sources are generally made up by injector (linear accelerator or microtron), 'booster' (synchrotron), storage ring, insertions ('Wigglers' and ondulators) and light lines. The interest by these sources are due to the high intensity, large spectrum (from infrared to the X-rays), polarization and pulsed structure of the produced radiation. For the ultra-vacuum obtainement, necessary for the functioning storage rings (p=10 -9 Torr), several special procedures are used. In Brazil the Synchrotron Radiation National Laboratory of the CNPq worked out a conceptual project of synchrotron radiation source, whose execution should begin by the construction of the several components prototypes. (L.C.) [pt

Pressure Actuated Leaf Seals for Improved Turbine Shaft Sealing

Science.gov (United States)

Grondahl, Clayton

2006-01-01

This presentation introduces a shaft seal in which leaf seal elements are constructed from slotted shim material formed and layered into a frusto-conical assembly. Limited elastic deflection of seal leaves with increasing system pressure close large startup clearance to a small, non-contacting, steady state running clearance. At shutdown seal elements resiliently retract as differential seal pressure diminishes. Large seal clearance during startup and shutdown provides a mechanism for rub avoidance. Minimum operating clearance improves performance and non-contacting operation promises long seal life. Design features of this seal, sample calculations at differential pressures up to 2400 psid and benefit comparison with brush and labyrinth seals is documented in paper, AIAA 2005 3985, presented at the Advanced Seal Technology session of the Joint Propulsion Conference in Tucson this past July. In this presentation use of bimetallic leaf material will be discussed. Frictional heating of bimetallic leaf seals during a seal rub can relieve the rub condition to some extent with a change in seal shape. Improved leaf seal rub tolerance is expected with bimetallic material.

Estimates of radiation doses from various sources of exposure

International Nuclear Information System (INIS)

Anon.

1992-01-01

This chapter provides an overview of radiation doses to individuals and to the collective US population from various sources of ionizing radiation. Summary tables present doses from various sources of ionizing radiation. Summary tables present doses from occupational exposures and annual per capita doses from natural background, the healing arts, nuclear weapons, nuclear energy and consumer products. Although doses from non-ionizing radiation are not as yet readily available in a concise form, the major sources of non-ionizing radiation are listed

Radiation security regulation. 1st revision

International Nuclear Information System (INIS)

1984-01-01

Established are allowable maximum levels for personnel occupationally exposed to ionizing radiation in the ININ and for the public, in accordance with the international standards; defined are categories of radiation facilities, requirements and operating conditions that must be met. Demarcated are the kinds of placards to be posted in controlled and restricted areas and the signs, symbols and tags to be used, defined and established is environmental dosimetric and medical radiation monitoring. Regulated are methods for handling sealed and unsealed sources of radiation, work clothes, closing of radiation installations, storage, transfer and transport of radioactive material; classified are types of possible radiation accidents, action to be taken upon the occurrence and subsequent clean up. (corporate author)

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)

Plasma x-ray radiation source.

Science.gov (United States)

Popkov, N F; Kargin, V I; Ryaslov, E A; Pikar', A S

1995-01-01

This paper gives the results of studies on a plasma x-ray source, which enables one to obtain a 2.5-krad radiation dose per pulse over an area of 100 cm2 in the quantum energy range from 20 to 500 keV. Pulse duration is 100 ns. Spectral radiation distributions from a diode under various operation conditions of a plasma are obtained. A Marx generator served as an initial energy source of 120 kJ with a discharge time of T/4 = 10-6 s. A short electromagnetic pulse (10-7 s) was shaped using plasma erosion opening switches.

Ionizing radiations: effects and sources

International Nuclear Information System (INIS)

Vignes, S.; Nenot, J.C.

1978-01-01

Having first mentioned the effects of ionizing radiations in cancerogenisis, pre-natal, and genetic fields, the authors present the different sources of radiations and estimate their respective contributions to the total irradiation dose. Their paper makes reference to the main elements of a report issued by the United Nations Scientific Committee in 1977 [fr

Calibration and check light source

Energy Technology Data Exchange (ETDEWEB)

Nejedla, B; Krotil, J

1979-02-15

The light source is designed for calibrating photomultipliers and checking the function of the thermoluminescent dosemeters evaluation equipment. The check light source consists of a polymer material-based (polyvinyl toluene) plastic scintillator and a 2-phenyl-5-(4-bisphenyl)-1,3,4-oxadiazol and/or paraterphenyl activator, and of emission spectrum shifters for response in the green and the blue light regions. The plastic scintillator is sealed in a case to whose bottom a radiation source is fixed, such as a /sup 90/Sr-/sup 90/Y source of an activity of 1.85x10/sup 3/s/sup -1/ to 0.74x10/sup 9/s/sup -1/.

Safety quality classification test of the sealed neutron sources used in start-up neutron source rods for Qinshan Nuclear Power Plant

International Nuclear Information System (INIS)

Yao Chunbing; Guo Gang; Chao Jinglan; Duan Liming

1992-01-01

According to the regulations listed in the GB4075, the safety quality classification tests have been carried out for the neutron sources. The test items include temperature, external pressure, impact, vibration and puncture, Two dummy sealed sources are used for each test item. The testing equipment used have been examined and verified to be qualified by the measuring department which is admitted by the National standard Bureau. The leak rate of each tested sample is measured by UL-100 Helium Leak Detector (its minimum detectable leak rate is 1 x 10 -10 Pa·m 3 ·s -1 ). The samples with leak rate less than 1.33 x 10 -8 Pa·m 3 ·s -1 are considered up to the standard. The test results show the safety quality classification class of the neutron sources have reached the class of GB/E66545 which exceeds the preset class

The safety of radiation sources and radioactive materials in China

International Nuclear Information System (INIS)

Liu, H.

2001-01-01

The report describes the present infrastructure for the safety of radiation sources in China, where applications of radiation sources have become more and more widespread in the past years. In particular, it refers to the main functions of the National Nuclear Safety Administration of the State Environmental Protection Administration (SEPA), which is acting as the regulatory body for nuclear and radiation safety at nuclear installations, the Ministry of Public Health which issues licences for the use of radiation sources, and the Ministry of Public Security, which deals with the security of radiation sources. The report also refers to the main requirements of the existing regulatory system for radiation safety, i.e. the basic dose limits for radiation workers and the public, the licensing system for nuclear installations and for radioisotope-based and other irradiation devices, and the environmental impact assessment system. Information on the nationwide survey of radiation sources carried out by SEPA in 1991 is provided, and on some accidents that occurred in China due to loss of control of radiation sources and errors in the operation of irradiation facilities. (author)

The role of the Gosatomnadzor of Russia in national regulating of safety of radiation sources and security of radioactive materials

International Nuclear Information System (INIS)

Mikhailov, M.V.; Sitnikov, S.A.

2001-01-01

As at the end of 1999, the Gosatomnadzor of Russia supervised 6551 radiation sources, including 1285 unsealed sources with individual activity from a minimal level to 1x10 12 Bq and a total activity of 585x10 12 Bq, and also 5266 sealed sources with individual activity from 30 to 1x10 17 Bq and the total activity of more than 11x10 17 Bq. A national infrastructure has been created in the Russian Federation in order to regulate the safety of nuclear energy use. The infrastructure includes the legal system and the regulatory authorities based on and acting according to it. The regulation of radiation safety, including assurance of radiation source safety and radioactive material security (management of disused sources, planning, preparedness and response to abnormal events and emergencies, recovery of control over orphan sources, informing users and others who might be affected by lost source, and education and training in the safety of radiation sources and the security of radioactive materials), is realized within this infrastructure. The legal system includes federal laws ('On the Use of Nuclear Energy' and 'On Public Radiation Safety'), a number of decrees and resolutions of the President and the Government of the Russian Federation, federal standards and rules for nuclear energy use, and also departmental and industrial manuals and rules, State standards, construction standards and rules and other documents. The safety regulation tasks have been defined by these laws, according to which regulatory authorities are entrusted with the development, approval and putting into force of standards and rules in the nuclear energy use, with issuing licenses for carrying out nuclear activities, with safety supervision assurance, with review and inspection implementation, with control over development and realization of protective measures for workers, population and environment in emergencies at nuclear and radiation hazardous facilities. Russian national regulatory

Low frequency interference between short synchrotron radiation sources

Directory of Open Access Journals (Sweden)

F. Méot

2001-06-01

Full Text Available A recently developed analytical formalism describing low frequency far-field synchrotron radiation (SR is applied to the calculation of spectral angular radiation densities from interfering short sources (edge, short magnet. This is illustrated by analytical calculation of synchrotron radiation from various assemblies of short dipoles, including an “isolated” highest density infrared SR source.

[Use of ionizing radiation sources in metallurgy: risk assessment].

Science.gov (United States)

Giugni, U

2012-01-01

Use of ionizing radiation sources in the metallurgical industry: risk assessment. Radioactive sources and fixed or mobile X-ray equipment are used for both process and quality control. The use of ionizing radiation sources requires careful risk assessment. The text lists the characteristics of the sources and the legal requirements, and contains a description of the documentation required and the methods used for risk assessment. It describes how to estimate the doses to operators and the relevant classification criteria used for the purpose of radiation protection. Training programs must be organized in close collaboration between the radiation protection expert and the occupational physician.

VAK III. Seals and sealing system

International Nuclear Information System (INIS)

d'Agraives, B.C.; Dal Cero, G.; Debeir, R.; Mascetti, E.; Toornvliet, J.; Volcan, A.

1986-01-01

This report presents the VAK III seals and sealing system, which have been used over a period of two years at the Kahl nuclear facility (Federal Republic of Germany), where field tests and feasibility studies were conducted in order to offer a possible solution for the sealing of LWR fuel assemblies. It has been prepared with the aim of an assessment study to be done at the IAEA. It gives all characteristics and technical descriptions for: the sealing principle, the seal construction, the operating tools, the data processing, the drawings, the publications related to that seal. The main points of progress are: the Strong Random Internal Defects (STRID) incorporated in the seals, allowing the obtention of a good signature stability; the Integrity Check on the Seal Status (broken or not) obtained through a decisive mechanical improvement: the Double Breakage Integrity Check (DOBRIC) and with a better ultrasonic evidence of that status; the provision of new function tools, allowing the performance of Identity Measurements in dry conditions (which means also at the manufacturer plant) or in deeper water (wet storage); the study and development of a new JRC VAK 45 Compact Instrument Box, in which all the measuring functions can be grouped and incorporating an autonomous Minicomputer offering to the Inspection the possibility of performing, on the spot, Correlation and Decision processes. The general benefit of such a feasibility study should be to convince the potential users that such a Safeguards Sealing System can be studied for slightly - or largely - different other applications, provided that the Basic and Operating Functions required to the system be clearly defined, possibly after a common agreement would be stated

Carbon sources and trophic relationships of ice seals during recent environmental shifts in the Bering Sea.

Science.gov (United States)

Wang, Shiway W; Springer, Alan M; Budge, Suzanne M; Horstmann, Lara; Quakenbush, Lori T; Wooller, Matthew J

2016-04-01

Dramatic multiyear fluctuations in water temperature and seasonal sea ice extent and duration across the Bering-Chukchi continental shelf have occurred in this century, raising a pressing ecological question: Do such environmental changes alter marine production processes linking primary producers to upper trophic-level predators? We examined this question by comparing the blubber fatty acid (FA) composition and stable carbon isotope ratios of individual FA (δ¹³CFA) of adult ringed seals (Pusa hispida), bearded seals (Erignathus barbatus), spotted seals (Phoca largha), and ribbon seals (Histriophoca fasciata), collectively known as "ice seals," sampled during an anomalously warm, low sea ice period in 2002-2005 in the Bering Sea and a subsequent cold, high sea ice period in 2007-2010. δ¹³C(FA) values, used to estimate the contribution to seals of carbon derived from sea ice algae (sympagic production) relative to that derived from water column phytoplankton (pelagic production), indicated that during the cold period, sympagic production accounted for 62-80% of the FA in the blubber of bearded seals, 51-62% in spotted seals, and 21-60% in ringed seals. Moreover, the δ¹³CFA values of bearded seals indicated a greater incorporation of sympagic FAs during the cold period than the warm period. This result provides the first empirical evidence of an ecosystem-scale effect of a putative change in sympagic production in the Western Arctic. The FA composition of ice seals showed clear evidence of resource partitioning among ringed, bearded, and spotted seals, and little niche separation between spotted and ribbon seals, which is consistent with previous studies. Despite interannual variability, the FA composition of ringed and bearded seals showed little evidence of differences in diet between the warm and cold periods. The findings that sympagic production contributes significantly to food webs supporting ice seals, and that the contribution apparently is less in

Radiation protection with consumer products containing gaseous tritium light sources

International Nuclear Information System (INIS)

Rahders, Erio; Haeusler, Uwe

2017-01-01

Consumer products containing gaseous tritium light sources (GTLS) were examined with respect to their radiological safety potential regarding leak tightness or accidents. The maximum tritium leakage rate of 2.7 Bq/d determined from experimental testing is well below the criterion for leak tightness of sealed radioactive sources in DIN 25426-4. In order to investigate the incorporation of tritium due to contact with consumer products, 2 scenarios were reviewed; the correct use of a tritium watch and the accident scenario with a keyring.

A case of a found radiographic source

International Nuclear Information System (INIS)

Pucelj, B.; Korun, M.; Kavsek, D.; Kreft, Z.; Krizman, M.; Martincic, R.; Rosman, M.; Sutej, T.

1996-01-01

High dose-rate levels were detected outdoors in the vicinity of a bunker used for storage of radiographic sources in a plant which manufactures metallic products. The investigation revealed that radiation was due to a buried sealed radiographic source, containing 28 GBq of 137 Cs. A special republic radiological emergency team removed the source in a carefully planned operation. There was no evidence for overexposure of the population or of radiographic and other workers of the plant. The highest dose to the recovery team was 50 μSv

Regulatory control of radiation sources. Safety guide

International Nuclear Information System (INIS)

2004-01-01

The basic requirements for the protection of persons against exposure to ionizing radiation and for the safety of radiation sources were established in the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources (the Basic Safety Standards), jointly sponsored by the Food and Agriculture Organization of the United Nations (FAO), the International Atomic Energy Agency (IAEA), the International Labour Organization (ILO), the OECD Nuclear Energy Agency (OECD/ NEA), the Pan American Health Organization (PAHO) and the World Health Organization (WHO) (the Sponsoring Organizations). The application of the Basic Safety Standards is based on the presumption that national infrastructures are in place to enable governments to discharge their responsibilities for radiation protection and safety. Requirements relating to the legal and governmental infrastructure for the safety of nuclear facilities and sources of ionizing radiation, radiation protection, the safe management of radioactive waste and the safe transport of radioactive material are established in the Safety Requirements on Legal and Governmental Infrastructure for Nuclear, Radiation, Radioactive Waste and Transport Safety, Safety Standards Series No. GS-R-1. This Safety Guide, which is jointly sponsored by the FAO, the IAEA, the International Labour Office, the PAHO and the WHO, gives detailed guidance on the key elements for the organization and operation of a national regulatory infrastructure for radiation safety, with particular reference to the functions of the national regulatory body that are necessary to ensure the implementation of the Basic Safety Standards. The Safety Guide is based technically on material first published in IAEA-TECDOC-10671, which was jointly sponsored by the FAO, the IAEA, the OECD/NEA, the PAHO and the WHO. The requirements established in GS-R-1 have been taken into account. The Safety Guide is oriented towards national

Control of radioisotopes and radiation sources in Indonesia

International Nuclear Information System (INIS)

Ridwan, M.

2001-01-01

Radioisotopes and radiation sources are extensively used in Indonesia in medicine, industry, mining, agriculture and research. These materials are controlled by the regulatory authority, according to established legal procedures. The Nuclear Energy Control Board of Indonesia (BAPETEN), which was established in 1998 through the Nuclear Energy Act No. 10/1997, is entrusted with the control of any application of nuclear energy, including the application of radioisotopes and radiation sources, through regulation, licensing and inspection. The control is aimed to assure welfare, security and peace, the safety and health of workers and the public, and environmental protection. The number of licences issued to date is around 2400, consisting of 1600 licences for radioisotopes and radiation sources used in hospitals, 347 in radiography, 256 in industry, 53 in mining, and the rest in many other areas such as research and agriculture. A licence can cover one or more radioisotopes or radiation sources, depending on the location of the user institution. These radioisotopes and radiation sources are Co-60, Cs-137, Ir-192, Ra-226, Am-241, Sr-90, Kr-85, Pm-147, linear accelerator and X-ray, and short half-life radioisotopes such as I-125, I-131 and Tc-99m. There are 10 LINACs, 27 X-ray medicines, 61 radioisotope devices for Co-60 and Cs-137, and 10 mHDR Ir-192 for therapeutic purposes currently used in Indonesia and some Ra-226 in storage. Any activity related to the application of nuclear energy is required to be conducted in a manner which observes safety and security. According to the legal requirements, each user has to employ at least one radiation safety officer. To improve the control of the application of radiation sources and radioactive material in the country, BAPETEN introduced some new approaches to the users, including regular dialogues with radiation safety officers and the management of the users, requalification for radiation protection officers twice in five

Study of classification and disposed method for disused sealed radioactive source in Korea

Energy Technology Data Exchange (ETDEWEB)

Kim, Suk Hoon; Kim, Ju Youl; Lee, Seung Hee [FNC Technology Co., Ltd.,Yongin (Korea, Republic of)

2016-09-15

In accordance with the classification system of radioactive waste in Korea, all the disused sealed radioactive sources (DSRSs) fall under the category of EW, VLLW or LILW, and should be managed in compliance with the restrictions for the disposal method. In this study, the management and disposal method are drawn in consideration of half-life of radionuclides contained in the source and A/D value (i.e. the activity A of the source dividing by the D value for the relevant radionuclide, which is used to provide an initial ranking of relative risk for sources) in addition to the domestic classification scheme and disposal method, based on the characteristic analysis and review results of the management practices in IAEA and foreign countries. For all the DSRSs that are being stored (as of March 2015) in the centralized temporary disposal facility for radioisotope wastes, applicability of the derivation result is confirmed through performing the characteristic analysis and case studies for assessing quantity and volume of DSRSs to be managed by each method. However, the methodology derived from this study is not applicable to the following sources; i) DSRSs without information on the radioactivity, ii) DSRSs that are not possible to calculate the specific activity and/or the source-specific A/D value. Accordingly, it is essential to identify the inherent characteristics for each of DSRSs prior to implementation of this management and disposal method.

Remote vacuum or pressure sealing device and method for critical isolated systems

Science.gov (United States)

Brock, James David [Newport News, VA; Keith, Christopher D [Newport News, VA

2012-07-10

A remote vacuum or pressure sealing apparatus and method for making a radiation tolerant, remotely prepared seal that maintains a vacuum or pressure tight seal throughout a wide temperature range. The remote sealing apparatus includes a fixed threaded sealing surface on an isolated system, a gasket, and an insert consisting of a plug with a protruding sample holder. An insert coupling device, provided for inserting samples within the isolated system, includes a threaded fastener for cooperating with the fixed threaded sealing surface on the isolated system. The insert coupling device includes a locating pin for azimuthal orientation, coupling pins, a tooted coaxial socket wrench, and an insert coupling actuator for actuating the coupling pins. The remote aspect of the sealing apparatus maintains the isolation of the system from the user's environment, safely preserving the user and the system from detrimental effect from each respectively.

Design of analytical instrumentation with D-T sealed neutron generators

International Nuclear Information System (INIS)

Qiao Yahua; Wu Jizong; Zheng Weiming; Liu Quanwei; Zhang Min

2008-01-01

Analytical instrumentation with D-T sealed neutron generators source activation, The 14 MeV D-T sealed neutron tube with 10 9 n · s -1 neutron yield is used as generator source. The optimal structure of moderator and shield was achieved by MC computing.The instrumentation's configuration is showed. The instrumentation is made up of the SMY-DT50.8-2.1 sealed neutron tube and the high-voltage power supply system, which center is the sealed neutron generators. 6 cm Pb and 20 cm polythene is chosen as moderator, Pb, polythene and 10 cm boron-PE was chosen as shield .The sample box is far the source from 9 cm, the measurement system were made up of HPGe detector and the sample transforming system. After moderator and shield, the thermal neutron fluence rate at the point of sample is 0.93 × 10 6 n · s -1 cm -2 , which is accorded with design demand, and the laboratory and surroundings reaches the safety standard of the dose levels. (authors)

Device for verification of seals by optical fibers

International Nuclear Information System (INIS)

Neuilly, M.; Guitaud, M.H.; Dufour, J.L.

1993-01-01

The seal is built around an optical fiber with a verification device. This device is made of a lighting source and photographic means supported by a rotating assembly which allow to take an image of each optical fiber end. These images are compared with reference images taken just after the sealing. (A.B.). 5 refs., 6 figs

WADOSE, Radiation Source in Vitrification Waste Storage Apparatus

International Nuclear Information System (INIS)

Morita, Jun-ichi; Tashiro, Shingo; Kikkawa, Shizuo; Tsuboi, Takashi

2007-01-01

1 - Description of program or function: This is a radiation shielding program which analyzes unknown dose rates using known radiation sources. It can also evaluate radiation sources from measured dose rates. For instance, dose rates measured at several points in the hot cell of WASTEF are introduced into WADOS, and as a result, Ci of radiation sources and their positions are estimated with structural arrangement data of the WASTEF cells. The later functional addition is very useful for actual operation of a hot cell and others. NEA-1142/02: The code was originally written in non standard Fortran dialect and has been fully translated into Fortran 90, Fortran 77 compatible. 2 - Method of solution: Point kernel ray tracing method (the same method as QAD code). 3 - Restrictions on the complexity of the problem: Modeling of source form for input is available for cylinder, plate, point and others which are simplified geometrically

Disk shaped radiation sources for education purposes made of chemical fertilizer

International Nuclear Information System (INIS)

Kawano, Takao

2008-01-01

A method for fabricating a disk-shaped radiation source from material containing natural radioisotopes was developed. In this compression and formation method, a certain amount of powdered material is placed in a stainless steel formwork and compressed to form a solid disk. Using this method, educational radiation sources were fabricated using commercially available chemical fertilizers that naturally contain the radionuclide, 40 K, which emits either beta or gamma rays, at each disintegration. The compression and formation method was evaluated by inspecting eleven radiation sources thus fabricated. Then the suitability of the fertilizer radiation source as an education aid was evaluated. The results showed that the method could be used to fabricate radiation sources without the need for learning special skills or techniques. It was also found that the potassium fertilizer radiation source could be used to demonstrate that the inverse-square law can be applied to the distance between the radiation source and detector, and that an exponential relationship can be seen between the shielding effectiveness and the total thickness of the shielding materials. It is concluded that a natural fertilizer radiation source is an appropriate aid for demonstrating the characteristics of radiation. (author)

Establishing control over nuclear materials and radiation sources in Georgia

International Nuclear Information System (INIS)

Basilia, G.

2010-01-01

Regulatory control over radiation sources in Georgia was lost after disintegration of the Soviet Union. A number of radiation accidents and illegal events occurred in Georgia. From 1999 Nuclear and Radiation Safety Service of the Ministry of Environmental Protection and Natural Resources is responsible for regulatory control over radiation sources in Georgia. US NRC Regulatory Assistance Program in Georgia Assist the Service in establishing long term regulatory control over sources. Main focuses of US NRC program are country-wide inventory, create National Registry of sources, safe storage of disused sources, upgrade legislation and regulation, implementation licensing and inspection activities

Sealing device

Science.gov (United States)

Garcia-Crespo, Andres Jose

2013-12-10

A sealing device for sealing a gap between a dovetail of a bucket assembly and a rotor wheel is disclosed. The sealing device includes a cover plate configured to cover the gap and a retention member protruding from the cover plate and configured to engage the dovetail. The sealing device provides a seal against the gap when the bucket assemply is subjected to a centrifugal force.

Optical Imaging of Ionizing Radiation from Clinical Sources.

Science.gov (United States)

Shaffer, Travis M; Drain, Charles Michael; Grimm, Jan

2016-11-01

Nuclear medicine uses ionizing radiation for both in vivo diagnosis and therapy. Ionizing radiation comes from a variety of sources, including x-rays, beam therapy, brachytherapy, and various injected radionuclides. Although PET and SPECT remain clinical mainstays, optical readouts of ionizing radiation offer numerous benefits and complement these standard techniques. Furthermore, for ionizing radiation sources that cannot be imaged using these standard techniques, optical imaging offers a unique imaging alternative. This article reviews optical imaging of both radionuclide- and beam-based ionizing radiation from high-energy photons and charged particles through mechanisms including radioluminescence, Cerenkov luminescence, and scintillation. Therapeutically, these visible photons have been combined with photodynamic therapeutic agents preclinically for increasing therapeutic response at depths difficult to reach with external light sources. Last, new microscopy methods that allow single-cell optical imaging of radionuclides are reviewed. © 2016 by the Society of Nuclear Medicine and Molecular Imaging, Inc.

Postgraduate educational course in radiation protection and the safety of radiation sources. Standard syllabus

International Nuclear Information System (INIS)

2003-01-01

The aim of the Postgraduate Educational Course in Radiation Protection and the Safety of Radiation Sources is to meet the needs of professionals at graduate level, or the equivalent, for initial training to acquire a sound basis in radiation protection and the safety of radiation sources. The course also aims to provide the necessary basic tools for those who will become trainers in radiation protection and in the safe use of radiation sources in their countries. It is designed to provide both theoretical and practical training in the multidisciplinary scientific and/or technical bases of international recommendations and standards on radiation protection and their implementation. The participants should have had a formal education to a level equivalent to a university degree in the physical, chemical or life sciences or engineering and should have been selected to work in the field of radiation protection and the safe use of radiation sources in their countries. The present revision of the Standard Syllabus takes into account the requirements of the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources (BSS), IAEA Safety Series No. 115 (1996) and recommendations of related Safety Guides, as well as experience gained from the Postgraduate Educational Course on Radiation Protection and Safety of Radiation Sources held in several regions in recent years. The general aim of the course, as mentioned, is the same. Some of the improvements in the present version are as follows: The learning objective of each part is specified. The prerequisites for each part are specified. The structure of the syllabus has been changed: the parts on Principles of Radiation Protection and on Regulatory Control were moved ahead of Dose Assessment and after Biological Effects of Radiation. The part on the interface with nuclear safety was dropped and a module on radiation protection in nuclear power plants has been included. A

Postgraduate educational course in radiation protection and the safety of radiation sources. Standard syllabus

International Nuclear Information System (INIS)

2002-01-01

The aim of the Postgraduate Educational Course in Radiation Protection and the Safety of Radiation Sources is to meet the needs of professionals at graduate level, or the equivalent, for initial training to acquire a sound basis in radiation protection and the safety of radiation sources. The course also aims to provide the necessary basic tools for those who will become trainers in radiation protection and in the safe use of radiation sources in their countries. It is designed to provide both theoretical and practical training in the multidisciplinary scientific and/or technical bases of international recommendations and standards on radiation protection and their implementation. The participants should have had a formal education to a level equivalent to a university degree in the physical, chemical or life sciences or engineering and should have been selected to work in the field of radiation protection and the safe use of radiation sources in their countries. The present revision of the Standard Syllabus takes into account the requirements of the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources (BSS), IAEA Safety Series No. 115 (1996) and recommendations of related Safety Guides, as well as experience gained from the Postgraduate Educational Course on Radiation Protection and Safety of Radiation Sources held in several regions in recent years. The general aim of the course, as mentioned, is the same. Some of the improvements in the present version are as follows: The learning objective of each part is specified. The prerequisites for each part are specified. The structure of the syllabus has been changed: the parts on Principles of Radiation Protection and on Regulatory Control were moved ahead of Dose Assessment and after Biological Effects of Radiation. The part on the interface with nuclear safety was dropped and a module on radiation protection in nuclear power plants has been included. A

Categorization of radioactive sources. Revision of IAEA-TECDOC-1191, Categorization of radiation sources

International Nuclear Information System (INIS)

2003-07-01

Radioactive sources are used throughout the world for a wide variety of peaceful purposes in industry, medicine, agriculture, research and education; and they are also used in military applications. The International Basic Safety Standards provide an internationally harmonized basis for ensuring the safe and secure use of sources of ionizing radiation. Because of the wide variety of uses and activities of radiation sources, a categorization system is necessary so that the controls that are applied to the sources are commensurate with the radiological risks. In September 1998, following an assessment of the major findings of the first International Conference on the Safety of Radiation Sources and the Security of Radioactive Materials, held in Dijon, France, from 14 to 18 September 1998 (the Dijon Conference), the IAEA's General Conference (in resolution GC(42)/RES/12), inter alia, encouraged all governments 'to take steps to ensure the existence within their territories of effective national systems of control for ensuring the safety of radiation sources and the security of radioactive materials' and requested the Secretariat 'to prepare for the consideration of the Board of Governors a report on: (i) how national systems for ensuring the safety of radiation sources and the security of radioactive materials can be operated at a high level of effectiveness; and, (ii) whether international undertakings concerned with the effective operation of such systems and attracting broad adherence could be formulated'. In February 1999, the Secretariat submitted to the IAEA Board of Governors a report prepared in response to the request made of it by the General Conference. The Board took up the report at its March 1999 session and, inter alia, requested the Secretariat to prepare an action plan that took into account the conclusions and recommendations in the report, and the Board's discussion of the report. In August 1999, the Secretariat circulated a proposed Action Plan for

STUDY ON THERMAL DEFORMATIONS OF THE PRIMARY SEALING OF FRONT SEALING

Directory of Open Access Journals (Sweden)

Mihaela ISTRATE

2015-05-01

Full Text Available The thermal phenomena appear at the level of the film within the primary sealing interstitium. An important temperature gradient is performed in the stator and in the rotor, which produces thermoelastic deformations. These deformations are of the order of film width and affect essentially the interstitium geometry. According to the temperature increase direction the repartition in the friction ring is different. The farthest areas from the temperature drops or the nearest to the heat sources will have he highest temperature. These dilate more that the rest of the areas and modify the interstitium form. From the calculation relations it comes out that deformations depend also on certain operating conditions, which can be modified through time (pressure, temperature, the sealing efficiency being thus different in time.

Use of radiation technologies in agriculture and medicine

International Nuclear Information System (INIS)

Petukhov, V.K.; Chekushin, A.I.

1994-01-01

The most important directions of radiation and radiation biological technologies in the agriculture and medicine are elucidated. Kazakstan have possibility for application radiation technologies. There is powerful irradiation plant on the base of WWR-K reactor such could use for medicine materials sterilization. Has been proposed gamma-radiation plant with following technical characteristics: sources activity - 100-120 Ku; effective energy of radiation - 0,6-0,7 MeV; gamma-radiation use coefficient - 35 %; irradiation dose rate - 30-40 R/c; nonuniform irradiation rate - 12 %. Processing tools have being situated to hermetically sealed cylindrical container (height - 2 m; diameter - 1,2 m) and then have being put down under water towards gamma-irradiators

Development of Yb-169 radiation source for new nondestructive inspection

International Nuclear Information System (INIS)

Yamabayashi, Hisamichi

1994-01-01

As the nondestructive inspection method for large structures, there has been radiography, and X-ray and γ-ray have been used as the radiation. The transmissivity of radiation through materials changes by the energy of the radiation and the density and thickness of the materials. At present about 880 γ-ray radiography apparatuses are used in Japanese private enterprises, and about 70% of them use 192 Ir γ-ray sources, and about 30% use 60 Co or 137 Cs sources. Recently the defect inspection for the worlded parts of thin wall small tubes and so on have become to be regarded as important, and the 169 Yb source that emits lower energy γ-ray is suitable to the purpose. There are many reports that 169 Yb radiography was applied successfully. As the 169 Yb radiation source, pellets and balls are on the market. 169 Yb is made by the neutron irradiation of 168 Yb in nuclear reactors. The characteristics of 169 Yb, the manufacture of 169 Yb radiation sources and the applicability of 169 Yb radiation sources to nondestructive inspection are reported. Also in Japan, many basic experiments on 169 Yb radiation sources have been carried out, and the irradiation apparatuses are small and light, and the control area can be set small. (K.I.)

Radiation sources and process

International Nuclear Information System (INIS)

Honious, H.B.; Janzow, E.F.; Malson, H.A.; Moyer, S.E.

1980-01-01

The invention relates to radiation sources comprising a substrate having an electrically-conductive non-radioactive metal surface, a layer of a metal radioactive isotope of the scandium group, which in addition to scandium, yttrium, lanthanum and actinium, includes all the lanthanide and actinide series of elements, with the actinide series usually being preferred because of the nature of the radioactive isotopes therein, particularly americium-241, curium-244, plutonium-238, californium-252 and promethium-147, and a non-radioactive bonding metal codeposited on the surface by electroplating the isotope and bonding metal from an electrolytic solution, the isotope being present in the layer in minor amount as compared to the bonding metal, and with or without a non-radioactive protective metal coating covering the isotoype and bonding metal on the surface, the coating being sufficiently thin to permit radiation to pass through the coating. The invention also relates to a process for providing radiation sources comprising codepositing a layer of the metal radioactive isotope with a non-radioactive bonding metal from an electrolytic solution in which the isotope is present in minor molar amount as compared to the bonding metal such that the codeposited layer contains a minor molar amount of the isotope compared to the bonding metal by electroplating on an electrically-conductive non-radioactive metal surface of a cathode substrate, and with or without depositing a nonradioactive protective metal coating over the isotope and bonding metal on the surface, the coating being sufficiently thin to permit radiation to pass through the coating

Overview of terahertz radiation sources

International Nuclear Information System (INIS)

Gallerano, G.P.; Biedron, S.G.

2004-01-01

Although terahertz (THz) radiation was first observed about hundred years ago, the corresponding portion of the electromagnetic spectrum has been for long time considered a rather poorly explored region at the boundary between the microwaves and the infrared. This situation has changed during the past ten years with the rapid development of coherent THz sources, such as solid state oscillators, quantum cascade lasers, optically pumped solid state devices and novel free electron devices, which have in turn stimulated a wide variety of applications from material science to telecommunications, from biology to biomedicine. For a comprehensive review of THz technology the reader is addressed to a recent paper by P. Siegel. In this paper we focus on the development and perspectives of THz radiation sources.

Sealing Failure Analysis on V-Shaped Sealing Rings of an Inserted Sealing Tool Used for Multistage Fracturing Processes

Directory of Open Access Journals (Sweden)

Gang Hu

2018-06-01

Full Text Available The inserted sealing tool is a critical downhole implement that is used to balance the downhole pressure in multistage fracturing operations and prevent fracturing fluid from overflow and/or backward flow. The sealing ring of an inserted sealing tool plays an important role in downhole sealing since a sealing failure would ail the fracturing operation. In order to improve the sealing performance and reduce the potential fracturing failures, this research aims to investigate the influence of V-shaped sealing ring geometries on sealing performance. Constitutive experiments of rubber materials were carried out and the parameters of the constitutive relationship of rubber materials were obtained. A two-dimensional axisymmetric model considering the sealing ring has been established and influences are investigated with considerations of various system parameters and operating conditions. It is found that the stresses concentrated at the shoulder and inner vertex of the sealing ring have direct impact on the damage of the sealing rings under operational conditions. Moreover, the sealing interference, among several other factors, greatly affects the life of the sealing ring. A new design of the sealing ring is suggested with optimized geometric parameters. Its geometric parameters are the edge height of 5 mm, the vertex angle of 90°–100°, and the interference of 0.1 mm, which show a better performance and prolonged operation life of the sealing ring.

Radiation protection safety in Uganda -- Experience and prospects of the National Radiation Protection Service

International Nuclear Information System (INIS)

Kisolo, A.

2001-01-01

The Uganda National Radiation Protection Service (NRPS) is a technical body under the Atomic Energy Control Board, established by Law - the Atomic Energy Decree of 1972, Decree No. 12, to oversee and enforce safety of radiation sources, practices and workers; and to protect the patients, members of the public and the environment from the dangers of ionizing radiation and radioactive wastes. The Ionizing Radiation Regulations (Standards) - Statutory Instruments Supplement No. 21 of 1996 -- back up the Law. The Law requires all users, importers and operators of radiation sources and radioactive materials to notify the NRPS for registration and licensing. The NRPS is responsible for licensing and for the regulatory enforcement of compliance to the requirements for the safety of radiation sources and practices. There are about 200 diagnostic X-ray units, two radiotherapy centres, one nuclear medicine unit, several neutron probes, about three level gauges and two non-destructive testing sources and a number of small sealed sources in teaching and research institutions. About 50% of these sources have been entered in our inventory using the RAIS software provided by the IAEA. There are about 500 radiation workers and 250 underground miners. The NRPS covers about 50% of the radiation workers. It is planned that by June 2001, all occupational workers will be monitored, bringing coverage to 100%. The Government of Uganda is making the necessary legal, administrative and technical arrangements aimed at establishing the National Radiation Protection Commission as an autonomous regulatory authority. The Atomic Energy Decree of 1972 and Regulations of 1996 are being revised to provide for the National Radiation Protection Commission and to make it comply with the requirements of the International Basic Safety Standards Safety Series No. 115. (author)

All-fiber femtosecond Cherenkov radiation source

DEFF Research Database (Denmark)

Liu, Xiaomin; Lægsgaard, Jesper; Møller, Uffe

2012-01-01

-conversion medium, we demonstrate milliwatt-level, stable, and tunable Cherenkov radiation at visible wavelengths 580–630 nm, with pulse duration of sub-160-fs, and the 3 dB spectral bandwidth not exceeding 36 nm. Such an all-fiber Cherenkov radiation source is promising for practical applications in biophotonics...

Devices for obtaining information about radiation sources

International Nuclear Information System (INIS)

Tosswill, C.H.

1981-01-01

The invention provides a sensitive, fast high-resolution device for obtaining information about the distribution of gamma and X-radiation sources and provides a radiation detector useful in such a device. It comprises a slit collimator with a multiplicity of slits each with slit-defining walls of material and thickness to absorb beam components impinging on them. The slits extend further in one direction than the other. The detector for separately detecting beam components passing through the slits also provides data output signals. It comprises a plurality of radiation transducing portions which are not photoconductor elements each at the end of a slit. A positioner operates to change the transverse position of the slits and radiation transducing portions relative to the source, wherein each radiation transducing element is positioned within its respective slit between the slit defining walls. Full details and preferred embodiments are given. (U.K.)

Upgrading elastomer seals for nuclear service

Energy Technology Data Exchange (ETDEWEB)

Wittich, K C; Wensel, R; LaRose, R; Kuran, S

1995-06-01

Pumps, valves and instruments in nuclear plants have historically contained whatever elastomer each equipment supplier traditionally used for corresponding non-nuclear service. The proliferation of elastomer compounds, and their sometimes uncertain reliability, is now being reduced by upgrading and standardizing on a handful of compounds that have each been verified to be high performers for their class of service conditions. The objective is to make cost-effective improvements in the reliability and integrity of equipment in Canadian-designed nuclear plants. The effort focuses on elastomer seals and includes: understanding sealing fundamentals, developing relevant data for superior compounds for each service, and improving quality assurance methods, including handling and inspection guidelines. In practice, discussions with plant personnel and review of plant records are the first step. Two severe-service examples are given where these needs have been met by the following progression of activities: inspecting and laboratory testing of seals removed from service, preliminary and qualification testing of improvements, introduction into service, and monitoring the upgraded seals during phase-in periods. Large gains in reliability and integrity have been demonstrated for simulated normal and accident service conditions of heat, radiation and other deteriorative influences. Significant savings in maintenance costs are also projected. (author). 2 refs., 6 figs.

Upgrading elastomer seals for nuclear service

International Nuclear Information System (INIS)

Wittich, K.C.; Wensel, R.; LaRose, R.; Kuran, S.

1995-06-01

Pumps, valves and instruments in nuclear plants have historically contained whatever elastomer each equipment supplier traditionally used for corresponding non-nuclear service. The proliferation of elastomer compounds, and their sometimes uncertain reliability, is now being reduced by upgrading and standardizing on a handful of compounds that have each been verified to be high performers for their class of service conditions. The objective is to make cost-effective improvements in the reliability and integrity of equipment in Canadian-designed nuclear plants. The effort focuses on elastomer seals and includes: understanding sealing fundamentals, developing relevant data for superior compounds for each service, and improving quality assurance methods, including handling and inspection guidelines. In practice, discussions with plant personnel and review of plant records are the first step. Two severe-service examples are given where these needs have been met by the following progression of activities: inspecting and laboratory testing of seals removed from service, preliminary and qualification testing of improvements, introduction into service, and monitoring the upgraded seals during phase-in periods. Large gains in reliability and integrity have been demonstrated for simulated normal and accident service conditions of heat, radiation and other deteriorative influences. Significant savings in maintenance costs are also projected. (author). 2 refs., 6 figs

Upgrading elastomer seals for nuclear service

International Nuclear Information System (INIS)

Wittich, K.C.; Wensel, R.; Larose, R.; Kuran, S.

1998-01-01

Pumps, valves and instruments in nuclear plants have historically contained whatever elastomer each equipment supplier traditionally used for corresponding non-nuclear service. The proliferation of elastomer compounds, and their sometimes uncertain reliability, is now being reduced by upgrading and standardizing on a handful of compounds that have each been verified to be high performers for their class of service conditions. The objective is to make cost-effective improvements in the reliability and integrity of equipment in Canadian-designed nuclear plants. The effort focuses on elastomer seals and includes: understanding sealing fundamentals, developing relevant data for superior compounds for each service, and improving quality assurance methods, including handling and inspection guidelines. In practice, discussion with plant personnel and review of plant records are the first step. Two severe-service examples are given where these needs have been met by the following progression of activities: inspecting and laboratory testing of seals removed from service, preliminary and qualification testing of improvements, introduction into service, and monitoring the upgraded seals during phase-in periods. Large gains in reliability and integrity have been demonstrated for simulated normal and accident service conditions of heat, radiation and other deteriorative influences. Significant savings in maintenance costs are also projected. (author)

Radiation survey of aircraft and heavy machinery scrap.

Science.gov (United States)

Idriss, Hajo; Salih, Isam; Gumaa, Elsadig; Yassin, Abbas; Yousif, E H; Abdel Hamid, Saad Eldeen M; Sam, A K

2012-12-01

This study was conducted primarily to survey aircraft and heavy machinery at 30 locations within Khartoum State using handheld radiation survey meters to detect and identify any radiation sources that might be present and to estimate radiation dose levels. The survey has resulted in detection of 16 sealed sources of (90)Sr and one of (226)Ra in aircraft scrap. Of course, (90)Sr sources are used in military aircraft as temperature sensors while (226)Ra is used for indicating fuel levels. These sources were found intact without spreading radioactivity contamination; however, none was detected in heavy machine scrap. The levels of radiation dose measured at 0.1m from the source fall within the range of 25.1-40.2 μSv/h with an average value of 33.52 ± 4.06 μSv/h. These orphan sources have been separated from the scrap, tested for possible leakage, conditioned and stored in waste management facility. The result of this study has revealed without doubt that the scrap constitute a serious source of public exposure and highlights the importance of legislation making radiation monitoring of scrap in the country mandatory before it is sold to metal industry for reprocessing. Copyright © 2012 Elsevier Ltd. All rights reserved.

Natural radiation source fabricated from commercially available instant coffee

International Nuclear Information System (INIS)

Kawano, Takao; Ando, Yoshiaki; Izumi, Yuuichi

2015-01-01

Commercially available instant coffee, Nescafe Excella, contained the radionuclide 40 K. From the instant coffee, sixteen coffee-block radiation sources were successfully fabricated with sufficiently low production dependences. The coffee-block radiation sources were examined their suitability for a radiation protection course. Although a part of radiation counts(cpm) obtained with 1 minute measurement were largely deviated, those determined by 5 minute measurements and five times of 1 minute measurement were less deviated, enabling better comprehension of the three cardinal principles of radiation protection. (author)

Protection in handling ionizing radiation sources in national economy

International Nuclear Information System (INIS)

1986-01-01

The collection of study texts is divided into 13 chapters giving an explanation of the structure of the atom, the properties of ionizing radiation and its interactions, quantities and units used, basic dosimetric methods, biological radiation effects, the sources of population exposure, the principles of radiation protection, technological applications of ionizing radiation, the monitoring of personnel and environment, the method of recording and filing, the method of protection from external radiation and internal contamination, health care, and requirements for protection in handling nonsealed sources. (M.D.)

Regulatory control and safety of radiation and radioactive sources in Bangladesh

International Nuclear Information System (INIS)

Mollah, A.S.

2001-01-01

The application of ionizing radiation and radioactive sources in different fields such as, medicine, industry, agriculture, research and teaching is constantly increasing in Bangladesh. Any system enacted to control exposure to ionizing radiation has as primary objective the protection of health of people against the deleterious effects of radiation. Establishing the appropriate level of radiological protection and safety of radiation sources used in practice or intervention attains this objective. The regulatory program governing the safe use of radioactive and radiation sources in Bangladesh is based on the legislation enacted as Nuclear Safety and Radiation Control (NSRC) Act-93 and NSRC Rules-97 and its implementation by the competent authority. The radiation control infrastructures and procedure are described as well as their functioning for the implementation of relevant activities such as licensing, regular inspection, personal dose monitoring, emergency preparedness, etc. The issue of security of radiation source is dealt in close relation with the preparation and use of the inventory of all radiation sources in the country

Source and special nuclear material sealing and labeling requirements

International Nuclear Information System (INIS)

Jordan, K.N.

1978-04-01

Purpose of this document is to define requirements for the use of tamper-indicating seals and identifying labels on SS Material containers at Rockwell Hanford Operations. The requirements defined in this document are applicable to all Rockwell Hanford Operation employees involved in handling, processing, packaging, transferring, shipping, receiving or storing SS Material

THE ROLE OF RADIATION ACCIDENTS AND INDUSTRIAL APPLICATIONS OF IONIZING RADIATION SOURCES IN THE PROBLEM OF RADIATION DAMAGE

OpenAIRE

Кіхтенко, Ігор Миколайович

2016-01-01

Subject of research – the relevance of radiation damage at modern development of industry and medicine. In the world of radiation sources used in different fields of practice and their application in the future will increase, which greatly increases the likelihood of injury in a significant contingent of people.Research topic – the definition of the role of nuclear energy and the industrial use of ionizing radiation sources in the problem of radiation damage. The purpose of research – identif...

Devices for obtaining information about radiation sources

International Nuclear Information System (INIS)

Tosswill, C.H.

1981-01-01

The invention provides a sensitive, fast, high-resolution device for obtaining information about the distribution of gamma and X-radiation sources and provides a radiation detector useful in such a device. It comprises a slit collimator with a multiplicity of slits each with slit-defining walls of material and thickness to absorb beam components impinging on them. The slits extend further in one transverse direction than the other. The detector for separately detecting beam components passing through the slits also provides data output signals. It comprises a plurality of radiation transducing portions, each at the end of a slit. A positioner changes the transverse position of the slits and radiation transducer (a photoconductor) relative to the source. Applications are in nuclear medicine and industry. Full details and preferred embodiments are given. (U.K.)

The feasibility of 10 keV X-ray as radiation source in total dose response radiation test

International Nuclear Information System (INIS)

Li Ruoyu; Li Bin; Luo Hongwei; Shi Qian

2005-01-01

The standard radiation source utilized in traditional total dose response radiation test is 60 Co, which is environment-threatening. X-rays, as a new radiation source, has the advantages such as safety, precise control of dose rate, strong intensity, possibility of wafer-level test or even on-line test, which greatly reduce cost for package, test and transportation. This paper discussed the feasibility of X-rays replacing 60 Co as the radiation source, based on the radiation mechanism and the effects of radiation on gate oxide. (authors)

There are radiation sources out there!

International Nuclear Information System (INIS)

Bahran, M.Y.

2001-01-01

During the past few years we have been working in the area of the safety of radiation sources and radioactive materials. In this paper we summarize our findings and describe the recovery of an abandoned source. We call for further international co-operation in this area. In particular, we suggest an international system for the tagging and tracking of radioactive sources. (author)

Dosimetric analysis of radiation sources for use dermatological lesions

International Nuclear Information System (INIS)

Tada, Ariane

2010-01-01

Skin lesions undergoing therapy with radiation sources may have different patterns of malignancy. Malignant lesions or cancer most commonly found in radiotherapy services are carcinomas. Radiation therapy in skin lesions is performed with low penetration beams and orthovoltage X-rays, electron beams and radioactive sources ( 192 Ir, 198 Au, e 90 Sr) arranged on a surface mold or in metal applicator. This study aims to analyze the therapeutic radiation dose profile produced by radiation sources used in skin lesions radiotherapy procedures . Experimental measurements for the analysis of dosimetric radiation sources were compared with calculations obtained from a computer system based on the Monte Carlo Method. Computational results had a good agreement with the experimental measurements. Experimental measurements and computational results by the MCNP4C code were both physically consistent as expected. These experimental measurements compared with calculations using the MCNP-4C code have been used to validate the calculations obtained by MCNP code and to provide a reliable medical application for each clinical case. (author)

Categorization of radiation sources

International Nuclear Information System (INIS)

2000-12-01

The objective of this report is to develop a categorization scheme for radiation sources that could be relevant to decisions both in a retrospective application to bring sources under control and in a prospective sense to guide the application of the regulatory infrastructure. The Action Plan envisages that the preparation of guidance on national strategies and programmes for the detection and location of orphan sources and their subsequent management should commence after the categorization of sources has been carried out. In the prospective application of the system of notification, registration, and licensing, the categorization is relevant to prioritize a regulatory authority's resources and training activities; to guide the degree of detail necessary for a safety assessment; and to serve as a measure of the intensity of effort which a regulatory authority should apply to the safety and security of a particular type of source

Failure analysis and seal life prediction for contacting mechanical seals

Science.gov (United States)

Sun, J. J.; He, X. Y.; Wei, L.; Feng, X.

2008-11-01

Fault tree analysis method was applied to quantitatively investigate the causes of the leakage failure of mechanical seals. It is pointed out that the change of the surface topography is the main reasons causing the leakage of mechanical seals under the condition of constant preloads. Based on the fractal geometry theory, the relationship between the surface topography and working time were investigated by experiments, and the effects of unit load acting on seal face on leakage path in a mechanical seal were analyzed. The model of predicting seal life of mechanical seals was established on the basis of the relationship between the surface topography and working time and allowable leakage. The seal life of 108 mechanical seal operating at the system of diesel fuel storage and transportation was predicted and the problem of the condition monitoring for the long-period operation of mechanical seal was discussed by this method. The research results indicate that the method of predicting seal life of mechanical seals is feasible, and also is foundation to make scheduled maintenance time and to achieve safe-reliability and low-cost operation for industrial devices.

Ionizing radiation sources management in the Commonwealth of Independent States - CIS

International Nuclear Information System (INIS)

Iskra, A.; Bufetova, M.

2006-01-01

Ionizing radiation sources cover a broad band of power: from powerful NPP reactors and research reactors to portable radioisotope ionizing radiation sources applied in medicine, agriculture, industry and in the energy supply systems of remote facilities. At present, scales and use field of radionuclide sources in the CIS have the tendency to increase. In this connection, the issues of ionizing radiation sources management safety at all stages of their life cycle, from production to treatment, have been of a great importance. The materials on ionizing radiation sources inventory and treatment in the CIS (Russia, Armenia, Belarus, Georgia, Kazakhstan, Kyrgyzstan, Tajikistan and Ukraine) are presented in the report. It is shown that in some republics, there is difficulty in ionizing radiation sources accounting and control system; the national regulatory and legal framework bases regulating activity on radioactive sources use, localization and treatment require update. Many problems are connected with the sources beyond state accounting. The problem of ionizing radiation sources use safety is complicated by the growing activity of various terrorist groups. The opportunity to use ionizing radiation sources with terrorism goals requires the application of defined systems of security and physical protection at all stages of their management. For this purpose a collective, with all CIS countries, organization of radioactive sources accounting and control as well as countermeasures on their illegal transportation and use are necessary. In this connection, the information collection regarding situation with providing of ionizing radiation sources safety, conditions of equipment and storage facilities, radioactive materials accounting and control system in the CIS countries is vitally needed

Ceramic Seal.

Energy Technology Data Exchange (ETDEWEB)

Smartt, Heidi A. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Romero, Juan A. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Custer, Joyce Olsen [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Hymel, Ross W. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Krementz, Dan [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Gobin, Derek [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Harpring, Larry [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Martinez-Rodriguez, Michael [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Varble, Don [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); DiMaio, Jeff [Tetramer Technologies, Pendleton, SC (United States); Hudson, Stephen [Tetramer Technologies, Pendleton, SC (United States)

2016-11-01

Containment/Surveillance (C/S) measures are critical to any verification regime in order to maintain Continuity of Knowledge (CoK). The Ceramic Seal project is research into the next generation technologies to advance C/S, in particular improving security and efficiency. The Ceramic Seal is a small form factor loop seal with improved tamper-indication including a frangible seal body, tamper planes, external coatings, and electronic monitoring of the seal body integrity. It improves efficiency through a self-securing wire and in-situ verification with a handheld reader. Sandia National Laboratories (SNL) and Savannah River National Laboratory (SRNL), under sponsorship from the U.S. National Nuclear Security Administration (NNSA) Office of Defense Nuclear Nonproliferation Research and Development (DNN R&D), have previously designed and have now fabricated and tested Ceramic Seals. Tests have occurred at both SNL and SRNL, with different types of tests occurring at each facility. This interim report will describe the Ceramic Seal prototype, the design and development of a handheld standalone reader and an interface to a data acquisition system, fabrication of the seals, and results of initial testing.

Ceramic Seal

International Nuclear Information System (INIS)

Smartt, Heidi A.; Romero, Juan A.; Custer, Joyce Olsen; Hymel, Ross W.; Krementz, Dan; Gobin, Derek; Harpring, Larry; Martinez-Rodriguez, Michael; Varble, Don; DiMaio, Jeff; Hudson, Stephen

2016-01-01

Containment/Surveillance (C/S) measures are critical to any verification regime in order to maintain Continuity of Knowledge (CoK). The Ceramic Seal project is research into the next generation technologies to advance C/S, in particular improving security and efficiency. The Ceramic Seal is a small form factor loop seal with improved tamper-indication including a frangible seal body, tamper planes, external coatings, and electronic monitoring of the seal body integrity. It improves efficiency through a self-securing wire and in-situ verification with a handheld reader. Sandia National Laboratories (SNL) and Savannah River National Laboratory (SRNL), under sponsorship from the U.S. National Nuclear Security Administration (NNSA) Office of Defense Nuclear Nonproliferation Research and Development (DNN R&D), have previously designed and have now fabricated and tested Ceramic Seals. Tests have occurred at both SNL and SRNL, with different types of tests occurring at each facility. This interim report will describe the Ceramic Seal prototype, the design and development of a handheld standalone reader and an interface to a data acquisition system, fabrication of the seals, and results of initial testing.

Assessment of the Proposed Design of a New Spent Sealed Radioactive Sources Storage Facility at Novi Han

International Nuclear Information System (INIS)

Alardin, J.M.; Lacroix, J.P.; Glibert, R.; Marneffe, L. de

2001-09-01

The NOVI HAN radioactive waste repository (NHRWR) in Bulgaria, built according to a Soviet design, was commissioned in 1964. The State Committee on the Use of Atomic Energy for Peaceful Purposes (CUAEPP) temporarily stopped operations at the repository from October 1994 until measures for improvement of the facility are undertaken. Since 1994, the Spent Sealed Radioactive Sources (SSRS) have been temporarily stored at the facilities at IRT-2000 research reactor of the Bulgarian Academy of Sciences (BAS) in Sofia. In view of the importance of the radiological risks associated with the present management of the SSRS in Bulgaria, the present study contract has been launched to critically review the proposal to provide a new interim storage facility for SSRS at NHRWR. A comprehensive critical review was performed of the feasibility study for the construction of a new SSRS facility at Novi Han, carried out by the local consultant engineering company (EQE), and detailed recommendations were made concerning the proposed new development at the site. The authors think that new concepts and procedures in the management of all categories of SSRS including smoke detectors have to be introduced, taking into account the regulatory framework and the inventories of existing and anticipated SSRS. This should be the basis for the technical specification of the new facilities for conditioning and storage of spent sealed radioactive sources (not only SHARS). (author)

Mechanical seal assembly

Science.gov (United States)

Kotlyar, Oleg M.

2001-01-01

An improved mechanical seal assembly is provided for sealing rotating shafts with respect to their shaft housings, wherein the rotating shafts are subject to substantial axial vibrations. The mechanical seal assembly generally includes a rotating sealing ring fixed to the shaft, a non-rotating sealing ring adjacent to and in close contact with the rotating sealing ring for forming an annular seal about the shaft, and a mechanical diode element that applies a biasing force to the non-rotating sealing ring by means of hemispherical joint. The alignment of the mechanical diode with respect to the sealing rings is maintained by a series of linear bearings positioned axially along a desired length of the mechanical diode. Alternative embodiments include mechanical or hydraulic amplification components for amplifying axial displacement of the non-rotating sealing ring and transferring it to the mechanical diode.

Mechanical Seal Assembly

Energy Technology Data Exchange (ETDEWEB)

Kotlyar, Oleg M.

1999-06-18

An improved mechanical seal assembly is provided for sealing rotating shafts with respect to their shaft housings, wherein the rotating shafts are subject to substantial axial vibrations. The mechanical seal assembly generally includes a rotating sealing ring fixed to the shaft, a non-rotating sealing ring adjacent to and in close contact with the rotating sealing ring for forming an annular seal about the shaft, and a mechanical diode element that applies a biasing force to the non-rotating sealing ring by means of hemispherical joint. The alignment of the mechanical diode with respect to the sealing rings is maintained by a series of linear bearings positioned axially along a desired length of the mechanical diode. Alternative embodiments include mechanical or hydraulic amplification components for amplifying axial displacement of the non-rotating sealing ring and transferring it to the mechanical diode.

Radiation protection type testing and licensing of diagnostic X-ray equipment in the GDR

International Nuclear Information System (INIS)

Taschner, P.; Poulheim, K.F.; Feldheim, W.

1987-01-01

The results of more than 10 years experience in type testing and type licensing of diagnostic X-ray equipment with respect to meeting radiation protection requirements as well as the implications for the conduct of these procedures resulting from the introduction of new radiation protection legislation in 1983 and 1984, are described. At present an updated version of the 'Regulation of 16 December 1977 concerning radiation protection type testing and licensing of sealed radiation sources and equipment emitting ionizing radiation' is being prepared. (author)

On the choice of working conditions for isotope radiation sources in irradiation plants

International Nuclear Information System (INIS)

Syrkus, N.P.; Breger, A.Kh.; Putilov, A.V.

1975-01-01

The problems of selecting an optimal regime for isotopic sources of radiation in powerful radiational installations depending on the costs, parameters of the radiational process (epsilon) and the radioactive isotope halflife are considered. When the radiation sources are simultaneusly replaced, then the optimal time of replacement of sources increases in the radiational installation with the radiation process parameter epsilon<0. Although the cost of a radiational product is lower during continuous replacement of radiation sources, the cost of products in the regime of simultaneous replacement of sources can be decreased, particularly, in the case of a secondary use of the radiactive sources

Glass sealing

Energy Technology Data Exchange (ETDEWEB)

Brow, R.K.; Kovacic, L.; Chambers, R.S. [Sandia National Labs., Albuquerque, NM (United States)

1996-04-01

Hernetic glass sealing technologies developed for weapons component applications can be utilized for the design and manufacture of fuel cells. Design and processing of of a seal are optimized through an integrated approach based on glass composition research, finite element analysis, and sealing process definition. Glass sealing procedures are selected to accommodate the limits imposed by glass composition and predicted calculations.

Technological progress in sealed lead/acid batteries

Science.gov (United States)

Yamashita, J.; Nakashima, H.; Kasai, Y.

A brief review is given of the history of the research and development of sealed lead/acid batteries during the 30 years since, in 1959, the Yuasa Battery Co. introduced a small-sized sealed battery as the power supply for portable television sets. In 1965, Yuasa began the full-scale mass production and sale of a small-sized sealed lead/acid battery under the NOYPER brand. In 1970, the use of a PbCa alloy grid was adopted, and there followed the successful development of a sealed battery with an oxygen-recombination facility. In 1976, Yuasa more or less established the basic technology for the valve-regulated sealed lead/acid battery — the NP battery — which is now the type in general use. Throughout the 1980s, Yuasa, has continued development in order to expand the sphere of application for the production technology of valve-regulated batteries for motorcycles, as well as for stationary duties with large capacities of 100 to 3000 A h. Recently, in order to improve the reliability and boost the output of sealed lead/acid batteries for employment in UPS power sources, Yuasa has been working intently on the design of a valve-regulated lead/acid battery with outstanding characteristics for high-rate discharge and resistance to high temperatures.

Obtention of brachytherapy seeds by sealing process using polymer; Obtencao de sementes de braquiterapia pelo processo de selagem com polimero

Energy Technology Data Exchange (ETDEWEB)

Lana, Diogo Alberto P.D.; Ferraz, Wilmar B.; Santos, Ana Maria M., E-mail: amms@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil); Carvalho, Luiz Claudio F.M. Garcia [Universidade Federal de Minas Gerais (UFMG), Belo Horizonte, MG (Brazil)

2012-08-15

Brachytherapy is an advanced cancer treatment where radioactive seeds or sources are placed near or directly into the tumor thus reducing the radiation exposure in the surrounding healthy tissues. Several kinds of seeds have been developed in order to obtain a better dose distribution around them and with a lower cost manufacturing. These seeds consist of an encapsulation (titanium or stainless steel tube), a radionuclide carrier, and X-ray marker. The usual sealing process of the seeds is done with laser welding, but this process can promote radionuclide volatilization. In this paper, we present a new sealing process using epoxy resin and characterizations of two epoxy resins. These resins were characterized by Fourier transform infrared spectroscopic (FTIR), ultraviolet-visible spectroscopy (UV-vis) and differential scanning calorimetry (DSC). Interactions of the resins and of the sealed seeds in a simulated body fluid (SBF) were evaluated by scanning electron microscopy (SEM), energy dispersive X-ray spectroscopy (EDS), and by a counting gamma-rays. (author)

Design of repository sealing systems - 1981

International Nuclear Information System (INIS)

Ellison, R.D.; Shukla, D.K.; Kelsall, P.C.; D'Appolonia Consulting Engineers, Albuquerque, NM)

1982-01-01

Isolating nuclear waste in geologic repositories will require the sealing of penetrations such as access shafts and tunnels, disposal rooms, and exploration boreholes. This paper discusses seal designs developed for a repository in bedded salt referenced to the stratigraphy of southeastern New Mexico. Designs are based on a multiple component concept whereby individual components are designed for a specific function and location. For a repository in salt the major function of the seals is to exclude groundwater inflow. Two main types of component are included for this purpose: (1) bulk-heads are dense concrete structures keyed into the walls of the penetration and are intended to reduce flow at the interface between the seal and the salt; (2) backfills are granular materials compacted in place in the penetration. In the repository the major backfill material is crushed salt, which is expected to consolidate and recrystallize as the rooms close in response to salt creep. Densely compacted clays will be used as backfill in the shafts closer to potential sources of water inflow. 22 references, 10 figures, 1 table

Impurity radiation from a beam-plasma neutron source

International Nuclear Information System (INIS)

Molvik, A.W.

1995-01-01

Impurity radiation, in a worst case evaluation for a beam-plasma neutron source (BPNS), does not limit performance. Impurities originate from four sources: (a) sputtering from walls by charge exchange or alpha particle bombardment, (b) sputtering from limiters, (c) plasma desorption of gas from walls and (d) injection with neutral beams. Sources (c) and (d) are negligible; adsorbed gas on the walls of the confinement chamber and the neutral beam sources is removed by the steady state discharge. Source (b) is negligible for impinging ion energies below the sputtering threshold (T i ≤ 0.025 keV on tungsten) and for power densities to the limiter within the capabilities of water cooling (30-40 MW/m 2 ); both conditions can be satisfied in the BPNS. Source (a) radiates 0.025 MW/m 2 to the neutron irradiation samples, compared with 5 to 10 MW/m 2 of neutrons; and radiates a total of 0.08 MW from the plasma column, compared with 60 MW of injected power. The particle bombardment that yields source (a) deposits an average of 2.7 MW/m 2 on the samples, within the capabilities of helium gas cooling (10 MW/m 2 ). An additional worst case for source (d) is evaluated for present day 2 to 5 s pulsed neutral beams with 0.1% impurity density and is benchmarked against 2XIIB. The total radiation would increase a factor of 1.5 to ≤ 0.12 MW, supporting the conclusion that impurities will not have a significant impact on a BPN. (author). 61 refs, 7 figs, 2 tabs