Nuclear radiation and its role in general nuclear medicine

International Nuclear Information System (INIS)

Kempaiah, A.; Ravi, C.

2012-01-01

Radiation is really nothing more than the emission of energy through space, as well as through physical objects. Nuclear radiations are emitted due to decay of nuclei of radioactive materials and damage cells and the DNA inside them through its ionizing effect. That causes melanoma and other cancers. Nuclear radiation has a number of beneficial uses especially in medical field with low levels of radioactive compounds, better than X-rays. There are some 440 nuclear reactors worldwide, people around will be under the effect of radiation. In nuclear medicine (medical imaging) small amount of radioactive materials were used to diagnose and determine the severity of or treat a variety of disease, including many types of cancers, heart disease, gastrointestinal, endocrine, neurological disorders and other abnormalities within the body it is painless and cost-effective techniques and provides information about both structure and function. Nuclear medicine diagnostic procedures called Gamma camera, single photon emission computed tomography (SPECT) and positron emission tomography (PET) were discussed in this paper. (author)

Nuclear radiation and the properties of concrete

International Nuclear Information System (INIS)

Kaplan, M.F.

1983-08-01

Concrete is used for structures in which the concrete is exposed to nuclear radiation. Exposure to nuclear radiation may affect the properties of concrete. The report mentions the types of nuclear radiation while radiation damage in concrete is discussed. Attention is also given to the effects of neutron and gamma radiation on compressive and tensile strength of concrete. Finally radiation shielding, the attenuation of nuclear radiation and the value of concrete as a shielding material is discussed

Nuclear materials control technology in the post-cold war world: Radiation-based methods and information management systems

International Nuclear Information System (INIS)

Tape, J.W.; Eccleston, G.W.; Ensslin, N.; Markin, J.T.

1993-01-01

The end of the cold war is providing both opportunities and requirements for improving the control of nuclear materials around the world. The dismantlement of nuclear weapons and the growth of nuclear power, including the use of plutonium in light water reactors and breeder reactor programs, coupled with enhanced proliferation concerns, drive the need for improved nuclear materials control. We describe nuclear materials control and the role of technology in making controls more effective and efficient. The current use and anticipated development in selected radiation-based methods and related information management systems am described briefly

Special nuclear material radiation monitors for the 1980's

International Nuclear Information System (INIS)

Fehlau, P.E.

1985-01-01

During the two decades that automatic gamma-radiation monitors have been applied to detecting special nuclear material (SNM), little attention has been devoted to how well the monitors perform in plant environments. Visits to 11 DOE facilities revealed poor information flow between developers, manufacturers, and maintainers of SNM radiation monitors. To help users achieve best performance from their monitors or select new ones, Los Alamos National Laboratory developed a hand-held monitor user's guide, calibration manuals for some commercial SNM pedestrian monitors, and an application guide for SNM pedestrian monitors. In addition, Los Alamos evaluated new commercial SNM monitors, considered whether to apply neutron detection to SNM monitoring, and investigated the problem of operating gamma-ray SNM monitors in variable plutonium gamma-radiation fields. As a result, the performance of existing SNM monitors will improve and alternative monitoring methods will become commerciallly available during the 1980s. 9 refs., 6 figs., 1 tab

Radiation Effects in Nuclear Ceramics

Directory of Open Access Journals (Sweden)

L. Thomé

2012-01-01

Full Text Available Due to outstanding physicochemical properties, ceramics are key engineering materials in many industrial domains. The evaluation of the damage created in ceramics employed in radiative media is a challenging problem for electronic, space, and nuclear industries. In this latter field, ceramics can be used as immobilization forms for radioactive wastes, inert fuel matrices for actinide transmutation, cladding materials for gas-cooled fission reactors, and structural components for fusion reactors. Information on the radiation stability of nuclear materials may be obtained by simulating the different types of interactions involved during the slowing down of energetic particles with ion beams delivered by various types of accelerators. This paper presents a review of the radiation effects occurring in nuclear ceramics, with an emphasis on recent results concerning the damage accumulation processes. Energetic ions in the KeV-GeV range are used to explore the nuclear collision (at low energy and electronic excitation (at high energy regimes. The recovery by electronic excitation of the damage created by ballistic collisions (SHIBIEC process is also addressed.

Radiation effects on materials in the near-field of nuclear waste repository. 1998 annual progress report

International Nuclear Information System (INIS)

Ewing, R.C.; Wang, L.M.

1998-01-01

'Site restoration activities at DOE facilities and the permanent disposal of nuclear waste generated at DOE facilities involve working with and within various types and levels of radiation fields. Once the nuclear waste is incorporated into a final form, radioactive decay will decrease the radiation field over geologic time scales, but the alpha-decay dose for these solids will still reach values as high as 10 18 alpha-decay events/gm in periods as short as 1,000 years. This dose is well within the range for which important chemical (e.g., increased leach rate) and physical (e.g., volume expansion) changes may occur in crystalline ceramics. Release and sorption of long-lived actinides (e.g., 237 Np) can provide a radiation exposure to backfill materials, and changes in important properties (e.g., cation exchange capacity) may occur. The objective of this research program is to evaluate the long term radiation effects in the materials in the near-field of a nuclear waste repository with accelerated experiments in the laboratory using energetic particles (electrons, ions and neutrons). Experiments on the microstructural evolution during irradiation of two important groups of materials, sheet silicates (e.g., clays) and zeolites (analcime), have been conducted; and studies of radiation-induced changes in chemical properties (e.g. cation exchange capacity) are underway. As of the mid-2nd year of the 3-year project, experiments on the microstructural evolution during irradiation of two important group of materials, sheet silicates (mica) and zeolites (analcime), have been conducted; and studies of radiation-induced changes in chemical properties (e.g., cation exchange capacity) are underway.'

Physics and technology of nuclear materials

International Nuclear Information System (INIS)

Ursu, I.

1985-01-01

The subject is covered in chapters, entitled; elements of nuclear reactor physics; structure and properties of materials (including radiation effects); fuel materials (uranium, plutonium, thorium); structural materials (including - aluminium, zirconium, stainless steels, ferritic steels, magnesium alloys, neutron irradiation induced changes in the mechanical properties of structural materials); moderator materials (including - nuclear graphite, natural (light) water, heavy water, beryllium, metal hydrides); materials for reactor reactivity control; coolant materials; shielding materials; nuclear fuel elements; nuclear material recovery from irradiated fuel and recycling; quality control of nuclear materials; materials for fusion reactors (thermonuclear fusion reaction, physical processes in fusion reactors, fuel materials, materials for blanket and cooling system, structural materials, materials for magnetic devices, specific problems of material irradiation). (U.K.)

Nuclear radiation gauge standard

International Nuclear Information System (INIS)

Berry, R.L.

1977-01-01

A hydrophobic standard for calibrating nuclear radiation moisture gauges is described, comprising a body of superposed interleaved thin layers of a moderating material containing hydrogen in the molecular structure thereof and of a substantially non-moderating material

Strengthening global norms for protecting nuclear materials - feedback on little countries radiation safety

International Nuclear Information System (INIS)

Chelidze, L.; Kakushadze, S.

2002-01-01

Full text: Georgia is the part of New Great Silk Road, connecting Europe and Asia. Along this rout will be laid oil and gas pipelines, transport and telecommunication lines. Unfortunately, besides economical communication, the rout can be used for illegal transit of nuclear materials. There is special concern regarding uncontrolled territories of conflict zones. Taking into consideration recent terrible terrorist acts we feel great responsibility for ensuring safety of this rout, which is a precondition of economical development and political stability of the whole Caucasian region A potentially hazardous radiological situation developed in Georgia with orphan radiation sources in the late 1990s and 2001: discovery of high-activity strong Radiation sources of (Strontium-90 from thermo-generators) in Tsalenjikha district. Eight such generators were brought to Georgia in 1984, and four of them have been found in Svanety mountainous region in addition to the two found in the Tsalenjikha, but remaining two are not yet found. During the last years several incidents of illicit trafficking were reported. The radiation problems greatly relate to the withdrawal of the Russian military bases. The radiological accident took place in Lilo, Georgia, when sealed radiation sources had been abandoned by a previous owner at a site. Taking into account the geopolitical location of Georgia it is quite important to strengthen the physical protection infrastructure in country with has serious territorial problems. The first step was to provide an appropriate legal framework for the safety management in the country and clearly identify regulatory body. The ministry implements state control in the nuclear and radiation safety field for protection of environment and natural resources of Georgia (hereinafter referred to as the Ministry). The Ministry is obliged to supervise the physical protection systems. The Ministry shall co-ordinate the state system of physical protection of the use

Regulations concerning the fabricating business of nuclear fuel materials

International Nuclear Information System (INIS)

1978-01-01

The Regulation is revised on the basis of ''The law for the regulations of nuclear source materials, nuclear fuel materials and reactors'' and the ''Provisions concerning the enterprises processing nuclear fuel materials'' in the Enforcement Ordinance for the Law, to enforce such provisions. This is the complete revision of the regulation of the same name in 1957. Terms are explained, such as exposure radiation dose, cumulative dose, control area, surrounding inspection area, persons engaged in works, radioactive wastes, area for incoming and outgoing of materials, fluctuation of stocks, batch, real stocks, effective value and main measuring points. For the applications for the permission of the enterprises processing nuclear fuel materials, the location of an enterprise, the construction of buildings and the construction of and the equipments for facilities of chemical processing, forming, coating, assembling, storage of nuclear fuel materials, disposal of radioactive wastes and radiation control must be written. Records shall be made and maintained for the periods specified on the inspection of processing facilities, nuclear fuel materials, radiation control, operation, maintainance, accidents of processing facilities and weather. Limit to entrance into the control area, measures for exposure radiation dose, patrol and inspection, operation of processing facilities, transport of materials, disposal of radioactive wastes, safety regulations are provided for. Reports to be filed by the persons engaging in the enterprises processing nuclear fuel materials are prescribed. (Okada, K.)

Radiation damage of structural materials

International Nuclear Information System (INIS)

Koutsky, J.; Kocik, J.

1994-01-01

Maintaining the integrity of nuclear power plants (NPP) is critical in the prevention or control of severe accidents. This monograph deals with both basic groups of structural materials used in the design of light-water nuclear reactors, making the primary safety barriers of NPPs. Emphasis is placed on materials used in VVER-type nuclear reactors: Cr-Mo-V and Cr-Ni-Mo-V steel for reactor pressure vessels (RPV) and Zr-Nb alloys for fuel element cladding. The book is divided into seven main chapters, with the exception of the opening one and the chapter providing phenomenological background for the subject of radiation damage. Chapters 3-6 are devoted to RPV steels and chapters 7-9 to zirconium alloys, analyzing their radiation damage structure, changes of mechanical properties due to neutron irradiation as well as factors influencing the degree of their performance degradation. The recovery of damaged materials is also discussed. Considerable attention is paid to a comparison of VVER-type and western-type light-water materials

The regulations concerning refining business of nuclear source material and nuclear fuel materials

International Nuclear Information System (INIS)

1979-01-01

The regulations are provided for under the law for the regulations of nuclear source materials, nuclear fuel materials and reactors and provisions concerning refining business in the enforcement order for the law. The basic concepts and terms are defined, such as: exposure dose, accumulative dose; controlled area; inspected surrounding area and employee. Refining facilities listed in the application for designation shall be classified into clushing and leaching, thickning, refining facilities, storage facilities of nuclear source materials and nuclear fuel materials, disposal facilities of contaminated substances and building for refining, etc. Business program attached to the application shall include expected time of beginning of refining, estimated production amount of nuclear source materials or nuclear fuel materials for the first three years and funds necessary for construction, etc. Records shall be made and kept for particular periods on delivery and storage of nuclear source materials and nuclear fuel materials, control of radiation, maintenance and accidents of refining facilities. Safety securing, application of internationally regulated substances and measures in dangerous situations are stipulated respectively. Exposure dose of employees and other specified matters shall be reported by the refiner yearly to the Director General of Science and Technology Agency and the Minister of International Trade and Industry. (Okada, K.)

Multiscale modeling of radiation effects in nuclear reactor structural materials

Energy Technology Data Exchange (ETDEWEB)

Kwon, Junhyun [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2015-10-15

Most problems in irradiated materials originate from the atomic collision of high-energy particles and lattice atoms. This collision leads to displacement cascades through the energy transfer reaction and causes various types of defects such as vacancies, interstitials, and clusters. The behavior of the point defects created in the displacement cascades is important because these defects play a major role in a microstructural evolution and further affect the changes in material properties. Rapid advances have been made in the computational capabilities for a realistic simulation of complex physical phenomena, such as irradiation and aging effects. At the same time, progress has been made in understanding the effect of radiation in metals, especially iron-based alloys. In this work, we present some of our ongoing work in this area, which illustrates a multiscale modeling for evaluating a microstructural evolution and mechanical property changes during irradiation. Multiscale modeling approaches are briefly presented here in the following order: nuclear interaction, atomic-level interaction, atomistic modeling, microstructural evolution modeling and mechanical property modeling. This is one of many possible methods for classifying techniques. The effort in developing physical multiscale models applied to radiation damage has been focused on a single crystal or single-grain materials.

Nuclear and hazardous material perspective

International Nuclear Information System (INIS)

Sandquist, Gary M.; Kunze, Jay F.; Rogers, Vern C.

2007-01-01

The reemerging nuclear enterprise in the 21. century empowering the power industry and nuclear technology is still viewed with fear and concern by many of the public and many political leaders. Nuclear phobia is also exhibited by many nuclear professionals. The fears and concerns of these groups are complex and varied, but focus primarily on (1) management and disposal of radioactive waste [especially spent nuclear fuel and low level radioactive waste], (2) radiation exposures at any level, and (3) the threat nuclear terrorism. The root cause of all these concerns is the exaggerated risk perceived to human health from radiation exposure. These risks from radiation exposure are compounded by the universal threat of nuclear weapons and the disastrous consequences if these weapons or materials become available to terrorists or rogue nations. This paper addresses the bases and rationality for these fears and considers methods and options for mitigating these fears. Scientific evidence and actual data are provided. Radiation risks are compared to similar risks from common chemicals and familiar human activities that are routinely accepted. (authors)

Protection and control of nuclear materials

International Nuclear Information System (INIS)

Jalouneix, J.; Winter, D.

2007-01-01

In the framework of the French regulation on nuclear materials possession, the first liability is the one of operators who have to know at any time the quantity, quality and localization of any nuclear material in their possession. This requires an organization of the follow up and of the inventory of these materials together with an efficient protection against theft or sabotage. The French organization foresees a control of the implementation of this regulation at nuclear facilities and during the transport of nuclear materials by the minister of industry with the sustain of the institute of radiation protection and nuclear safety (IRSN). This article presents this organization: 1 - protection against malevolence; 2 - national protection and control of nuclear materials: goals, administrative organization, legal and regulatory content (authorization, control, sanctions), nuclear materials protection inside facilities (physical protection, follow up and inventory, security studies), protection of nuclear material transports (physical protection, follow up), control of nuclear materials (inspection at facilities, control of nuclear material measurements, inspection of nuclear materials during transport); 3 - international commitments of France: non-proliferation treaty, EURATOM regulation, international convention on the physical protection of nuclear materials, enforcement in France. (J.S.)

Nuclear safety and radiation protection in France in 2011

International Nuclear Information System (INIS)

2012-01-01

The first part of this voluminous report describe the different ASN (Nuclear Safety Authority) actions: nuclear activities (ionising radiation and health and environmental risks), principles and stakeholders in nuclear safety regulation, radiation protection and protection of the environment, regulation, regulation of nuclear activities and exposure to ionizing radiation, radiological emergencies, public information and transparency, international relations. It also gives an overview of nuclear safety and radiation protection activities in the different French regions. The second part addresses activities regulated by the ASN: medical uses of ionizing radiation, non-medical uses of ionizing radiation, transport of radioactive materials, nuclear power plants, nuclear fuel cycle installations, nuclear research facilities and various nuclear installations, safe decommissioning of basic nuclear installations, radioactive waste and contaminated sites and soils

The regulations concerning the uses of nuclear source materials

International Nuclear Information System (INIS)

1981-01-01

This rule is established under the provisions of the law concerning the regulation of nuclear raw materials, nuclear fuel materials and nuclear reactors and the ordinance for the execution of this law, and to enforce them. Basic terms are defined, such as exposure radiation dose, cumulative dose, control area, surrounding monitoring area, worker and radioactive waste. Nuclear raw materials shall be used at the facilities for using them, and control areas and surrounding monitoring areas shall be set up. Cumulative dose and exposure radiation dose of workers shall not exceed the permissible quantities defined by the General Director of the Science and Technology Agency. Records shall be made in each works or enterprise on the accept, delivery and stock of each kind of nuclear raw materials, radiation control and the accidents in the facilities of using nuclear raw materials, and kept for specified periods, respectively. The users of nuclear raw materials shall present reports in each works or enterprise on the stock of these materials on July 30 and December 31, every year. They shall submit reports immediately to the Director General on the particular accidents concerning nuclear raw materials and their facilities and on the circumstances and the measures taken against such accidents within ten days. These reports shall be presented on internationally regulated raw materials too. (Okada, K.)

Passive nondestructive assay of nuclear materials

International Nuclear Information System (INIS)

Reilly, D.; Ensslin, N.; Smith, H. Jr.; Kreiner, S.

1991-03-01

The term nondestructive assay (NDA) is applied to a series of measurement techniques for nuclear fuel materials. The techniques measure radiation induced or emitted spontaneously from the nuclear material; the measurements are nondestructive in that they do not alter the physical or chemical state of the nuclear material. NDA techniques are characterized as passive or active depending on whether they measure radiation from the spontaneous decay of the nuclear material or radiation induced by an external source. This book emphasizes passive NDA techniques, although certain active techniques like gamma-ray absorption densitometry and x-ray fluorescence are discussed here because of their intimate relation to passive assay techniques. The principal NDA techniques are classified as gamma-ray assay, neutron assay, and calorimetry. Gamma-ray assay techniques are treated in Chapters 1--10. Neutron assay techniques are the subject of Chapters 11--17. Chapters 11--13 cover the origin of neutrons, neutron interactions, and neutron detectors. Chapters 14--17 cover the theory and applications of total and coincidence neutron counting. Chapter 18 deals with the assay of irradiated nuclear fuel, which uses both gamma-ray and neutron assay techniques. Chapter 19 covers perimeter monitoring, which uses gamma-ray and neutron detectors of high sensitivity to check that no unauthorized nuclear material crosses a facility boundary. The subject of Chapter 20 is attribute and semiquantitative measurements. The goal of these measurements is a rapid verification of the contents of nuclear material containers to assist physical inventory verifications. Waste and holdup measurements are also treated in this chapter. Chapters 21 and 22 cover calorimetry theory and application, and Chapter 23 is a brief application guide to illustrate which techniques can be used to solve certain measurement problems

Radiation sensitive devices and systems for detection of radioactive materials and related methods

Science.gov (United States)

Kotter, Dale K

2014-12-02

Radiation sensitive devices include a substrate comprising a radiation sensitive material and a plurality of resonance elements coupled to the substrate. Each resonance element is configured to resonate responsive to non-ionizing incident radiation. Systems for detecting radiation from a special nuclear material include a radiation sensitive device and a sensor located remotely from the radiation sensitive device and configured to measure an output signal from the radiation sensitive device. In such systems, the radiation sensitive device includes a radiation sensitive material and a plurality of resonance elements positioned on the radiation sensitive material. Methods for detecting a presence of a special nuclear material include positioning a radiation sensitive device in a location where special nuclear materials are to be detected and remotely interrogating the radiation sensitive device with a sensor.

Materials for nuclear reactors

International Nuclear Information System (INIS)

Banerjee, S.; Kamath, H.S.

2005-01-01

The improved performance of present generation nuclear reactors and the realization of advanced reactor concepts, both, require development of better materials. Physical metallurgy/materials science principles which have been exploited in meeting the exacting requirements of nuclear reactor materials (fuels and structural materials), are outlined citing a few specific examples. While the incentive for improvement of traditional fuels (e.g., UO 2 fuel) is primarily for increasing the average core burn up, the development of advanced fuels (e.g., MOX, mixed carbide, nitride, silicide and dispersion fuels) are directed towards better utilization of fissile and fertile inventories through adaptation of innovative fuel cycles. As the burn up of UO 2 fuel reaches higher levels, a more detailed and quantitative understanding of the phenomena such as fission gas release, fuel restructuring induced by radiation and thermal gradients and pellet-clad interaction is being achieved. Development of zirconium based alloys for both cladding and pressure tube applications is discussed with reference to their physical metallurgy, fabrication techniques and in-reactor degradation mechanisms. The issue of radiation embrittlement of reactor pressure vessels (RPVs) is covered drawing a comparison between the western and eastern specifications of RPV steels. The search for new materials which can stand higher rates of atomic displacement due to radiation has led to the development of swelling resistant austenitic and ferritic stainless steels for fast reactor applications as exemplified by the development of the D-9 steel for Indian fast breeder reactor. The presentation will conclude by listing various materials related phenomena, which have a strong bearing on the successful development of future nuclear energy systems. (author)

Radiation effects on materials in high-radiation environments

International Nuclear Information System (INIS)

Weber, W.J.; Mansur, L.K.; Clinard, F.W. Jr.; Parkin, D.M.

1991-01-01

A workshop on Radiation Effects on Materials in High-Radiation Environments was held in Salt Lake City, Utah (USA) from August 13 to 15, 1990 under the auspices of the Division of Materials Sciences, Office of Basic Energy Sciences, US Department of Energy. The workshop focused on ceramics, alloys, and intermetallics and covered research needs and capabilities, recent experimental data, theory, and computer simulations. It was concluded that there is clearly a continuing scientific and technological need for fundamental knowledge on the underlying causes of radiation-induced property changes in materials. Furthermore, the success of many current and emerging nuclear-related technologies critically depend on renewed support for basic radiation-effects research, irradiation facilities, and training of scientists. The highlights of the workshop are reviewed and specific recommendations are made regarding research needs. (orig.)

Uncovering Special Nuclear Materials by Low-energy Nuclear Reaction Imaging.

Science.gov (United States)

Rose, P B; Erickson, A S; Mayer, M; Nattress, J; Jovanovic, I

2016-04-18

Weapons-grade uranium and plutonium could be used as nuclear explosives with extreme destructive potential. The problem of their detection, especially in standard cargo containers during transit, has been described as "searching for a needle in a haystack" because of the inherently low rate of spontaneous emission of characteristic penetrating radiation and the ease of its shielding. Currently, the only practical approach for uncovering well-shielded special nuclear materials is by use of active interrogation using an external radiation source. However, the similarity of these materials to shielding and the required radiation doses that may exceed regulatory limits prevent this method from being widely used in practice. We introduce a low-dose active detection technique, referred to as low-energy nuclear reaction imaging, which exploits the physics of interactions of multi-MeV monoenergetic photons and neutrons to simultaneously measure the material's areal density and effective atomic number, while confirming the presence of fissionable materials by observing the beta-delayed neutron emission. For the first time, we demonstrate identification and imaging of uranium with this novel technique using a simple yet robust source, setting the stage for its wide adoption in security applications.

Illicit diversion of nuclear materials

International Nuclear Information System (INIS)

Bett, F.L.

1975-08-01

This paper discusses the means of preventing illegal use of nuclear material by terrorists or other sub-national groups and by governments. With respect to sub-national groups, it concludes that the preventive measures of national safeguards systems, when taken together with the practical difficulties of using nuclear material, would make the diversion and illegal use of nuclear material unattractive in comparison with other avenues open to these groups to attain their ends. It notes that there are only certain areas in the nuclear fuel cycle, e.g. production of some types of nuclear fuel embodying highly enriched uranium and shipment of strategically significant nuclear material, which contain material potentially useful to these groups. It also discusses the difficult practical problems, e.g. coping with radiation, which would face the groups in making use of the materials for terrorist purposes. Concerning illegal use by Governments, the paper describes the role of international safeguards, as applied by the International Atomic Energy Agency, and the real deterrent effect of these safeguards which is achieved through the requirements to maintain comprehensive operating records of the use of nuclear material and by regular inspections to verify these records. The paper makes the point that Australia would not consider supplying nuclear material unless it were subject to international safeguards. (author)

Electromagnetic and nuclear radiation detector using micromechanical sensors

Science.gov (United States)

Thundat, Thomas G.; Warmack, Robert J.; Wachter, Eric A.

2000-01-01

Electromagnetic and nuclear radiation is detected by micromechanical sensors that can be coated with various interactive materials. As the micromechanical sensors absorb radiation, the sensors bend and/or undergo a shift in resonance characteristics. The bending and resonance changes are detected with high sensitivity by any of several detection methods including optical, capacitive, and piezoresistive methods. Wide bands of the electromagnetic spectrum can be imaged with picoJoule sensitivity, and specific absorptive coatings can be used for selective sensitivity in specific wavelength bands. Microcantilevers coated with optical cross-linking polymers are useful as integrating optical radiation dosimeters. Nuclear radiation dosimetry is possible by fabricating cantilevers from materials that are sensitive to various nuclear particles or radiation. Upon exposure to radiation, the cantilever bends due to stress and its resonance frequency shifts due to changes in elastic properties, based on cantilever shape and properties of the coating.

Detecting Illicit Nuclear Materials

International Nuclear Information System (INIS)

Kouzes, Richard T.

2005-01-01

The threat that weapons of mass destruction might enter the United States has led to a number of efforts for the detection and interdiction of nuclear, radiological, chemical, and biological weapons at our borders. There have been multiple deployments of instrumentation to detect radiation signatures to interdict radiological material, including weapons and weapons material worldwide

Attributes identification of nuclear material by non-destructive radiation measurement methods

International Nuclear Information System (INIS)

Gan Lin

2002-01-01

Full text: The nuclear materials should be controlled under the regulation of National Safeguard System. The non-destructive analysis method, which is simple and quick, provide a effective process in determining the nuclear materials, nuclear scraps and wastes. The method play a very important role in the fields of nuclear material control and physical protection against the illegal removal and smuggling of nuclear material. The application of non-destructive analysis in attributes identification of nuclear material is briefly described in this paper. The attributes determined by radioactive detection technique are useful tolls to identify the characterization of special nuclear material (isotopic composition, enrichment etc.). (author)

Materials science for nuclear detection

OpenAIRE

Peurrung, Anthony

2008-01-01

The increasing importance of nuclear detection technology has led to a variety of research efforts that seek to accelerate the discovery and development of useful new radiation detection materials. These efforts aim to improve our understanding of how these materials perform, develop formalized discovery tools, and enable rapid and effective performance characterization. We provide an overview of these efforts along with an introduction to the history, physics, and taxonomy of radiation detec...

Radiation damage of structural materials

CERN Document Server

Koutsky, Jaroslav

1994-01-01

Maintaining the integrity of nuclear power plants is critical in the prevention or control of severe accidents. This monograph deals with both basic groups of structural materials used in the design of light-water nuclear reactors, making the primary safety barriers of NPPs. Emphasis is placed on materials used in VVER-type nuclear reactors: Cr-Mo-V and Cr-Ni-Mo-V steel for RPV and Zr-Nb alloys for fuel element cladding. The book is divided into 7 main chapters, with the exception of the opening one and the chapter providing a phenomenological background for the subject of radiation damage. Ch

Radiation Damage in Reactor Materials. Part of the Proceedings of the Symposium on Radiation Damage in Solids and Reactor Materials

Energy Technology Data Exchange (ETDEWEB)

NONE

1963-08-15

Radiation damage has presented a new design parameter for the selection of materials to be used in fuel and cladding elements, moderators, structural components and pressure vessels in nuclear reactors. The severe and novel requirements for certain optimum combinations of physical and nuclear properties have emphasized the need for a better understanding of the basic mechanisms of radiation damage. This knowledge is not only essential for progress in the field of nuclear energy, but has direct applications to space technology and semi-conductor research as well. The IAEA, as part of its programme of promoting nuclear technology, therefore convened the Symposium on Radiation Damage in Solids and Reactor Materials, 7-11 May 1962. At the invitation of, and with generous material assistance from, the Government of Italy, the Symposium was held at Venice. The Symposium was primarily concerned with the investigation of the fundamental processes of radiation that underlie the behaviour of metals, alloys and ceramics that are actually useful or potentially useful reactor materials. Two sessions were devoted to studies of irradiation effects on simple metals, as these effects are easiest to interpret. Other topics included general theory, alloys, fissionable and moderator materials and special experimental techniques for radiation damage studies. The properties influenced by irradiation which were of main concern were those of primary importance to the behaviour of solids as reactor materials (e. g. dimensional stability, phase transformation, radiation hardening, fracture, fission-gas escape from uranium and its compounds). Other properties, such as optical, electrical and magnetic properties, and effects on semiconductors, ionic and other non-metallic crystals are also of interest in that these studies can increase our knowledge of the mechanism of radiation damage in solids and provide a tool for investigation into the physics of the solid state by offering a means of

Radiation Damage in Reactor Materials. Part of the Proceedings of the Symposium on Radiation Damage in Solids and Reactor Materials

International Nuclear Information System (INIS)

1963-01-01

Radiation damage has presented a new design parameter for the selection of materials to be used in fuel and cladding elements, moderators, structural components and pressure vessels in nuclear reactors. The severe and novel requirements for certain optimum combinations of physical and nuclear properties have emphasized the need for a better understanding of the basic mechanisms of radiation damage. This knowledge is not only essential for progress in the field of nuclear energy, but has direct applications to space technology and semi-conductor research as well. The IAEA, as part of its programme of promoting nuclear technology, therefore convened the Symposium on Radiation Damage in Solids and Reactor Materials, 7-11 May 1962. At the invitation of, and with generous material assistance from, the Government of Italy, the Symposium was held at Venice. The Symposium was primarily concerned with the investigation of the fundamental processes of radiation that underlie the behaviour of metals, alloys and ceramics that are actually useful or potentially useful reactor materials. Two sessions were devoted to studies of irradiation effects on simple metals, as these effects are easiest to interpret. Other topics included general theory, alloys, fissionable and moderator materials and special experimental techniques for radiation damage studies. The properties influenced by irradiation which were of main concern were those of primary importance to the behaviour of solids as reactor materials (e. g. dimensional stability, phase transformation, radiation hardening, fracture, fission-gas escape from uranium and its compounds). Other properties, such as optical, electrical and magnetic properties, and effects on semiconductors, ionic and other non-metallic crystals are also of interest in that these studies can increase our knowledge of the mechanism of radiation damage in solids and provide a tool for investigation into the physics of the solid state by offering a means of

Let's start learning radiation. Supplementary material on radiation for secondary school students

International Nuclear Information System (INIS)

Watanabe, Yoko; Yamashita, Kiyonobu; Shimada, Mayuka

2015-01-01

The Japan Atomic Energy Agency has been organizing training programs for engineers in Asian countries introducing nuclear technology. In 2012, we launched a course ‘Basic Radiation Knowledge for School Education’ as we thought disseminating accurate knowledge on radiation to school students and public would also be important in those countries after Fukushima-Daiichi nuclear power station accident. Ministry of Education, Culture, Sports, Science and Technology - Japan published supplemental learning material on radiation for secondary school students and teachers in Japanese in October 2011. Since the learning material is designed to give a clear explanation of radiation and covers various topics, we thought it would also be beneficial for young students in the world if a learning material in English was available. Therefore, we made a new learning material in English using the topics covered in supplemental learning material on radiation in Japanese as a reference. This learning material has been favourably evaluated by the International Atomic Energy Agency (IAEA) and will be widely used as a practical educational tool in many countries around the world through the IAEA. (author)

Report of the State Office for Nuclear Safety on state supervision of nuclear safety of nuclear facilities and radiation protection in 1998

International Nuclear Information System (INIS)

1999-05-01

The legislative basis of the authority of the State Office for Nuclear Safety as the Czech national regulatory body is outlined, its organizational scheme is presented, and the responsibilities of the various departments are highlighted. The operation of major Czech nuclear facilities, including the Dukovany NPP which is in operation and the Temelin NPP which is under construction, is described with respect to nuclear safety. Since the Office's responsibilities also cover radiation protection in the Czech Republic, a survey of ionizing radiation sources and their supervision is given. Other topics include, among other things, nuclear material transport, the state system for nuclear materials accountancy and control, central registries for radiation protection, nuclear waste management, the National Radiation Monitoring Network, personnel qualification and training, emergency planning, legislative activities, international cooperation, and public information. (P.A.)

Synthesis of functional materials by radiation

Energy Technology Data Exchange (ETDEWEB)

Nho, Young Chang; Kim, Ki Yup; Kang, Phil Hyun and others

2000-04-01

The radiation can induce chemical reaction to modify polymer under even the solid condition or in the low temperature. Therefore, the radiation processing is used as the means to develop the high functional polymer and new material which is impossible by chemical process. The radiation grafting process has the advantage to endow the adsorption function to the existing materials such as polymer membrane, fabric, non-fabric, non-woven fabric and film. Radiation crosslinking is effected with no pressure and is performed at low temperatures. Thus, temperature sensitive additives can be used in radiation crosslinking. The radiation crosslinking and grafting can be easily adjusted and is easily reproducible by controlling the radiation dose. The finished product contains no residuals of substances required to initiate the chemical crosslinking and grafting which can restrict the application possibilities, or can increase the failure rate. In these studies, radiation grafting and crosslinking were used to develop the toxic gas adsorbent, blood compatible polymer, acetabular cup of artificial joint, urokinase adsorbent, hydrogel, hollow fiber membrane adsorbing the heavy metals, and battery separator membrane. Because cable in nuclear power plant is directly related to safe operation, the life assessment of the cable system is an important issue. To assess the degradation and life time of cable is complicated owing to the various types and the different formulation of cable. In order to make an estimate the long term degradation occurring in a material, it is necessary to carry out the accelerated aging studies and to establish the appropriate test method to characterize the degradation. These studies are aimed at the evaluation technique on radiation degradation of polymer material and applying these results to nuclear equipment qualification.

Synthesis of functional materials by radiation

International Nuclear Information System (INIS)

Nho, Young Chang; Kim, Ki Yup; Kang, Phil Hyun and others

2000-04-01

The radiation can induce chemical reaction to modify polymer under even the solid condition or in the low temperature. Therefore, the radiation processing is used as the means to develop the high functional polymer and new material which is impossible by chemical process. The radiation grafting process has the advantage to endow the adsorption function to the existing materials such as polymer membrane, fabric, non-fabric, non-woven fabric and film. Radiation crosslinking is effected with no pressure and is performed at low temperatures. Thus, temperature sensitive additives can be used in radiation crosslinking. The radiation crosslinking and grafting can be easily adjusted and is easily reproducible by controlling the radiation dose. The finished product contains no residuals of substances required to initiate the chemical crosslinking and grafting which can restrict the application possibilities, or can increase the failure rate. In these studies, radiation grafting and crosslinking were used to develop the toxic gas adsorbent, blood compatible polymer, acetabular cup of artificial joint, urokinase adsorbent, hydrogel, hollow fiber membrane adsorbing the heavy metals, and battery separator membrane. Because cable in nuclear power plant is directly related to safe operation, the life assessment of the cable system is an important issue. To assess the degradation and life time of cable is complicated owing to the various types and the different formulation of cable. In order to make an estimate the long term degradation occurring in a material, it is necessary to carry out the accelerated aging studies and to establish the appropriate test method to characterize the degradation. These studies are aimed at the evaluation technique on radiation degradation of polymer material and applying these results to nuclear equipment qualification

Nuclear radiation in warfare

International Nuclear Information System (INIS)

Rotblat, J.

1986-01-01

The subject is covered in chapters, entitled: introduction; digest of nuclear weaponry (characteristics of nuclear weapons; effects of nuclear weapons other than ionizing radiation (fire-ball, fall-out, thermal radiation, blast wave, electromagnetic pulse); the nuclear arms race; war scenarios; biological effects of radiations on man (radiation doses; natural sources of radiation; acute effects of radiation; long-term somatic effects; genetic effects; factors affecting the biological response to radiation; internal exposure; synergistic effects; protection against radiation effects); radiations from nuclear explosions (initial radiation; fall-out; effects of fall-out on animal and plant life; contamination of water and food supplies by fall-out); radiation casualties in a nuclear war; effectiveness of civil defence; other warlike uses of radiation (attacks on civilian nuclear power installations; radiological warfare; terrorist activities); conclusion. (orig./HP) [de

Nuclear radiation in warfare

International Nuclear Information System (INIS)

Rotblat, J.

1981-01-01

The subject is covered in chapters, entitled: introduction; digest of nuclear weaponry (characteristics of nuclear weapons; effects of nuclear weapons other than ionizing radiation (fire-ball, fall-out, thermal radiation, blast wave, electromagnetic pulse); the nuclear arms race; war scenarios); biological effects of radiations on man (radiation doses; natural sources of radiation; acute effects of radiation; long-term somatic effects; genetic effects; factors affecting the biological response to radiation; internal exposure; synergistic effects; protection against radiation effects); radiations from nuclear explosions (initial radiation; fall-out; effects of fall-out on animal and plant life; contamination of water and food supplies by fall-out); radiation casualties in a nuclear war; effectiveness of civil defence; other warlike uses of radiation (attacks on civilian nuclear power installations; radiological warfare; terrorist activities); conclusion. (U.K.)

Problems on shipping high-enriched nuclear materials

International Nuclear Information System (INIS)

Ganzha, V.V.; Demko, N.A.; Deryavko, I.I.; Zelenski, D.I.; Kolbaenkov, A.N.; Pivovarov, O.S.; Storozhenko, A.N.; Chernyad'ev, V.V.; Yakovlev, V.V.; Gorin, N.V.; Prokhod'ko, A.I.; Sherbina, A.N.; Barsanov, V.I.; Dyakov, E.K.; Tishenko, M.F.; Khlystov, A.I.; Vasil'ev, A.P.; Smetannikov, V.P.

1998-01-01

In 1996-1998 all Russian nuclear materials were taken out of the Institute of Atomic Energy of Kazakhstan National Nuclear Centre (IAE NNC RK). In this report there are basic tasks related to the performance of this work. They are: 1) Preparation of Russian nuclear materials (NM) kept at IAE NNC RK for transportation; 2) accounting and control of Russian nuclear materials kept at IAE NNC RK; 3) arrangement of permit papers for NM transportation; 4) NM transportation from IAE NNC RK to the enterprises of Russian MINATOM; 5) provision of nuclear and radiation safety in the course of operations with NM; 6) provision of physical protection for Russian NM

Dictionary of radiation protection, radiobiology and nuclear medicine

Energy Technology Data Exchange (ETDEWEB)

Sube, R [comp.

1986-01-01

Radiation protection, including aspects of radiobiology, nuclear medicine, and nuclear legislation, has an important role within nuclear research and the use of radioactive materials. Radiation protection comprises all measures and efforts to prevent the unwanted distribution and negative influence of ionizing radiation, especially where the human organism and the living environment are involved. The increasing role of radiation protection is reflected by the foundation of institutes in all industrial countries to control such radiant energy and prevent radiation damage. Nowadays ionizing radiation is employed on a large scale for basic investigations in biochemistry, molecular biology and genetics, in soil tests, fertilization problems and pest control in agriculture, as well as for medicinal diagnoses and therapy. This dictionary is a thematic enlargement of the four-language 'Dictionary of Nuclear Engineering', compiled by the same author. It comprises about 12,000 terms in each language.

Nuclear technology in materials testing and radiation protection

International Nuclear Information System (INIS)

Neider, R.

1975-01-01

A report of the 1974 activities of the laboratories for physical and measuring technical fundamentals, radiation effects and radiation protection, application of radionuclides and testing of radioactive materials of the Bundesanstalt fuer Materialpruefung (BAM) is given. (RW/LH) [de

Proposal of secure camera-based radiation warning system for nuclear detection

International Nuclear Information System (INIS)

Tsuchiya, Ken'ichi; Kurosawa, Kenji; Akiba, Norimitsu; Kakuda, Hidetoshi; Imoto, Daisuke; Hirabayashi, Manato; Kuroki, Kenro

2016-01-01

Counter-terrorisms against radiological and nuclear threat are significant issues toward Tokyo 2020 Olympic and Paralympic Games. In terms of cost benefit, it is not easy to build a warning system for nuclear detection to prevent a Dirty Bomb attack (dispersion of radioactive materials using a conventional explosive) or a Silent Source attack (hidden radioactive materials) from occurring. We propose a nuclear detection system using the installed secure cameras. We describe a method to estimate radiation dose from noise pattern in CCD images caused by radiation. Some dosimeters under neutron and gamma-ray irradiations (0.1mSv-100mSv) were taken in CCD video camera. We confirmed amount of noise in CCD images increased in radiation exposure. The radiation detection using CMOS in secure cameras or cell phones has been implemented. However, in this presentation, we propose a warning system including neutron detection to search shielded nuclear materials or radiation exposure devices using criticality. (author)

Thermodynamics of nuclear materials

International Nuclear Information System (INIS)

1979-01-01

Full text: The science of chemical thermodynamics has substantially contributed to the understanding of the many problems encountered in nuclear and reactor technology. These problems include reaction of materials with their surroundings and chemical and physical changes of fuels. Modern reactor technology, by its very nature, has offered new fields of investigations for the scientists and engineers concerned with the design of nuclear fuel elements. Moreover, thermodynamics has been vital in predicting the behaviour of new materials for fission as well as fusion reactors. In this regard, the Symposium was organized to provide a mechanism for review and discussion of recent thermodynamic investigations of nuclear materials. The Symposium was held in the Juelich Nuclear Research Centre, at the invitation of the Government of the Federal Republic of Germany. The International Atomic Energy Agency has given much attention to the thermodynamics of nuclear materials, as is evidenced by its sponsorship of four international symposia in 1962, 1965, 1967, and 1974. The first three meetings were primarily concerned with the fundamental thermodynamics of nuclear materials; as with the 1974 meeting, this last Symposium was primarily aimed at the thermodynamic behaviour of nuclear materials in actual practice, i.e., applied thermodynamics. Many advances have been made since the 1974 meeting, both in fundamental and applied thermodynamics of nuclear materials, and this meeting provided opportunities for an exchange of new information on this topic. The Symposium dealt in part with the thermodynamic analysis of nuclear materials under conditions of high temperatures and a severe radiation environment. Several sessions were devoted to the thermodynamic studies of nuclear fuels and fission and fusion reactor materials under adverse conditions. These papers and ensuing discussions provided a better understanding of the chemical behaviour of fuels and materials under these

Better materials for nuclear energy

International Nuclear Information System (INIS)

Banerjee, S.

2005-01-01

The improved performance of present generation nuclear reactors and the realization of advanced reactor concepts, both, require development of better materials. Physical metallurgy /materials science principles which have been exploited in meeting the exacting requirements of nuclear systems comprising fuels, structural materials, moderators and coolants are outlined citing a few specific examples. While the incentive for improvement of traditional fuels (e.g., UO 2 fuel) is primarily for increasing the average core burn up, the development of advanced fuels (e.g., MOX, mixed carbide, nitride, silicide and dispersion fuels) are directed towards better utilization of fissile and fertile inventories through adaptation of innovative fuel cycles. As the burn up of UO 2 fuel reaches higher levels, a more detailed and quantitative understanding of the phenomena such as fission gas release, fuel restructuring - induced by radiation and thermal gradients and pellet-clad interaction is being achieved. Development of zirconium based alloys for both cladding and pressure tube applications is discussed with reference to their physical metallurgy, fabrication techniques, in-reactor degradation mechanisms, and in-service inspection. The issue of radiation embrittlement of reactor pressure vessels (RPVs) is covered drawing a comparison between the western and eastern specifications of RPV steels. The search for new materials which can stand higher rates of atomic displacement due to radiation has led to the development of swelling resistant austenitic and ferritic stainless steels for fast reactor applications as exemplified by the development of the D-9 steel for Indian fast breeder reactor. New challenges are thrown to material scientists for the development of materials suitable for high temperature reactors, which have a potential for providing primary heat for thermo chemical dissociation of water. Development of several ceramic materials, carbon based materials, dissimilar

Combating illicit trafficking in nuclear and other radioactive material. Reference material

International Nuclear Information System (INIS)

2007-01-01

This publication is intended for individuals and organizations that may be called upon to deal with the detection of and response to criminal or unauthorized acts involving nuclear or other radioactive material. It will also be useful for legislators, law enforcement agencies, government officials, technical experts, lawyers, diplomats and users of nuclear technology. This manual emphasizes the international initiatives for improving the security of nuclear and other radioactive material. However, it is recognized that effective measures for controlling the transfer of equipment, non-nuclear material, technology or information that may assist in the development of nuclear explosive devices, improvised nuclear devices (INDs) or other radiological dispersal devices (RDDs) are important elements of an effective nuclear security system. In addition, issues of personal integrity, inspection and investigative procedures are not discussed in this manual, all of which are essential elements for an effective overall security system. The manual considers a variety of elements that are recognized as being essential for dealing with incidents of criminal or unauthorized acts involving nuclear and other radioactive material. Depending on conditions in a specific State, including its legal and governmental infrastructure, some of the measures discussed will need to be adapted to suit that State's circumstances. However, much of the material can be applied directly in the context of other national programmes. This manual is divided into four main parts. Section 2 discusses the threat posed by criminal or unauthorized acts involving nuclear and other radioactive material, as well as the policy and legal bases underlying the international effort to restrain such activities. Sections 3 and 4 summarize the major international undertakings in the field. Sections 5-8 provide some basic technical information on radiation, radioactive material, the health consequences of radiation

Production of a nuclear radiation resistant and mechanically tough electrically insulating material

International Nuclear Information System (INIS)

Brechna, H.

1975-01-01

According to the invention, an electrically insulating material of high mechanical strength and resistance to nuclear radiation may be made of a hardenable plastic material coated on an inorganic supporting tissue. The synthetic resin serving as binder - duroplasts, e.g. epoxide resins, polyester resins or silicon resins - is heated, mixed with a catalyst, a wetting agent and a filler (and, if required, with 0.5-1.5 weight % thixotropic material) and coated, under reduced pressure (o.4 to 0.6 mm Hg), on the supporting tissue whose surface is cleaned before this by heating. It is then hardened. Hardening may also take place directly on the electric conductor to be insulated. One obtains a bubble-free wire coating. The inorganic supporting material is glas fibre tissue, also in combination with mica, while Al 2 O 3 , zirconium, zirconia, magnesium oxide, mica and silica (grain size 10-20 μ). The invention is illustrated by a number of examples. (UWI) [de

Graphite materials for nuclear reactors

International Nuclear Information System (INIS)

Oku, Tatsuo

1991-01-01

Graphite materials have been used in the nuclear fission reactors from the beginning of the reactor development for the speed reduction and reflection of neutron. Graphite materials are used both as a moderator and as a reflector in the core of high temperature gas-cooled reactors, and both as a radiation shielding material and as a reflector in the surrounding of the core for the fast breeder reactor. On the other hand, graphite materials are being positively used as a first wall of plasma as it is known that low Z materials are useful for holding high temperature plasma in the nuclear fusion devices. In this paper the present status of the application of graphite materials to the nuclear fission reactors and fusion devices (reactors) is presented. In addition, a part of results on the related properties to the structural design and safety evaluation and results examined on the subjects that should be done in the future are also described. (author)

Dictionary of radiation protection, radiobiology and nuclear medicine

International Nuclear Information System (INIS)

Sube, R.

1986-01-01

Radiation protection, including aspects of radiobiology, nuclear medicine, and nuclear legislation, has an important role within nuclear research and the use of radioactive materials. Radiation protection comprises all measures and efforts to prevent the unwanted distribution and negative influence of ionizing radiation, especially where the human organism and the living environment are involved. The increasing role of radiation protection is reflected by the foundation of institutes in all industrial countries to control such radiant energy and prevent radiation damage. Nowadays ionizing radiation is employed on a large scale for basic investigations in biochemistry, molecular biology and genetics, in soil tests, fertilization problems and pest control in agriculture, as well as for medicinal diagnoses and therapy. This dictionary is a thematic enlargement of the four-language 'Dictionary of Nuclear Engineering', compiled by the same author. It comprises about 12,000 terms in each language. (orig.)

Radiation protection in nuclear medicine

International Nuclear Information System (INIS)

Chougule, Arun

2014-01-01

The branch of medical science that utilizes the nuclear properties of the radioactivity and stable nuclides to make diagnostic evaluation of anatomical and/or physiological conditions of the body and provide therapy with unsealed radioactive sources is called Nuclear Medicine (NM). The use of unsealed radionuclides in medicine is increasing throughout the world for diagnosis and treatment. As per UNSCEAR report more than 6 million nuclear medicine procedures are conducted in a year. However we know that radiation is double edged sword and if not used carefully will be harmful to patient as well as staff and therefore a nuclear medicine procedure should be undertaken only after proper justification and optimization. Nuclear medicine procedures are different than the X-ray diagnostic procedures as in NM, radioisotope is administered to patient and patient becomes radioactive. The NM staff is involved in unpacking radioactive material, activity measurements, storage of sources, internal transports of sources, preparation of radiopharmaceuticals, administration of radiopharmaceutical, examination of the patient, care of the radioactive patient, handling of radioactive waste and therefore receives radiation dose. This talk will discuss the various steps for radiation safety of patient, staff and public during Nuclear Medicine procedures so as to implementing the ALARA concept. (author)

Radiation protection in nuclear medicine

International Nuclear Information System (INIS)

Seeburrun, V.

2013-04-01

Radiation protection in nuclear medicine in this project is concerned with the reduction of doses to workers, patients and members of the public. Protection of workers is achieved by adopting good personal habits, good housekeeping, proper use of personal protective devices and equipment, attend training and have continuous education. Exposure to radiation of workers and the members of the public are minimised by proper management of radioactive waste and safe transport of radioactive material. The design and shielding of a nuclear medicine department shall further provide for the protection of the worker, the patient and the general public. Protection of patient is achieved by justifying the procedure, delivering the minimum radiation dose possible to the patient while obtaining the best image quality and applying guidance levels. Special considerations shall be given to pregnant and breast-feeding patients. Quality assurance programme through image quality, radiopharmaceutical quality and patient records on nuclear medicine procedures shall provide assurance to the patient. (au)

Principles of nuclear radiation detection

International Nuclear Information System (INIS)

Eichholz, G.G.; Poston, J.W.

1985-01-01

This book covers the transistorization of equipment and provides an introduction into practice of semiconductor and thermoluminescent detectors. It discusses the principles of radiation detectors most widely used in nuclear technology, medical practice and radiation protection. It stresses the alternative detectors available and discusses practical considerations in choosing and setting up detector systems for actual use. Traditional materials, including semiconductors, TLD's and modern data handling facilities are covered

Radiation and Thermal Effects on Used Nuclear Fuel and Nuclear Waste Forms

Energy Technology Data Exchange (ETDEWEB)

Weber, William J. [Univ. of Tennessee, Knoxville, TN (United States). Dept. of Materials Science and Engineering; Zhang, Yanwen [Univ. of Tennessee, Knoxville, TN (United States). Dept. of Materials Science and Engineering

2016-09-20

This is the final report of the NEUP project “Radiation and Thermal Effects on Used Nuclear Fuel and Nuclear Waste Forms.” This project started on July 1, 2012 and was successfully completed on June 30, 2016. This report provides an overview of the main achievements, results and findings through the duration of the project. Additional details can be found in the main body of this report and in the individual Quarterly Reports and associated Deliverables of this project, which have been uploaded in PICS-NE. The objective of this research was to advance understanding and develop validated models on the effects of self-radiation from beta and alpha decay on the response of used nuclear fuel and nuclear waste forms during high-temperature interim storage and long-term permanent disposition. To achieve this objective, model used-fuel materials and model waste form materials were identified, fabricated, and studied.

High dose radiation damage in nuclear energy structural materials investigated by heavy ion irradiation simulation

International Nuclear Information System (INIS)

Zheng Yongnan; Xu Yongjun; Yuan Daqing

2014-01-01

Structural materials in ITER, ADS and fast reactor suffer high dose irradiations of neutrons and/or protons, that leads to severe displacement damage up to lOO dpa per year. Investigation of radiation damage induced by such a high dose irradiation has attracted great attention along with the development of nuclear energy facilities of new generation. However, it is deeply hampered for the lacking of high dose neutron and proton sources. Irradiation simulation of heavy ions produced by accelerators opens up an effective way for laboratory investigation of high dose irradiation induced radiation damage encountered in the ITER, ADS, etc. Radiation damage is caused mainly by atomic displacement in materials. The displacement rate of heavy ions is about lO 3 ∼10 7 orders higher than those of neutrons and protons. High displacement rate of heavy ions significantly reduces the irradiation time. The heavy ion irradiation simulation technique (HIIS) technique has been developed at China Institute of Atomic Energy and a series of the HIIS experiments have been performed to investigate radiation damage in stainless steels, tungsten and tantalum at irradiation temperatures from room temperature to 800 ℃ and in the irradiation dose region up to 100 dpa. The experimental results show that he radiation swelling peak for the modified stainless steel appears in the temperature region around 580 ℃ and the radiation damage is more sensitive to the temperature, the size of the radiation induced vacancy cluster or void increase with the increasing of the irradiation dose, and among the three materials the home-made modified stainless steel has the best radiation resistant property. (authors)

Radiation damage in organic materials

International Nuclear Information System (INIS)

Campbell, F.J.

1981-01-01

A surprising number of electrical components and seals are listed as being inside the containment building of a nuclear power plant. The types of radiation and their interaction with organic materials lead to a dosimetry discussion, and then a brief description of the chemical mechanisms which predominate in typical organic materials follows. Relative stability of polymer structures and the types of additives that contribute stabilization to the basic polymer matrix in formulated compounds are reviewed. However, the emphasis must now be directed toward the need to consider the total environment of nuclear plant service on the degradation of these materials if maximum reliability is to be achieved. The degradation mechanisms may be strongly affected by the dose-rate/oxidation effect. Temperature, steam and physical stress, when applied concurrently with the radiation field, can also influence the amount of absorbed dose required to produce a given change in the property being tested. Determining the degree of these influences and developing standardized test procedures to evaluate them have become the objective of several prominent research programs and international committee efforts. (author)

The Science of Nuclear Materials: A Modular, Laboratory-based Curriculum

Energy Technology Data Exchange (ETDEWEB)

Cahill, C.L., E-mail: cahill@gwu.edu [Department of Chemistry and Elliott School of International Affairs, The George Washington University, Washington, DC 20052 (United States); Feldman, G.; Briscoe, W.J. [Department of Physics, The George Washington University, Washington, DC 20052 (United States)

2014-06-15

The development of a curriculum for nuclear materials courses targeting students pursuing Master of Arts degrees at The George Washington University is described. The courses include basic concepts such as radiation and radioactivity as well as more complex topics such the nuclear fuel cycle, nuclear weapons, radiation detection and technological aspects of non-proliferation.

The Science of Nuclear Materials: A Modular, Laboratory-based Curriculum

International Nuclear Information System (INIS)

Cahill, C.L.; Feldman, G.; Briscoe, W.J.

2014-01-01

The development of a curriculum for nuclear materials courses targeting students pursuing Master of Arts degrees at The George Washington University is described. The courses include basic concepts such as radiation and radioactivity as well as more complex topics such the nuclear fuel cycle, nuclear weapons, radiation detection and technological aspects of non-proliferation

Risk Prevention for Nuclear Materials and Radioactive Sources

International Nuclear Information System (INIS)

Badawy, I.

2008-01-01

The present paper investigates the parameters which may have effects on the safety of nuclear materials and other radioactive sources used in peaceful applications of atomic energy. The emergency response planning in such situations are also indicated. In synergy with nuclear safety measures, an approach is developed in this study for risk prevention. It takes into consideration the collective implementation of measures of nuclear material accounting and control, physical protection and monitoring of such strategic and dangerous materials in an integrated and coordinated real-time mode at a nuclear or radiation facility and in any time

EV M-experiment in radiation material science

International Nuclear Information System (INIS)

Ganeev, G.Z.; Kislitsin, S.B.; Pyatiletov, Yu.S.; Turkebaev, T.Eh.; Tyupkina, O.G.

1999-01-01

To simulate rapid processes in materials, rearrangement at the atomic level, or processes in which the access to the materials is limited or considered to be hazardous, the EV M-experiment is going to be applied more often in the atomic material science (calculating experiment, computer-aided simulation). This paper presents the most important outcomes obtained from the calculating experiment carried out by scientists of the Institute of Nuclear Physics of NNC RK, who are considered to be followers of the scientific school named after Kirsanov V.V. The review consists of the following sections: 1. Simulation of dynamic processes of radiation damage of materials. 2. Simulation of radiation defects in materials. 3. Simulation of radiation defects migration processes in crystals. 4. Simulation of irradiated materials failure and deformation processes

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

Radiation Detection System for Prevention of Radiological and Nuclear Terrorism

International Nuclear Information System (INIS)

Kwak, Sung-Woo; Yoo, Ho-Sik; Jang, Sung-Sun; Kim, Jae-Kwang; Kim, Jung-Soo

2007-01-01

After the September 11 terrorist attack, the threat of a potential for a radiological or nuclear terrorist attack became more apparent. The threats relating to radiological or nuclear materials include a Radiological Dispersion Device (RDD), an Improved Nuclear Device (IND) or a State Nuclear Device (such as a Soviet manufactured suitcase nuclear weapon). For more effective countermeasures against the disaster, multilayer protection concept - prevention of smuggling of radioactive or nuclear material into our country through seaports or airports, detection and prevention of the threat materials in transit on a road, and prevention of their entry into a target building - is recommended. Due to different surrounding circumstances of where detection system is deployed, different types of radiation detection systems are required. There have been no studies on characteristics of detection equipment required under Korean specific conditions. This paper provides information on technical requirements of radiation detection system to achieve multi-layer countermeasures for the purpose of protecting the public and environment against radiological and nuclear terrorism

[Measures against Radiation Exposure Due to Large-Scale Nuclear Accident in Distant Place--Radioactive Materials in Nagasaki from Fukushima Daiichi Nuclear Power Plant].

Science.gov (United States)

Yuan, Jun; Sera, Koichiro; Takatsuji, Toshihiro

2015-01-01

To investigate human health effects of radiation exposure due to possible future nuclear accidents in distant places and other various findings of analysis of the radioactive materials contaminating the atmosphere of Nagasaki due to the Fukushima Daiichi Nuclear Power Plant accident. The concentrations of radioactive materials in aerosols in the atmosphere of Nagasaki were measured using a germanium semiconductor detector from March 2011 to March 2013. Internal exposure dose was calculated in accordance with ICRP Publ. 72. Air trajectories were analyzed using NOAA and METEX web-based systems. (134)Cs and (137)Cs were repeatedly detected. The air trajectory analysis showed that (134)Cs and (137)Cs flew directly from the Fukushima Daiichi Nuclear Power Plant from March to April 2011. However, the direct air trajectories were rarely detected after this period even when (134)Cs and (137)Cs were detected after this period. The activity ratios ((134)Cs/(137)Cs) of almost all the samples converted to those in March 2011 were about unity. This strongly suggests that the (134)Cs and (137)Cs detected mainly originated from the Fukushima Daiichi Nuclear Power Plant accident in March 2011. Although the (134)Cs and (137)Cs concentrations per air volume were very low and the human health effects of internal exposure via inhalation is expected to be negligible, the specific activities (concentrations per aerosol mass) were relatively high. It was found that possible future nuclear accidents may cause severe radioactive contaminations, which may require radiation exposure control of farm goods to more than 1000 km from places of nuclear accidents.

Nuclear Technology Series. Course 25: Radioactive Material Handling Techniques.

Science.gov (United States)

Center for Occupational Research and Development, Inc., Waco, TX.

This technical specialty course is one of thirty-five courses designed for use by two-year postsecondary institutions in five nuclear technician curriculum areas: (1) radiation protection technician, (2) nuclear instrumentation and control technician, (3) nuclear materials processing technician, (4) nuclear quality-assurance/quality-control…

Application of nuclear-physics methods in space materials science

Science.gov (United States)

Novikov, L. S.; Voronina, E. N.; Galanina, L. I.; Chirskaya, N. P.

2017-07-01

The brief history of the development of investigations at the Skobeltsyn Institute of Nuclear Physics, Moscow State University (SINP MSU) in the field of space materials science is outlined. A generalized scheme of a numerical simulation of the radiation impact on spacecraft materials and elements of spacecraft equipment is examined. The results obtained by solving some of the most important problems that modern space materials science should address in studying nuclear processes, the interaction of charged particles with matter, particle detection, the protection from ionizing radiation, and the impact of particles on nanostructures and nanomaterials are presented.

Nuclear safety and radiation protection report of the nuclear facilities - 2014

International Nuclear Information System (INIS)

2015-01-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the Tricastin operational hot base facility (INB no. 157, Bollene, Vaucluse (FR)), a nuclear workshop for storage and maintenance and qualification operations on some EdF equipments. Then, the nuclear safety and radiation protection measures taken regarding the facility are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2014, if some, are reported as well as the effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facility is presented and sorted by type of waste, quantities and type of conditioning. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions

Proceedings of the 6. Argentine congress on radiation protection and nuclear safety

International Nuclear Information System (INIS)

1998-01-01

The 6th Argentine Congress on Radiation Protection and Nuclear Safety was organized by the Radioprotection Argentine Society, in Buenos Aires, between the 22 and 24 of september of 1998. In this event, were presented almost 66 papers in the following sessions, about these subjects: 1.- Safety in nuclear installations. 2.- Control of nuclear material and physical protection of nuclear installations. 3.- Programs of quality assurance. 4.- Training, technical information and public information. 5.- Physical dosimetry. 6.- Physical dosimetry and occupational radiation protection. 7.- Exposure of the natural radiation. 8.- Environmental radiological safety. 9.- Biological effects of the ionizing radiations and biological dosimetry. 10.- Radiological protection of the medical practice and the radiological emergencies. 11.- Radioactive wastes management. 12.- Transport of radioactive materials

Development of superior radiation resistant materials and cables. 2

Energy Technology Data Exchange (ETDEWEB)

Ikehara, Junichiro; Kanemitsuya, Kazuhiko; Ohara, Hideo; Araki, Syogo; Hamachi, Katsuhiko [Mitsubishi Cable Industries Ltd., Tokyo (Japan)

1996-01-01

Many nuclear power plants have been constructed in Japan and electric power generation is now highly dependent on this technology. Therefore, the needs for facilities that will enrich and reprocess nuclear fuel from nuclear power stations will be high. As there are areas with high levels of radiation, the cables which can be used in these environments are needed. We have developed a superior radiation-resistant cable which uses halogen flame-retardant materials. This radiation-resistant cable consists of Ethylene-propylene rubber (EPDM) insulation and Chlorosulfonated polyethylene (CSM) sheath can be safely used in areas with high levels of radiation. We developed this product to aid in disaster prevention. Non-halogen, flame-retardant EPDM is used for the insulation, and low-halogen, flame-retardant CSM and new non-halogen, flame-retardant materials are used for the sheath. These cables have superior flame-retardant properties and generate little smoke on corrosive gas. This products can hence reduce the danger of a secondary disaster in a fire. We expect that these cables will find application in areas with high levels of radiation. (author).

Development of superior radiation resistant materials and cables. 2

International Nuclear Information System (INIS)

Ikehara, Junichiro; Kanemitsuya, Kazuhiko; Ohara, Hideo; Araki, Syogo; Hamachi, Katsuhiko

1996-01-01

Many nuclear power plants have been constructed in Japan and electric power generation is now highly dependent on this technology. Therefore, the needs for facilities that will enrich and reprocess nuclear fuel from nuclear power stations will be high. As there are areas with high levels of radiation, the cables which can be used in these environments are needed. We have developed a superior radiation-resistant cable which uses halogen flame-retardant materials. This radiation-resistant cable consists of Ethylene-propylene rubber (EPDM) insulation and Chlorosulfonated polyethylene (CSM) sheath can be safely used in areas with high levels of radiation. We developed this product to aid in disaster prevention. Non-halogen, flame-retardant EPDM is used for the insulation, and low-halogen, flame-retardant CSM and new non-halogen, flame-retardant materials are used for the sheath. These cables have superior flame-retardant properties and generate little smoke on corrosive gas. This products can hence reduce the danger of a secondary disaster in a fire. We expect that these cables will find application in areas with high levels of radiation. (author)

Technologies for detection of nuclear materials

International Nuclear Information System (INIS)

DeVolpi, A.

1996-01-01

Detection of smuggled nuclear materials at transit points requires monitoring unknown samples in large closed packages. This review contends that high-confidence nuclear-material detection requires induced fission as the primary mechanism, with passive radiation screening in a complementary role. With the right equipment, even small quantities of nuclear materials are detectable with a high probability at transit points. The equipment could also be linked synergistically with detectors of other contrabond. For screening postal mail and packages, passive monitors are probably more cost-effective. When a suspicious item is detected, a single active probe could then be used. Until active systems become mass produced, this two-stage screening/interrogation role for active/passive equipment is more economic for cargo at border crossings. For widespread monitoring of nuclear smuggling, it will probably be necessary to develop a system for simultaneously detecting most categories of contraband, including explosives and illicit drugs. With control of nuclear materials at known storage sites being the first line of defense, detection capabilities at international borders could establish a viable second line of defense against smuggling

Development of mobile radiation detection system against nuclear terrorism in Korea

International Nuclear Information System (INIS)

Kwak, Sung-Woo; Chang, Sung-Soon; Yoo, Ho-Sik

2011-01-01

A fixed radiation portal monitors (RPM) deployed at border, seaport, airport or key traffic checkpoints has played an important role in preventing the illicit trafficking and transport of nuclear and radioactive materials. However, the RPM usually is large and heavy and can't easily be moved to a different location. An intelligent terrorist may also circumvent the fixed RPM to avoid being detected. These reasons motivate us to develop a mobile radiation detection system. The objective of this paper is to report our experience on developing the mobile radiation detection system for the search and detection of nuclear and radioactive materials during road transport. Measurements were performed at various speeds and distances between the radioactive isotope (RI) transporting car and the measurement car. Results of our measurements and the detection limits of the system is described in this paper. The mobile radiation detection system developed should contribute to defending public's health and safety and the environment against nuclear and radiological terrorism by detecting nuclear or radioactive material hidden illegally in a vehicle. (author)

Pakistan nuclear safety and radiation protection ordinance-1984

International Nuclear Information System (INIS)

1984-01-01

An act to provide the regulations of nuclear safety and radiation protection in Pakistan has been explained. A legal and licensing procedure to handle production of nuclear materials, processing, storage of radioactive products and wastes has been described under this regulation. (A.B.)

Application of ceramic and glass materials in nuclear power plants

International Nuclear Information System (INIS)

Hamnabard, Z.

2008-01-01

Ceramic and glass are high temperature materials that can be used in many fields of application in nuclear industries. First, it is known that nuclear fuel UO 2 is a ceramic material. Also, ability to absorb neutrons without forming long lived radio-nuclides make the non-oxide ceramics attractive as an absorbent for neutron radiation arising in nuclear power plants. Glass-ceramic materials are a new type of ceramic that produced by the controlled nucleation and crystallization of glass, and have several advantages such as very low or null porosity, uniformity of microstructure, high chemical resistance etc. over conventional powder processed ceramics. These ceramic materials are synthesized in different systems based on their properties and applications. In nuclear industries, those are resistant to leaching and radiation damage for thousands of years, Such as glass-ceramics designed for radioactive waste immobilization and machinable glass-ceramics are used. This article introduces requirements of different glass and ceramic materials used in nuclear power plants and have been focused on developments in properties and application of them

Composite Materials under Extreme Radiation and Temperature Environments of the Next Generation Nuclear Reactors

International Nuclear Information System (INIS)

Simos, N.

2011-01-01

In the nuclear energy renaissance, driven by fission reactor concepts utilizing very high temperatures and fast neutron spectra, materials with enhanced performance that exceeds are expected to play a central role. With the operating temperatures of the Generation III reactors bringing the classical reactor materials close to their performance limits there is an urgent need to develop and qualify new alloys and composites. Efforts have been focused on the intricate relations and the high demands placed on materials at the anticipated extreme states within the next generation fusion and fission reactors which combine high radiation fluxes, elevated temperatures and aggressive environments. While nuclear reactors have been in operation for several decades, the structural materials associated with the next generation options need to endure much higher temperatures (1200 C), higher neutron doses (tens of displacements per atom, dpa), and extremely corrosive environments, which are beyond the experience on materials accumulated to-date. The most important consideration is the performance and reliability of structural materials for both in-core and out-of-core functions. While there exists a great body of nuclear materials research and operating experience/performance from fission reactors where epithermal and thermal neutrons interact with materials and alter their physio-mechanical properties, a process that is well understood by now, there are no operating or even experimental facilities that will facilitate the extreme conditions of flux and temperature anticipated and thus provide insights into the behaviour of these well understood materials. Materials, however, still need to be developed and their interaction and damage potential or lifetime to be quantified for the next generation nuclear energy. Based on material development advances, composites, and in particular ceramic composites, seem to inherently possess properties suitable for key functions within the

Lightweight Radiator for in Space Nuclear Electric Propulsion

Science.gov (United States)

Craven, Paul; Tomboulian, Briana; SanSoucie, Michael

2014-01-01

Nuclear electric propulsion (NEP) is a promising option for high-speed in-space travel due to the high energy density of nuclear fission power sources and efficient electric thrusters. Advanced power conversion technologies may require high operating temperatures and would benefit from lightweight radiator materials. Radiator performance dictates power output for nuclear electric propulsion systems. Game-changing propulsion systems are often enabled by novel designs using advanced materials. Pitch-based carbon fiber materials have the potential to offer significant improvements in operating temperature, thermal conductivity, and mass. These properties combine to allow advances in operational efficiency and high temperature feasibility. An effort at the NASA Marshall Space Flight Center to show that woven high thermal conductivity carbon fiber mats can be used to replace standard metal and composite radiator fins to dissipate waste heat from NEP systems is ongoing. The goals of this effort are to demonstrate a proof of concept, to show that a significant improvement of specific power (power/mass) can be achieved, and to develop a thermal model with predictive capabilities making use of constrained input parameter space. A description of this effort is presented.

Radiation dose registration and epidemiological study for workers of nuclear institutions in Japan

International Nuclear Information System (INIS)

Kumatori, T.

1992-01-01

The first nuclear reactor was operated in 1957 at Tokai-mura in Japan. Since then radiation dose of workers has been controlled by nuclear institutions according to the Law for the Regulations of Nuclear Source Material, Nuclear Fuel Material and Reactors. However, many nuclear power plants and other nuclear facilities were built, resulting in the remarkable increase of workers in controlled areas. Further, periodical inspection and repair work at nuclear facilities were carried out by employees of subcontractors, who were engaged in such work at many different facilities, so that it was getting more and more difficult to obtain accurate information of radiation dose on these workers. In order to meet this situation, the open-quotes Radiation Dose Registration Center for Workersclose quotes (RADREC) was established in November 1977 within the open-quotes Radiation Effects Associationclose quotes (REA), which was founded in September 1960 for the purpose of supporting the research on radiation effects and radiation protection. In January 1978, RADREC was designated by the Government as an organization to preserve the records on exposure of radiation workers, which was linked up with the registration system

Radiation, ionization, and detection in nuclear medicine

International Nuclear Information System (INIS)

Gupta, Tapan K.

2013-01-01

Up-to-date information on a wide range of topics relating to radiation, ionization, and detection in nuclear medicine. In-depth coverage of basic radiophysics relating to diagnosis and therapy. Extensive discussion of instrumentation and radiation detectors. Detailed information on mathematical modelling of radiation detectors. Although our understanding of cancer has improved, the disease continues to be a leading cause of death across the world. The good news is that the recent technological developments in radiotherapy, radionuclide diagnostics and therapy, digital imaging systems, and detection technology have raised hope that cancer will in the future be combatted more efficiently and effectively. For this goal to be achieved, however, safe use of radionuclides and detailed knowledge of radiation sources are essential. Radiation, Ionization, and Detection in Nuclear Medicine addresses these subjects and related issues very clearly and elaborately and will serve as the definitive source of detailed information in the field. Individual chapters cover fundamental aspects of nuclear radiation, including dose and energy, sources, and shielding; the detection and measurement of radiation exposure, with detailed information on mathematical modelling; medical imaging; the different types of radiation detector and their working principles; basic principles of and experimental techniques for deposition of scintillating materials; device fabrication; the optical and electrical behaviors of radiation detectors; and the instrumentation used in nuclear medicine and its application. The book will be an invaluable source of information for academia, industry, practitioners, and researchers.

Radiation, ionization, and detection in nuclear medicine

Energy Technology Data Exchange (ETDEWEB)

Gupta, Tapan K. [Radiation Monitoring Devices Research, Nuclear Medicine, Watertown, MA (United States)

2013-08-01

Up-to-date information on a wide range of topics relating to radiation, ionization, and detection in nuclear medicine. In-depth coverage of basic radiophysics relating to diagnosis and therapy. Extensive discussion of instrumentation and radiation detectors. Detailed information on mathematical modelling of radiation detectors. Although our understanding of cancer has improved, the disease continues to be a leading cause of death across the world. The good news is that the recent technological developments in radiotherapy, radionuclide diagnostics and therapy, digital imaging systems, and detection technology have raised hope that cancer will in the future be combatted more efficiently and effectively. For this goal to be achieved, however, safe use of radionuclides and detailed knowledge of radiation sources are essential. Radiation, Ionization, and Detection in Nuclear Medicine addresses these subjects and related issues very clearly and elaborately and will serve as the definitive source of detailed information in the field. Individual chapters cover fundamental aspects of nuclear radiation, including dose and energy, sources, and shielding; the detection and measurement of radiation exposure, with detailed information on mathematical modelling; medical imaging; the different types of radiation detector and their working principles; basic principles of and experimental techniques for deposition of scintillating materials; device fabrication; the optical and electrical behaviors of radiation detectors; and the instrumentation used in nuclear medicine and its application. The book will be an invaluable source of information for academia, industry, practitioners, and researchers.

History of radiation and nuclear disasters in the former USSR

International Nuclear Information System (INIS)

Malko, M.V.

2013-01-01

The report describes the history of radiation and nuclear accidents in the former USSR. These accidents accompanied development of military and civilian use of nuclear energy. Some of them as testing of the first Soviet nuclear, Kyshtym radiation accident, radiation contamination of the Karachai lake and the Techa river, nuclear accidents at the Soviet submarine on August 10, 1985 in the Chazhma Bay (near Vladivostok) as well as nuclear accidents on April 26, 1986 at the Chernobyl NPP were of large scale causing significant radiological problems for many hundreds thousands of people. There were a number of important reasons of these and other accidents. The most important among them were time pressure by development of nuclear weapon, an absence of required financial and material means for adequate management of problems of nuclear and radiation safety, and inadequate understanding of harmful interaction of ionizing radiation on organism as well as a hypersecrecy by realization of projects of military and civilian use of nuclear energy in the former USSR. (author)

Assessment of radiation shielding materials for protection of space crews using CR-39 plastic nuclear track detector

International Nuclear Information System (INIS)

DeWitt, J.M.; Benton, E.R.; Uchihori, Y.; Yasuda, N.; Benton, E.V.; Frank, A.L.

2009-01-01

A significant obstacle to long duration human space exploration such as the establishment of a permanent base on the surface of the Moon or a human mission to Mars is the risk posed by prolonged exposure to space radiation. In order to keep mission costs at acceptable levels while simultaneously minimizing the risk from radiation to space crew health and safety, a judicious use of optimized shielding materials will be required. We have undertaken a comprehensive study using CR-39 plastic nuclear track detector (PNTD) to characterize the radiation shielding properties of a range of materials-both common baseline materials such as Al and polyethylene, and novel multifunctional materials such as carbon composites-at heavy ion accelerators. The study consists of analyzing CR-39 PNTD exposed in front of and behind shielding targets of varying composition and at a number of depths (target thicknesses) relevant to the development and testing of materials for space radiation shielding. Most targets consist of 10 cm x 10 cm slabs of solid materials ranging in thickness from 1 to >30 g/cm 2 . Exposures have been made to beams of C, O, Ne, Si, Ar, and Fe at energies ranging from 290 MeV/amu to 1 GeV/amu at the National Institute of Radiological Sciences HIMAC and the NASA Space Radiation Laboratory (NSRL) at Brookhaven National Laboratory. Analysis of the exposed detectors yields LET spectrum, dose, and dose equivalent as functions of target depth and composition, and incident heavy ion charge, energy, and fluence. Efforts are currently underway to properly weigh and combine these results into a single quantitative estimate of a material's ability to shield space crews from the interplanetary galactic cosmic ray flux.

Spectral Analysis Method of Plastic Scintillator-based Radiation Detector against Nuclear/Radiological Terrorism

International Nuclear Information System (INIS)

Kwak, Sung-Woo; Yoo, Ho-Sik; Jang, Sung Soon; Kim, Jung-Soo; Yoon, Wan-Ki

2008-01-01

In these days, the threats relating to nuclear or radioactive materials have become a matter of internationally increased grave concern. A plastic scintillation detector in radiation portal monitoring (RPM) application has been used to detect radioactive sources in steel scrap entering reprocessing facilities, and to detect illicit transport of radioactive material across border ports-of-entry. The detection systems for RPM application usually are large and can not easily be moved to a different location. For some situations, an inconspicuous and mobile system for the radioactive or nuclear material during road transport is needed. The mobile radiation detection system has employed a NaI- based radiation detector to detect and identify the material hidden in vehicle. There are some operational constraints - short measuring time, weak activity due to heavy shield of illegal source, long distance - of inspection system in such nuclear security applications. Due to these constraints, large area sensor is required to maximize its sensitivity. Large NaI material, however, is extremely expensive. In designing a radiation detector for prevention of illicit trafficking of nuclear or radioactive materials, the trade-off should be carefully optimized between performance and cost in order to achieve cost-effective inspection system. For the cost-effective mobile radiation detection system, this paper describes new spectral analysis method to use the crude spectroscopic information available from a plastic detector to discriminate other man-made radiation source from NORM

Preliminary radiation criteria and nuclear analysis for ETF

International Nuclear Information System (INIS)

Engholm, B.A.

1980-09-01

Preliminary biological and materials radiation dose criteria for the Engineering Test Facility are described and tabulated. In keeping with the ETF Mission Statement, a key biological dose criterion is a 24-hour shutdown dose rate of 2 mrem/hr on the surface of the outboard bulk shield. Materials dose criteria, which primarily govern the inboard shield design, include 10 9 rads exposure limit to epoxy insulation, 3 x 10 -4 dpa damage to the TF coil copper stabilizer, and a total nuclear heating rate of 5 kW in the inboard TF coils. Nuclear analysis performed during FY 80 was directed primarily at the inboard and outboard bulk shielding, and at radiation streaming in the neutral beam drift ducts. Inboard and outboard shield thicknesses to achieve the biological and materials radiation criteria are 75 cm inboard and 125 cm outboard, the configuration consisting of alternating layers of stainless steel and borated water. The outboard shield also includes a 5 cm layer of lead. NBI duct streaming analyses performed by ORNL and LASL will play a key role in the design of the duct and NBI shielding in FY 81. The NBI aluminum cryopanel nuclear heating rate during the heating cycle is about 1 milliwatt/cm 3 , which is far less than the permissible limit

Nuclear safety and radiation protection report of Chinon nuclear facilities - 2012

International Nuclear Information System (INIS)

2013-01-01

This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the facilities (INBs no. 94 (irradiated materials workshop), 99 (fuel storage facility), 107 and 132 (NPPs in operation), 133, 153 and 161 (NPPs under deconstruction)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2012, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix. (J.S.)

Development of proactive technology against nuclear materials degradation

International Nuclear Information System (INIS)

Jeong, Yong Hwan; Kim, Hong Pyo; Lee, Bong Sang

2012-04-01

As the nuclear power plants are getting older, the extent of materials degradation increases and unexpected degradation mechanisms may occur under complex environments, including high-temperature and pressure, radiation and coolant. The components in the primary system are maintained at the temperature of 320 .deg. C, pressure of 2500 psi, and reactor internals are exposed to fast neutrons. The pipes and nozzles are affected by the mechanical, thermal and corrosive cyclic fatigue stresses. Since the steam generator tubes are affected by both primary and secondary coolants, the materials degradation mechanisms are dependent upon the multiple or complex factors. In this report, we make contribution to the enhancement of reactor safety by developing techniques for predicting and evaluating materials behaviors in nuclear environments. The research product in the following five areas, described in this report, plays a vital role in improving the safe operation of nuclear reactors, upgrading the level of skills and extending the use of nuclear power. Development of corrosion control and protection technology Development of fracture mechanical evaluation model of reactor pressure Development of prediction and analysis technology for radiation damage Development of advanced diagnostic techniques for micro-materials degradation Development of core technology for control of steam generator degradation

International dimension of illicit trafficking in nuclear and other radioactive material

International Nuclear Information System (INIS)

Zaitseva, L.; Bunn, G.; Steinhaeusler, F.

2002-01-01

Full text: Illicit trafficking in nuclear and other radioactive material is primarily associated with Russia and other former Soviet republics. Indeed, with the collapse of the former Soviet Union (FSU) in 1991, hundreds of tons of weapons-usable nuclear material and thousands of radiation sources were left without adequate control and protection, thus posing a risk for sabotage, theft and diversion. Out of 700 illicit trafficking incidents recorded in the Stanford's database on nuclear smuggling, theft and orphan radiation sources (DSTO), over 450 either took place in the former Soviet Union or involved material that had reportedly originated from the FSU. In the period 1992-1994, Western and Eastern Europe were heavily affected by the inflow of nuclear material smuggled from the FSU. Since then, various measures were taken by the European countries and former Soviet republics to prevent the trafficking of radioactive substances ranging from the improvement of physical security at nuclear facilities to the installation of detection equipment at international borders. However, although the number of illicit trafficking incidents in Western Europe has decreased dramatically since 1994 and the overall annual number of such cases has been lower than in 1994, evidence suggests that diverted nuclear material is still being smuggled out of the FSU. An increased number of interceptions of nuclear and other radioactive material in the Caucasus, Turkey and Central Asia, well-known for their drugs and arms smuggling routes, over the past three years demonstrates that the material may now be moving south rather than west. This is particularly alarming considering the proximity of three countries to the potential end-users of nuclear and other radioactive material, such as AI Qaida terrorist network and aspiring nuclear weapon states in the Middle East. Although the FSU remains the major potential source of nuclear and other radioactive material, it is not the only one. Thefts

German Democratic Republic State system of accounting for and control of nuclear material

International Nuclear Information System (INIS)

Roehnsch, W.; Gegusch, M.

1976-01-01

The system of accountancy for and control of nuclear material in the German Democratic Republic (GDR) with its legal bases and components is embedded in the overall State system of protection in the peaceful uses of nuclear energy. As the competent State authority, the Nuclear Safety and Radiation Protection Board of the GDR is also responsible for meeting the GDR's national and international tasks in the control of nuclear material. At enterprise level, the observance of all safety regulations for nuclear material, including the regulations for the control, is within the responsibility of managers of establishments, which are in any way concerned with the handling of nuclear material. To support managers and to function as internal control authorities, nuclear material officers have been appointed in these establishments. Design information, operating data, physical inventory of nuclear material and the respective enterprise records and reports are subject to State control by the Nuclear Material Inspectorate of the Nuclear Safety and Radiation Protection Board. This Inspectorate keeps the central records on nuclear material, forwards reports and information to, and maintains the necessary contacts with, the IAEA. For the nuclear material in the GDR four material balance areas have been established for control purposes. To rationalize central recording and reporting, electronic data processing is increasingly made use of. In a year-long national and international control of nuclear material, the State control system has stood the test and successfully co-operates with the IAEA. (author)

Nuclear safety and radiation protection report of the Chinon nuclear facilities - 2011

International Nuclear Information System (INIS)

2012-01-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Chinon nuclear power plant (Indre-et-Loire, 37 (FR)): 4 PWR reactors in operation (Chinon B, INB 107 and 132), 3 partially dismantled graphite-gas reactors (Chinon A, INB 133, 153 and 161), a workshop for irradiated materials (AMI, INB 94), and an inter-regional fuel storage facility (MIR, INB 99). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2011, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Nuclear safety and radiation protection report of the Chinon nuclear facilities - 2010

International Nuclear Information System (INIS)

2011-06-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Chinon nuclear power plant (Indre-et-Loire, 37 (FR)): 4 PWR reactors in operation (Chinon B, INB 107 and 132), 3 partially dismantled graphite-gas reactors (Chinon A, INB 133, 153 and 161), a workshop for irradiated materials (AMI, INB 94), and an inter-regional fuel storage facility (MIR, INB 99). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Nuclear and radiation technologies in Ukraine: opportunities, status and problems of implementation

International Nuclear Information System (INIS)

Gorbulyin, V.P.

2011-01-01

The collection contains research materials and information presented at the Scientific Conference 'Nuclear and radiation technologies in Ukraine' (September 17, 2009, Kyiv). The articles offered specific ways to address a number of issues relevant to nuclear energy, science, technology, medicine and related to the radiation and environmental safety, the use of radiation technologies in medicine, development of uranium and uranium processing industry, safety on factories of NFC, nuclear physical instrumentation, behaviour with radioactive wastes.

Radiation resistance of insulating materials for electric wires

International Nuclear Information System (INIS)

Kanemitsuya, Kazuhiko; Okuda, Tomoaki; Tachibana, Tadao; Yagi, Toshiaki; Seguchi, Tadao.

1990-01-01

In no halogen incombustible materials, smoke and poisonous gas generation at the time of burning is small, and corrosive gas rarely arises. Since no halogen electric wires and cables which use these material maintain safety for people and equipment in the case of fires, those are used for ships, tunnels, subways and so on. Also in nuclear power stations, the demand for no halogen cables becomes high although the condition of adoption is difficult. In this study, for the purpose of developing the no halogen cables for nuclear power stations, the basic data on the radiation resistance of no halogen incombustible materials were collected, and by using chemical analysis method, the radiation deterioration behavior was examined. The samples were those with base polymers of VLDPE, ULDPE, EEA, EMA and EVA. Gamma ray irradiation, tensile test, chemi-luminescence measurement, and the determination of gel fraction and swelling rate were carried out. The results are reported, In no halogen materials, when ethylene system copolymer is used as the base polymer instead of PE, the composition with good radiation resistance can be obtained, and by combining amine oxidation inhibitor, it is further improved. (K.I.)

Radiation shield for nuclear reactors

International Nuclear Information System (INIS)

Weissenfluh, J.A.

1978-01-01

A shield for use with nuclear reactor systems to attenuate radiation resulting from reactor operation is described. The shield comprises a container preferably of a thin, flexible or elastic material, which may be in the form of a bag, a mattress, a toroidal segment or toroid or the like filled with radiation attenuating liuid. Means are provided in the container for filling and draining the container in place. Due to its flexibility, the shield readily conforms to irregularities in surfaces with which it may be in contact in a shielding position

Radiation stability of fluorite-type nuclear oxides

Energy Technology Data Exchange (ETDEWEB)

Garrido, Frederico [Centre de Spectrometrie Nucleaire et de Spectrometrie de Masse, CNRS-IN2P3-Universite Paris-Sud, Batiments 104-108, 91405 Orsay Campus (France)], E-mail: Frederico.Garrido@csnsm.in2p3.fr; Vincent, Laetitia [Centre de Spectrometrie Nucleaire et de Spectrometrie de Masse, CNRS-IN2P3-Universite Paris-Sud, Batiments 104-108, 91405 Orsay Campus (France); Nowicki, Lech [Andrzej Soltan Institute for Nuclear Studies, Hoza 69, 00-681 Warsaw (Poland); Sattonnay, Gael [Laboratoire d' Etudes des Materiaux Hors-Equilibre, Institut de Chimie Moleculaire et des Materiaux d' Orsay, UMR 8182, Universite Paris-Sud, Batiment 410, 91405 Orsay Cedex (France); Thome, Lionel [Centre de Spectrometrie Nucleaire et de Spectrometrie de Masse, CNRS-IN2P3-Universite Paris-Sud, Batiments 104-108, 91405 Orsay Campus (France)

2008-06-15

Oxides with the fluorite-type structure are radiation tolerant materials. They are widely used or envisaged in hostile nuclear environments, such as nuclear fuels or inert transmutation matrices for actinide burning. Study of the radiation stability of this class of solids in various radiative fields is of major importance. Two issues which may affect the stability of materials are considered in this work: the production of radiation damage (ballistic contribution); the modification of the matrix composition by doping (chemical contribution). Both contributions may drastically affect the solid stability. Urania and zirconia single crystals were chosen as fluorite-type canonical systems. They were implanted with low-energy inert gases (He or Xe). The damage in-growth, due to both ballistic and chemical contributions, was investigated by in situ RBS/C experiments in the channelling mode and TEM. Two main steps in the disordering kinetics were observed for both inert gases. Relevant key parameters were found to be: the number of displaced lattice atoms created by the slowing-down of energetic ions during the implantation process; the concentration of noble gas atoms in the solid which cause the formation of large stress fields surrounding gas aggregates.

Tungsten - Yttrium Based Nuclear Structural Materials

Science.gov (United States)

Ramana, Chintalapalle; Chessa, Jack; Martinenz, Gustavo

2013-04-01

The challenging problem currently facing the nuclear science community in this 21st century is design and development of novel structural materials, which will have an impact on the next-generation nuclear reactors. The materials available at present include reduced activation ferritic/martensitic steels, dispersion strengthened reduced activation ferritic steels, and vanadium- or tungsten-based alloys. These materials exhibit one or more specific problems, which are either intrinsic or caused by reactors. This work is focussed towards tungsten-yttrium (W-Y) based alloys and oxide ceramics, which can be utilized in nuclear applications. The goal is to derive a fundamental scientific understanding of W-Y-based materials. In collaboration with University of Califonia -- Davis, the project is designated to demonstrate the W-Y based alloys, ceramics and composites with enhanced physical, mechanical, thermo-chemical properties and higher radiation resistance. Efforts are focussed on understanding the microstructure, manipulating materials behavior under charged-particle and neutron irradiation, and create a knowledge database of defects, elemental diffusion/segregation, and defect trapping along grain boundaries and interfaces. Preliminary results will be discussed.

Synthesis of functional materials by radiation and qualification testing of organic materials in nuclear power plant

International Nuclear Information System (INIS)

Nho, Young Chang; Kim, Ki Yup; Kang, Phil Hyun and others; Jun, Hong Jae; Suh, Dong Hak; Lee, Young Moo; Min, Byung Kak; Bae, You Han

2003-05-01

The radiation crosslinking and grafting can be easily adjusted and is easily reproducible by controlling the radiation dose. These studies aim to develop new biomaterials such as covering for burns and wound, and controlled release of drug. A radiation technology was used to develop PTC materials useful in devices that limit electric fault currents. Radiation-curing of fiber-matrix composites is a promising application. There are a number of advantages to radiation curing of composites, compared with conventional thermal processing. Radiation curing at ambient temperature allows tighter control of part dimensions, and elimination of internal stresses which otherwise occur on cooling and which reduce material strength. These studies involved radiation curing of epoxy resins with various fibers and filler for structural application for aerospace and sport goods. The chain scission is the basis of other radiation treatments aimed at enhancing processing characteristics of polymers. These studies aim to make PTFE powder from PTFE scrap using the radiation degradation which allows incorporation of the material into coatings, inks etc. Low density polyethylene, crosslinked polyethylene, ethylene propylene rubber, and acrylonitrile butadiene rubber as cable insulating, seathing and sealing materials were irradiated for the accelerated ageing tests. Degradation was investigated by measuring dielectric analysis, thermogravimetric analysis, and dynamic mechanical analysis. Dielectric tanδ, storage modulus and loss modulus were increased with irradiation doses. However, decomposition temperature decreased with irradiation doses

The nuclear safety authority (ASN) presents its report on the status of nuclear safety and radiation protection in France in 2010

International Nuclear Information System (INIS)

2011-01-01

After a presentation of the French nuclear safety authority (ASN) and of some events which occurred in 2010, this report present the actions performed by the ASN in different fields: nuclear activities (ionizing radiations and risks for health and for the environment), principles and actors of control of nuclear safety, radiation protection and environment protection, regulation, control of nuclear activities and of exposures to ionizing radiations, emergency situations, public information and transparency, international relationship. It proposes a regional overview of nuclear safety and radiation protection in France. It addresses the activities controlled by the ASN: medical and non medical usages of ionizing radiations, transportation of radioactive materials, electronuclear power stations, installations involved in the nuclear fuel cycle, research nuclear installations and other nuclear installations, safety in basic nuclear installation dismantling, radioactive wastes and polluted sites

Structural integrity of materials in nuclear service: a bibliography

International Nuclear Information System (INIS)

Heddleson, F.A.

1977-01-01

This report contains 679 abstracts from the Nuclear Safety Information Center (NSIC) computer file dated 1973 through 1976 covering material properties with respect to structural integrity. All materials important to the nuclear industry (except concrete) are covered for mechanical properties, chemical properties, corrosion, fracture or failure, radiation damage, creep, cracking, and swelling. Keyword, author, and permuted-title indexes are included for the convenience of the user

Structural integrity of materials in nuclear service: a bibliography

Energy Technology Data Exchange (ETDEWEB)

Heddleson, F.A.

1977-06-07

This report contains 679 abstracts from the Nuclear Safety Information Center (NSIC) computer file dated 1973 through 1976 covering material properties with respect to structural integrity. All materials important to the nuclear industry (except concrete) are covered for mechanical properties, chemical properties, corrosion, fracture or failure, radiation damage, creep, cracking, and swelling. Keyword, author, and permuted-title indexes are included for the convenience of the user.

Special nuclear material simulation device

Science.gov (United States)

Leckey, John H.; DeMint, Amy; Gooch, Jack; Hawk, Todd; Pickett, Chris A.; Blessinger, Chris; York, Robbie L.

2014-08-12

An apparatus for simulating special nuclear material is provided. The apparatus typically contains a small quantity of special nuclear material (SNM) in a configuration that simulates a much larger quantity of SNM. Generally the apparatus includes a spherical shell that is formed from an alloy containing a small quantity of highly enriched uranium. Also typically provided is a core of depleted uranium. A spacer, typically aluminum, may be used to separate the depleted uranium from the shell of uranium alloy. A cladding, typically made of titanium, is provided to seal the source. Methods are provided to simulate SNM for testing radiation monitoring portals. Typically the methods use at least one primary SNM spectral line and exclude at least one secondary SNM spectral line.

Cooperation in Nuclear Waste Management, Radiation Protection, Emergency Preparedness, Reactor Safety and Nuclear Non-Proliferation in Eastern Europe

International Nuclear Information System (INIS)

Dassen, Lars van; Delalic, Zlatan; Ekblad, Christer; Keyser, Peter; Turner, Roland; Rosengaard, Ulf; German, Olga; Grapengiesser, Sten; Andersson, Sarmite; Sandberg, Viviana; Olsson, Kjell; Stenberg, Tor

2009-10-01

The Swedish Radiation Safety Authority (SSM) is trusted with the task of implementing Sweden's bilateral assistance to Russia, Ukraine, Georgia, Belarus and Armenia in the fields of reactor safety, nuclear waste management, nuclear non-proliferation as well as radiation protection and emergency preparedness. In these fields, SSM also participates in various projects financed by the European Union. The purpose of this project-oriented report is to provide the Swedish Government and other funding agencies as well as other interested audiences in Sweden and abroad with an encompassing understanding of our work and in particular the work performed during 2008. the activities are divided into four subfields: Nuclear waste management; Reactor safety; Radiation safety and emergency preparedness; and, Nuclear non-proliferation. SSM implements projects in the field of spent nuclear fuel and radioactive waste management in Russia. The problems in this field also exist in other countries, yet the concentration of nuclear and radioactive materials are nowhere higher than in north-west Russia. And given the fact that most of these materials stem from the Cold War era and remain stored under conditions that vary from 'possibly acceptable' to 'wildly appalling' it is obvious that Sweden's first priority in the field of managing nuclear spent fuel and radioactive waste lies in this part of Russia. The prioritisation and selection of projects in reactor safety are established following thorough discussions with the partners in Russia and Ukraine. For specific guidance on safety and recommended safety improvements at RBMK and VVER reactors, SSM relies on analyses and handbooks established by the IAEA in the 1990s. In 2008, there were 16 projects in reactor safety. SSM implements a large number of projects in the field of radiation protection and emergency preparedness. The activities are at a first glance at some distance from the activities covered and foreseen by for instance the

Cooperation in Nuclear Waste Management, Radiation Protection, Emergency Preparedness, Reactor Safety and Nuclear Non-Proliferation in Eastern Europe

Energy Technology Data Exchange (ETDEWEB)

Dassen, Lars van; Delalic, Zlatan; Ekblad, Christer; Keyser, Peter; Turner, Roland; Rosengaard, Ulf; German, Olga; Grapengiesser, Sten; Andersson, Sarmite; Sandberg, Viviana; Olsson, Kjell; Stenberg, Tor

2009-10-15

The Swedish Radiation Safety Authority (SSM) is trusted with the task of implementing Sweden's bilateral assistance to Russia, Ukraine, Georgia, Belarus and Armenia in the fields of reactor safety, nuclear waste management, nuclear non-proliferation as well as radiation protection and emergency preparedness. In these fields, SSM also participates in various projects financed by the European Union. The purpose of this project-oriented report is to provide the Swedish Government and other funding agencies as well as other interested audiences in Sweden and abroad with an encompassing understanding of our work and in particular the work performed during 2008. the activities are divided into four subfields: Nuclear waste management; Reactor safety; Radiation safety and emergency preparedness; and, Nuclear non-proliferation. SSM implements projects in the field of spent nuclear fuel and radioactive waste management in Russia. The problems in this field also exist in other countries, yet the concentration of nuclear and radioactive materials are nowhere higher than in north-west Russia. And given the fact that most of these materials stem from the Cold War era and remain stored under conditions that vary from 'possibly acceptable' to 'wildly appalling' it is obvious that Sweden's first priority in the field of managing nuclear spent fuel and radioactive waste lies in this part of Russia. The prioritisation and selection of projects in reactor safety are established following thorough discussions with the partners in Russia and Ukraine. For specific guidance on safety and recommended safety improvements at RBMK and VVER reactors, SSM relies on analyses and handbooks established by the IAEA in the 1990s. In 2008, there were 16 projects in reactor safety. SSM implements a large number of projects in the field of radiation protection and emergency preparedness. The activities are at a first glance at some distance from the activities covered and

Radiation effects on power cables for nuclear power plants

International Nuclear Information System (INIS)

Arora, R.; Munshi, P.; Badshah, M.G.Q.

1988-01-01

A large number of power and control cables, insulated with organic/polymeric materials, are installed quite near the reactor in nuclear power plants. The reliability of electrical equipment, receiving power through these cables, is critically important for the design and safety of the power stations. The radiation intensity inside the containment varies significantly from one location to another. The extent of material degradation is associated with the local radiation intensity. The cables used in the nuclear environment require several unique properties, the most obvious of these being radiation resistance, fire resistance, and the ability to withstand the loss-of-coolant accident in a nuclear power plant as specified in Institute of Electrical and Electronics Engineers (IEEE) Standard 383. In this study, four specific electrical power cable samples insulated with polyethylene, polyvinyl chloride, ethylene propylene rubber, and silicone rubber were chosen to investigate the effect of radiation in reactor environments on the electrical properties of the samples. Voltage breakdown tests and dielectric loss factor (tan δ) and conductor resistance measurements were carried out on each sample before and after irradiating them to near lifetime doses at ambient temperatures in atmospheric conditions

Nuclear safety and radiation protection report of the Fessenheim nuclear facilities - 2011

International Nuclear Information System (INIS)

2012-01-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Fessenheim nuclear power plant (INB 75, Haut-Rhin, 68 (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2011, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Nuclear safety and radiation protection report of the Gravelines nuclear facilities - 2013

International Nuclear Information System (INIS)

2014-01-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Gravelines nuclear power plant (INB 96, 97 and 122, Nord (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2013, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions

Nuclear safety and radiation protection report of the Penly nuclear facilities - 2010

International Nuclear Information System (INIS)

2011-06-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Penly nuclear power plant (INB 136 and 140, Seine-Maritime, 76 (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Nuclear safety and radiation protection report of the Fessenheim nuclear facilities - 2010

International Nuclear Information System (INIS)

2011-06-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Fessenheim nuclear power plant (INB 75, Haut-Rhin, 68 (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Nuclear safety and radiation protection report of the Blayais nuclear facilities - 2011

International Nuclear Information System (INIS)

2012-01-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Blayais nuclear power plant (INB 86 and 110, Gironde (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2011, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Nuclear safety and radiation protection report of the Gravelines nuclear facilities - 2011

International Nuclear Information System (INIS)

2012-01-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Gravelines nuclear power plant (INB 96, 97 and 122, Nord (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2011, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Nuclear safety and radiation protection report of the Gravelines nuclear facilities - 2012

International Nuclear Information System (INIS)

2013-01-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Gravelines nuclear power plant (INB 96, 97 and 122, Nord (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2012, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions

Nuclear safety and radiation protection report of the Penly nuclear facilities - 2011

International Nuclear Information System (INIS)

2012-01-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Penly nuclear power plant (INB 136 and 140, Seine-Maritime, 76 (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2011, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Nuclear safety and radiation protection report of the Gravelines nuclear facilities - 2014

International Nuclear Information System (INIS)

2015-01-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Gravelines nuclear power plant (INB 96, 97 and 122, Nord (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2014, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions

Nuclear safety and radiation protection report of the Gravelines nuclear facilities - 2010

International Nuclear Information System (INIS)

2011-06-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Gravelines nuclear power plant (INB 96, 97 and 122, Nord (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Nuclear safety and radiation protection report of the Civaux nuclear facilities - 2011

International Nuclear Information System (INIS)

2012-01-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Civaux nuclear power plant (INB 158 and 159, Vienne (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2011, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Nuclear safety and radiation protection report of the Blayais nuclear facilities - 2010

International Nuclear Information System (INIS)

2011-06-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Blayais nuclear power plant (INB 86 and 110, Gironde (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Nuclear safety and radiation protection report of the Civaux nuclear facilities - 2010

International Nuclear Information System (INIS)

2011-06-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Civaux nuclear power plant (INB 158 and 159, Vienne (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Report on the legislation in the field of nuclear safety and regulatory control of radiation sources and radioactive materials in Yugoslavia

International Nuclear Information System (INIS)

Kolundzija, V.

2001-01-01

The national regulatory infrastructure in Yugoslavia is described in the report, including the legal framework governing the safety of radiation sources and the security of radioactive materials. The organization and competencies of the Yugoslav Nuclear Safety Administration are explained, in particular regarding the national system of notification, registration, licensing, inspection and enforcement of radiation sources and radioactive materials, where the Federal Ministry of Economy and the Federal Ministry of Labour, Health and Social Policy are sharing competencies. Finally, the report refers to the national provisions on the management of disused sources; on planning, preparedness and response to abnormal events and emergencies; on the recovery of control over orphan sources; and on the education and training in the safety of radiation sources and the security of radioactive materials. (author)

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

International Nuclear Information System (INIS)

2014-01-01

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

New aspects regarding to radiation protection in nuclear medicine

International Nuclear Information System (INIS)

Shabestani Monfared, A.; Amiri, M.

2002-01-01

Introduction and objectives: The society has been concerned about nuclear energy usage and nuclear environment pollution for ages. The necessity of using radiation and its applications in modern life especially in medicine is undeniable. Some interesting properties such as the potential for non-destructive tests, detection simplicity, and penetrability into substances and having reactions with them cause radiation to be known as a useful tool for peace purposes. Nuclear weapons' experiments (1945-1973) and nuclear accidents in Three-Mile Island in USA, Goiania in Brazil and Chernobyl in Ukraine Republic have enhanced man's worries towards nuclear radiation and radioactivity in environment, and founding associations and groups which are against nuclear energy, such as green peace society, can be related with above mentioned concerns. Today, nuclear medicine has rapidly been developed so that in some cases plays a unique role in diagnosis but unfortunately in spite of diagnostic and therapeutic advantages, the term N UCLEAR c an induce worries in patients and society. In this article, base on new documents we intend to show that this worries has no scientific basis. Material and Methods: To produce a realistic view, regarding to radiation protection we used several ways such as natural origin of radiation, high natural background radiation areas' data non-linear dose-effect model, risk versus benefit, use of arbitrary unit for measurement of radiation, radio adaptive response and radiation hormesis. Discussion and conclusion: Harmful effects of radiation on biologic systems has obviously been shown, but most of related documents are based on receiving high doses in nuclear and atomic accidents and explosions and radiation protection regulations are based on this observations. So, it sometimes causes patients are afraid of low doses of radiation in medical diagnostic procedures so that some of them even resist against performing this procedures. Thus, being aware of

Nuclear energy - Fissile materials - Principles of criticality safety in storing, handling and processing

International Nuclear Information System (INIS)

1995-01-01

This International Standard specifies the basic principles and limitations which govern operations with fissile materials. It discusses general criticality safety criteria for equipment design and for the development of operating controls, while providing guidance for the assessment of procedures, equipment, and operations. It does not cover quality assurance requirements or details of equipment or operational procedures, nor does it cover the effects of radiation on man or materials, or sources of such radiation, either natural or as the result of nuclear chain reactions. Transport of fissile materials outside the boundaries of nuclear establishments is not within the scope of this International Standard and should be governed by appropriate national and international standards and regulations. These criteria apply to operations with fissile materials outside nuclear reactors but within the boundaries of nuclear establishments. They are concerned with the limitations which must be imposed on operations because of the unique properties of these materials which permit them to support nuclear chain reactions. These principles apply to quantities of fissile materials in which nuclear criticality can be established

Safeguards for nuclear material transparency monitoring

International Nuclear Information System (INIS)

MacArthur, D.A.; Wolford, J.K.

1999-01-01

The US and the Russian Federation are currently engaged in negotiating or implementing several nuclear arms and nuclear material control agreements. These involve placing nuclear material in specially designed containers within controlled facilities. Some of the agreements require the removal of nuclear components from stockpile weapons. These components are placed in steel containers that are then sealed and tagged. Current strategies for monitoring the agreements involve taking neutron and gamma radiation measurements of components in their containers to monitor the presence, mass, and composition of plutonium or highly enriched uranium, as well as other attributes that indicate the use of the material in a weapon. If accurate enough to be useful, these measurements will yield data containing information about the design of the weapon being monitored. In each case, the design data are considered sensitive by one or both parties to the agreement. To prevent the disclosure of this information in a bilateral or trilateral inspection scenario, so-called information barriers have evolved. These barriers combine hardware, software, and procedural safeguards to contain the sensitive data within a protected volume, presenting to the inspector only the processed results needed for verification. Interlocks and volatile memory guard against disclosure in case of failure. Implementing these safeguards requires innovation in radiation measurement instruments and data security. Demonstrating their reliability requires independent testing to uncover any flaws in design. This study discusses the general problem and gives a proposed solution for a high resolution gamma ray detection system. It uses historical examples to illustrate the evolution of other successful systems

Nuclear reactor structural material forming less radioactive corrosion product

International Nuclear Information System (INIS)

Nakazawa, Hiroshi.

1988-01-01

Purpose: To provide nuclear reactor structural materials forming less radioactive corrosion products. Constitution: Ni-based alloys such as inconel alloy 718, 600 or inconel alloy 750 and 690 having excellent corrosion resistance and mechanical property even in coolants at high temperature and high pressure have generally been used as nuclear reactor structural materials. However, even such materials yield corrosion products being attacked by coolants circulating in the nuclear reactor, which produce by neutron irradiation radioactive corrosion products, that are deposited in primary circuit pipeways to constitute exposure sources. The present invention dissolves dissolves this problems by providing less activating nuclear reactor structural materials. That is, taking notice on the fact that Ni-58 contained generally by 68 % in Ni changes into Co-58 under irradiation of neutron thereby causing activation, the surface of nuclear reactor structural materials is applied with Ni plating by using Ni with a reduced content of Ni-58 isotopes. Accordingly, increase in the radiation level of the nuclear reactor structural materials can be inhibited. (K.M.)

Evaluation and development of advanced nuclear materials: IAEA activities

International Nuclear Information System (INIS)

Inozemtsev, V.; Basak, U.; Killeen, J.; Dyck, G.; Zeman, A.; )

2011-01-01

Economical, environmental and non-proliferation issues associated with sustainable development of nuclear power bring about a need for optimization of fuel cycles and implementation of advanced nuclear systems. While a number of physical and design concepts are available for innovative reactors, the absence of reliable materials able to sustain new challenging irradiation conditions represents the real bottle-neck for practical implementation of these promising ideas. Materials performance and integrity are key issues for the safety and competitiveness of future nuclear installations being developed for sustainable nuclear energy production incorporating fuel recycling and waste transmutation systems. These systems will feature high thermal operational efficiency, improved utilization of resources (both fissile and fertile materials) and reduced production of nuclear waste. They will require development, qualification and deployment of new and advanced fuel and structural materials with improved mechanical and chemical properties combined with high radiation and corrosion resistance. The extensive, diverse, and expensive efforts toward the development of these materials can be more effectively organized within international collaborative programmes with wide participation of research, design and engineering communities. IAEA carries out a number of international projects supporting interested Member States with the use of available IAEA program implementation tools (Coordinated Research Projects, Technical Meetings, Expert Reviews, etc). The presentation summarizes the activities targeting material developments for advanced nuclear systems, with particular emphasis on fast reactors, which are the focal topics of IAEA Coordinated Research Projects 'Accelerator Simulation and Theoretical Modelling of Radiation Effects' (on-going), 'Benchmarking of Structural Materials Pre-Selected for Advanced Nuclear Reactors', 'Examination of advanced fast reactor fuel and core

Nuclear safety and radiation protection report of the Chinon nuclear facilities - 2014

International Nuclear Information System (INIS)

2015-01-01

This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the facilities (INBs no. 94 (irradiated materials workshop), 99 (fuel storage facility), 107 and 132 (NPPs in operation), 133, 153 and 161 (NPPs under deconstruction)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2014, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

Nuclear safety and radiation protection report of the Chinon nuclear facilities - 2013

International Nuclear Information System (INIS)

2014-01-01

This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the facilities (INBs no. 94 (irradiated materials workshop), 99 (fuel storage facility), 107 and 132 (NPPs in operation), 133, 153 and 161 (NPPs under deconstruction)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2013, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

Nuclear instrumentation for radiation measurement

International Nuclear Information System (INIS)

Madan, V.K.

2012-01-01

Nuclear radiation cannot be detected by human senses. Nuclear detectors and associated electronics facilitate detection and measurement of different types of radiation like alpha particles, beta particles, gamma radiation, and detection of neutrons. Nuclear instrumentation has evolved greatly since the discovery of radioactivity. There has been tremendous advancement in detector technology, electronics, computer technology, and development of efficient algorithms and methods for spectral processing to extract precisely qualitative and quantitative information of the radiation. Various types of detectors and nuclear instruments are presently available and are used for different applications. This paper describes nuclear radiation, its detection and measurement and associated electronics, spectral information extraction, and advances in these fields. The paper also describes challenges in this field

The Radiation Safety Information Computational Center (RSICC): A Resource for Nuclear Science Applications

Energy Technology Data Exchange (ETDEWEB)

Kirk, Bernadette Lugue [ORNL

2009-01-01

The Radiation Safety Information Computational Center (RSICC) has been in existence since 1963. RSICC collects, organizes, evaluates and disseminates technical information (software and nuclear data) involving the transport of neutral and charged particle radiation, and shielding and protection from the radiation associated with: nuclear weapons and materials, fission and fusion reactors, outer space, accelerators, medical facilities, and nuclear waste management. RSICC serves over 12,000 scientists and engineers from about 100 countries.

Tamper and radiation resistant instrumentation for safeguarding special nuclear materials

International Nuclear Information System (INIS)

Parsons, B.B.; Wells, J.L.

1977-01-01

A tamper-resistant liquid level/accountability instrumentation system for safeguards use has been developed and tested. The tests demonstrate the accuracy of liquid level measurement using TDR (Time Domain Reflectometry) techniques and the accuracy of differential pressure and temperature measurements utilizing a custom designed liquid level sensor probe. The calibrated liquid level, differential pressure, and temperature data provide sufficient information to accurately determine volume, density, and specific gravity. Test solutions used include ordinary tap water, diluted nitric acid in varying concentrations, and diluted uranium trioxide also in varying concentrations. System operations and preliminary test results conducted at the General Electric Midwest Fuel Recovery Plant and the National Bureau of Standards, respectively, suggest that the system will provide the safeguards inspector with an additional tool for real-time independent verification of normal operations and special nuclear materials accountancy data for chemical reprocessing plants. This paper discusses the system design concepts, including a brief description of the tamper and radiation resistant features, the preliminary test results, and the significance of the work

Proceedings of the 6. Argentine congress on radiation protection and nuclear safety; Actas del 6. congreso argentino de proteccion radiologica y seguridad nuclear

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-12-31

The 6th Argentine Congress on Radiation Protection and Nuclear Safety was organized by the Radioprotection Argentine Society, in Buenos Aires, between the 22 and 24 of september of 1998. In this event, were presented almost 66 papers in the following sessions, about these subjects: 1.- Safety in nuclear installations. 2.- Control of nuclear material and physical protection of nuclear installations. 3.- Programs of quality assurance. 4.- Training, technical information and public information. 5.- Physical dosimetry. 6.- Physical dosimetry and occupational radiation protection. 7.- Exposure of the natural radiation. 8.- Environmental radiological safety. 9.- Biological effects of the ionizing radiations and biological dosimetry. 10.- Radiological protection of the medical practice and the radiological emergencies. 11.- Radioactive wastes management. 12.- Transport of radioactive materials

Penetrating radiation as a tool for quality evaluation of nuclear fuels

International Nuclear Information System (INIS)

Ghosh, J.K.; Panakkal, J.P.; Chandrasekharan, K.N.; Subramanian, A.; Roy, P.R.

1983-01-01

Radiography is a universally accepted non-destructive evaluation technique for checking internal details of sealed components. Imaging nuclear fuels pose problems because of the high radiation attenuation of fuel materials. Radiography of nuclear fuels by penetrating radiations viz. X-rays, gamma rays and neutron is employed in the quality control of such fuels. This paper records the experience gathered during the inspection of nuclear fuel elements of different types fabricated at Radiometallurgy Division, B.A.R.C. and presents a comparative study of these three techniques in revealing inner details of nuclear fuels. (author)

Pakistan nuclear safety and radiation protection regulation 1990

International Nuclear Information System (INIS)

1990-01-01

In this act regulations of nuclear safety and radiation protection in Pakistan has been explained. A legal and licensing procedure to handle protection of nuclear materials, processing storage of radioactive products has been described under this regulation. In these regulations full explanation of accidental exposure, delegation of powers and record keeping/waste disposal of radioactive has been given. (A.B.)

Radiation and nuclear technologies in the Institute for Nuclear Research NAS of Ukraine

International Nuclear Information System (INIS)

Vishnevs'kij, Yi.M.; Gajdar, G.P.; Kovalenko, O.V.; Kovalyins'ka, T.V.; Kolomyijets', M.F.; Lips'ka, A.Yi.; Litovchenko, P.G.; Sakhno, V.Yi.; Shevel', V.M.

2014-01-01

The monograph describes some of the important developments of radiation and nuclear technology, made in INR NAS Ukraine. The first section describes radiation producing new materials and services using electrons with energies up to 5 MeV and Bremsstrahlung X-rays. We describe the original technology using ion emissions of the low and very low energies. In the second section the nuclear technologies, where ions, neutrons and other high-energy particles with energies are used, provide modification of the structure of matter nuclei in particular - radioactive isotopes for industrial and medical supplies and devices based on them.

Regulations concerning the fabricating business of nuclear fuel materials

International Nuclear Information System (INIS)

1985-01-01

In the Law for the Regulations of Nuclear Source Material, Nuclear Fuel Material and Reactors, the regulations have all been revised on the fabrication business of nuclear fuel materials. The revised regulations are given : application for permission of the fabrication business, application for permission of the alteration, application for approval of the design and the construction methods, application for approval of the alteration, application for the facilities inspection, facilities inspection, recordings, entry limitations etc. for controlled areas, measures concerning exposure radiation doses etc., operation of the fabrication facilities, transport within the site of the business, storage, disposal within the site of the business, security regulations, designation etc. of the licensed engineer of nuclear fuels, collection of reports, etc. (Mori, K.)

Illicit trafficking of nuclear material and other radioactive sources

International Nuclear Information System (INIS)

Yilmazer, A.; Yuecel, A.; Yavuz, U.

2001-01-01

As it is known, for the fact that the illicit trafficking and trading of nuclear materials are being increased over the past few years because of the huge demand of third world states. Nuclear materials like uranium, plutonium, and thorium are used in nuclear explosives that have very attractive features for crime groups, terrorist groups and, the states that are willing to have this power. Crime groups that make illegal trade of nuclear material are also trying to market strategic radioactive sources like red mercury and Osmium. This kind of illegal trade threats public safety, human health, environment also it brings significant threat on world peace and world public health. For these reasons, both states and international organizations should take a role in dealing with illicit trafficking. An important precondition for preventing this kind of incidents is the existence of a strengthened national system for control of all nuclear materials and other radioactive sources. Further, Governments are responsible for law enforcement within their borders for prevention of illegal trading and trafficking of nuclear materials and radiation sources

Radiation versus radiation: nuclear energy in perspective

International Nuclear Information System (INIS)

Gonzalez, A.J.; Anderer, J.

1989-01-01

This paper seeks to provide a proper perspective on radiation exposures from nuclear energy. Instead of comparing these exposures with other pollutants, natural and man-made, it assesses the radiation doses that result from the human environment and from the entire fuel cycle associated with nuclear generated electricity. It explores radiation versus radiation, not only in terms of absolute levels but, more importantly, of the enormous variability characterizing many radiation sources. The quantitative findings and their implications are meant to contribute to a balanced understanding of the radiological impact of nuclear energy, and so to help to bridge the information gap that is perceived to exist on this issue. The 1988 Unscear report and its seven scientific annexes provide an authoritative and dispassionate factual basis for examining radiation levels from all sources, natural and man-made. It is the main source for this paper. (author)

Basic mechanisms of radiation effects on electronic materials and devices

International Nuclear Information System (INIS)

Winokur, P.S.

1989-01-01

Many defense and nuclear reactor systems require complementary metal-oxide semiconductor integrated circuits that are tolerant to high levels of radiation. This radiation can result from space, hostile environments or nuclear reactor and accelerator beam environments. In addition, many techniques used to fabricate today's complex very-large-scale integration circuits expose the circuits to ionizing radiation during the process sequence. Whatever its origin, radiation can cause significant damage to integrated-circuit materials. This damage can lead to circuit performance degradation, logic upset, and even catastrophic circuit failure. This paper provides a brief overview of the basic mechanisms for radiation damage to silicon-based integrated circuits. Primary emphasis is on the effects of total-dose ionizing radiation on metal-oxide-semiconductor (MOS) structures

Radiation safety in nuclear medicine procedures

International Nuclear Information System (INIS)

Cho, Sang Geon; Kim, Ja Hae; Song, Ho Chun

2017-01-01

Since the nuclear disaster at the Fukushima Daiichi Nuclear Power Plant in 2011, radiation safety has become an important issue in nuclear medicine. Many structured guidelines or recommendations of various academic societies or international campaigns demonstrate important issues of radiation safety in nuclear medicine procedures. There are ongoing efforts to fulfill the basic principles of radiation protection in daily nuclear medicine practice. This article reviews important principles of radiation protection in nuclear medicine procedures. Useful references, important issues, future perspectives of the optimization of nuclear medicine procedures, and diagnostic reference level are also discussed

Radiation safety in nuclear medicine procedures

Energy Technology Data Exchange (ETDEWEB)

Cho, Sang Geon; Kim, Ja Hae; Song, Ho Chun [Dept. of Nuclear Medicine, Medical Radiation Safety Research Center, Chonnam National University Hospital, Gwangju (Korea, Republic of)

2017-03-15

Since the nuclear disaster at the Fukushima Daiichi Nuclear Power Plant in 2011, radiation safety has become an important issue in nuclear medicine. Many structured guidelines or recommendations of various academic societies or international campaigns demonstrate important issues of radiation safety in nuclear medicine procedures. There are ongoing efforts to fulfill the basic principles of radiation protection in daily nuclear medicine practice. This article reviews important principles of radiation protection in nuclear medicine procedures. Useful references, important issues, future perspectives of the optimization of nuclear medicine procedures, and diagnostic reference level are also discussed.

Nuclear safety and radiation protection report of the Tricastin nuclear facility (BCOT) - 2011

International Nuclear Information System (INIS)

2012-01-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the Tricastin operational hot base facility (INB no. 157, Bollene, Vaucluse (FR)), a nuclear workshop for storage and maintenance and qualification operations on some EdF equipments. Then, the nuclear safety and radiation protection measures taken regarding the facility are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2011, if some, are reported as well as the effluents discharge in the environment. Finally, the management of the radioactive materials and wastes generated by the facility is presented and sorted by type of waste, quantities and type of conditioning. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Regulation on the transport of nuclear fuel materials by vehicles

International Nuclear Information System (INIS)

1984-01-01

The regulations applying to the transport of nuclear fuel materials by vehicles, mentioned in the law for the regulations of nuclear source materials, nuclear fuel materials and reactors. The transport is for outside of the factories and the site of enterprises by such modes of transport as rail, trucks, etc. Covered are the following: definitions of terms, places of fuel materials handling, loading methods, limitations on mix loading with other cargo, radiation dose rates concerning the containers and the vehicles, transport indexes, signs and indications, limitations on train linkage during transport by rail, security guards, transport of empty containers, etc. together with ordinary rail cargo and so on. (Mori, K.)

Nuclear safety and radiation protection report of the Chooz nuclear facilities - 2011

International Nuclear Information System (INIS)

2012-01-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Chooz nuclear power plant (Ardennes (FR)): 2 PWR reactors in operation (Chooz B, INB 139 and 144) and one partially dismantled PWR reactor (Chooz A, INB 163). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2011, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary followed by the viewpoint of the Committees for health, safety and working conditions. (J.S.)

Nuclear safety and radiation protection report of the Paluel nuclear facilities - 2010

International Nuclear Information System (INIS)

2011-01-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Paluel nuclear power plant (INB no. 103 - Paluel 1, no. 104 - Paluel 2, no. 114 - Paluel 3 and no. 115 - Paluel 4, Cany-Barville - Seine-Maritime (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document ends with a glossary and no recommendation from the Committees for health, safety and working conditions. (J.S.)

Nuclear safety and radiation protection report of the Paluel nuclear facilities - 2011

International Nuclear Information System (INIS)

2012-01-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Paluel nuclear power plant (INB no. 103 - Paluel 1, no. 104 - Paluel 2, no. 114 - Paluel 3 and no. 115 - Paluel 4, Cany-Barville - Seine-Maritime (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities. The incidents and accidents which occurred in 2011, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Nuclear safety and radiation protection report of the Golfech nuclear facilities - 2011

International Nuclear Information System (INIS)

2012-01-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Golfech nuclear power plant (INB 135 and 142, Tarn-et-Garonne (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2011, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Nuclear safety and radiation protection report of the Cattenom nuclear facilities - 2011

International Nuclear Information System (INIS)

2012-01-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Cattenom nuclear power plant (INB 124, 125, 126 and 137, Moselle (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2011, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Nuclear safety and radiation protection report of the Cattenom nuclear facilities - 2010

International Nuclear Information System (INIS)

2011-06-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Cattenom nuclear power plant (INB 124, 125, 126 and 137, Moselle (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Nuclear safety and radiation protection report of the Golfech nuclear facilities - 2010

International Nuclear Information System (INIS)

2011-06-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Golfech nuclear power plant (INB 135 and 142, Tarn-et-Garonne (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Radiation processing program at the Malaysian Nuclear Agency

International Nuclear Information System (INIS)

Khairul Zaman

2007-01-01

Radiation processing technology has been proven to enhance industrial efficiency and productivity, improve product quality and competitiveness. For many years, variety of radiation crosslinkable materials based on synthetic polymers have been studied at the Malaysian Nuclear Agency either in the form of thermoplastic resins, polymer blends or composites. At present, effort is focused towards developing new materials based on natural polymers such as natural rubber and rubber based products, palm oil and palm oil based products and polysaccharide. In this respect, the most challenging issues are to develop new materials/products that have commercial value and to bring the products from laboratory to market. (author)

Evaluation of radiation-shielding properties of the composite material

International Nuclear Information System (INIS)

Pavlenko, V.I.; Chekashina, N.I.; Yastrebinskij, R.N.; Sokolenko, I.V.; Noskov, A.V.

2016-01-01

The paper presents the evaluation of radiation-shielding properties of composite materials with respect to gamma-radiation. As a binder for the synthesis of radiation-shielding composites we used lead boronsilicate glass matrix. As filler we used nanotubular chrysotile filled with lead tungstate PbWO4. It is shown that all the developed composites have good physical-mechanical characteristics, such as compressive strength, thermal stability and can be used as structural materials. On the basis of theoretical calculation we described the graphs of the gamma-quanta linear attenuation coefficient depending on the emitted energy for all investigated composites. We founded high radiation-shielding properties of all the composites on the basis of theoretical and experimental data compared to materials conventionally used in the nuclear industry - iron, concrete, etc

Nuclear energy - Radioprotection - Procedure for radiation protection monitoring in nuclear installations for external exposure to weakly penetrating radiation, especially to beta radiation

International Nuclear Information System (INIS)

2002-01-01

This International Standard specifies a procedure for radiation protection monitoring in nuclear installations for external exposure to weakly penetrating radiation, especially to beta radiation and describes the procedure in radiation protection monitoring for external exposure to weakly penetrating radiation in nuclear installations. This radiation comprises β - radiation, β + radiation and conversion electron radiation as well as photon radiation with energies below 15 keV. This International Standard describes the procedure in radiation protection planning and monitoring as well as the measurement and analysis to be applied. It applies to regular nuclear power plant operation including maintenance, waste handling and decommissioning. The recommendations of this International Standard may also be transferred to other nuclear fields including reprocessing, if the area-specific issues are considered. This International Standard may also be applied to radiation protection at accelerator facilities and in nuclear medicine, biology and research facilities

An Overview of the Regulation of Low Dose Radiation in the Nuclear and Non-nuclear Industries

International Nuclear Information System (INIS)

Menon, Shankar; Valencia, Luis; Teunckens, Lucien

2003-01-01

Now that increasing numbers of nuclear power stations are reaching the end of their commercially useful lives, the management of the large quantities of very low level radioactive material that arises during their decommissioning has become a major subject of discussion, with very significant economic implications. Much of this material can, in an environmentally advantageous manner, be recycled for reuse without radiological restrictions. Much larger quantities--2-3 orders of magnitude larger--of material, radiologically similar to the candidate material for recycling from the nuclear industry, arise in non-nuclear industries like coal, fertilizer, oil and gas, mining, etc. In such industries, naturally occurring radioactivity is artificially concentrated in products, by-products or waste to form TENORM (Technologically Enhanced Naturally Occurring Radioactive Material). It is only in the last decade that the international community has become aware of the prevalence of TENORM, specially the activity levels and quantities arising in so many non-nuclear industries. The first reaction of international organizations seems to have been to propose different standards for the nuclear and non-nuclear industries, with very stringent release criteria for radioactive material from the regulated nuclear industry and up to thirty to a hundred times more liberal criteria for the release/exemption of TENORM from the as yet unregulated non-nuclear industries. There are significant strategic issues that need to be discussed and resolved. Some examples of these are: - Disposal aspects of long-lived nuclides, - The use of radioactive residues in building materials, - Commercial aspects of differing and discriminating criteria in competing power industries in a world of deregulated electric power production. Of even greater importance is the need for the discussion of certain basic issues, such as - The quantitative risk levels of exposure to ionizing radiation, - The need for in

Nuclear materials

International Nuclear Information System (INIS)

1996-01-01

In 1998, Nuclear Regulatory Authority of the Slovak Republic (NRA SR) performed 38 inspections, 25 of them were performed in co-operation with IAEA inspectors. There is no fresh nuclear fuel at Bohunice A-1 NPP at present. Fresh fuel of Bohunice V-1 and V-2 NPPs is inspected in the fresh fuel storage.There are 327 fresh fuel assemblies in Mochovce NPP fresh fuel storage. In addition to that, are also 71 small users of nuclear materials in Slovakia. In most cases they use: covers made of depleted uranium for non-destructive works, detection of level in production plants, covers for therapeutical sources at medical facilities. In. 1995, NRA SR issued 4 new licences for nuclear material withdrawal. In the next part manipulation with nuclear materials, spent fuel stores and illegal trafficking in nuclear materials are reported

Radiation damage in nuclear waste ceramics

International Nuclear Information System (INIS)

Turcotte, R.P.; Roberts, F.P.; Rusin, J.M.; Wald, J.W.

1982-01-01

The text contains a number of specific observations about the radiation-induced changes in glass, glass-ceramic, and supercalcine nuclear waste forms. Other, more general conclusions can be summarized: Radiation-induced property changes follow an exponential ingrowth curve to saturation. Actinide host phases in both crystalline waste forms become X-ray amorphous. The magnitudes of the waste-form density changes observed could not be directly related to observed changes in the primary actinide phases. Although large crystal-structure changes occur in the materials studied, obvious physical degradation was not observed

Radiation doses and cause-specific mortality among workers at a nuclear materials fabrication plant

International Nuclear Information System (INIS)

Checkoway, H.; Pearce, N.; Crawford-Brown, D.J.; Cragle, D.L.

1988-01-01

A historical cohort mortality study was conducted among 6781 white male employees from a nuclear weapons materials fabrication plant for the years 1947-1979. Exposures of greatest concern are alpha and gamma radiation emanating primarily from insoluble uranium compounds. Among monitored workers, the mean cumulative alpha radiation dose to the lung was 8.21 rem, and the mean cumulative external whole body penetrating dose from gamma radiation was 0.96 rem. Relative to US white males, the cohort experienced mortality deficits from all causes combined, cardiovascular diseases, and from most site-specific cancers. Mortality excesses of lung and brain and central nervous system cancers were seen from comparisons with national and state rates. Dose-response trends were detected for lung cancer mortality with respect to cumulative alpha and gamma radiation, with the most pronounced trend occurring for gamma radiation among workers who received greater than or equal to 5 rem of alpha radiation. These trends diminished in magnitude when a 10-year latency assumption was applied. Under a zero-year latency assumption, the rate ratio for lung cancer mortality associated with joint exposure of greater than or equal to 5 versus less than 1 rem of both types of radiation is 4.60 (95% confidence limits (CL) 0.91, 23.35), while the corresponding result, assuming a 10-year latency, is 3.05 (95% CL 0.37, 24.83). While these rate ratios, which are based on three and one death, respectively, lack statistical precision, the observed dose-response trends indicate potential carcinogenic effects to the lung of relatively low-dose radiation. There are no dose-response trends for mortality from brain and central nervous system cancers

Nuclear safety and radiation protection report of the nuclear facility of Brennilis - 2011

International Nuclear Information System (INIS)

2012-01-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the partially dismantled facilities of the Monts d'Arree (EL4-D or Brennilis) site (INB 162 (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2011, are reported as well as the radioactive effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Nuclear safety and radiation protection report of the nuclear facilities of Brennilis - 2010

International Nuclear Information System (INIS)

2011-06-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the partially dismantled facilities of the Monts d'Arree (EL4-D or Brennilis) site (INB 162 (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

ASN report on the status of nuclear safety and radiation protection in France in 2011

International Nuclear Information System (INIS)

2012-01-01

The first part of this huge report proposes a detailed overview of ASN activities in different fields: ionizing radiations related to nuclear activities and risks for health and the environment, principles and actors of nuclear safety control, of radiation protection and of protection of the environment, regulation, control of nuclear activities and exposures to ionizing radiations, emergency situations, public information and transparency, international relationships, regional overview of nuclear safety and radiation protection. The second part addresses the activities controlled by the ASN: medical use of ionizing radiations, non medical use of ionizing radiations, transport of radioactive materials, electronuclear power stations, facilities involved in the nuclear fuel cycle, research facilities and other nuclear installations, the safety of dismantling of nuclear base installations, radioactive wastes and polluted sites and soils

Control and Management of Small Quantity Nuclear Material (SQNM) on Safeguards

International Nuclear Information System (INIS)

Park, Jae Hwan; Shin, Byung Woo; Park, Jae Beom

2009-01-01

Small Quantity Nuclear Material (SQNM) is defined as the nuclear material that is below the amount approved in atomic energy act. SQNM generally lists depleted uranium (DU) used as a catalyst or shielding material in exposure devices in industries. The SQNM users have a duty to report information on possessing and using SQNM regularly to the government. All nuclear materials must be included in IAEA reporting lists according to safeguards agreement and additional protocol regardless of amount. However, it is difficult to investigate the status of nuclear material possessed in industries because SQNM is excepted regulation item list in atomic energy act. Most SQNM user industries are small companies so they have some problems like the loss of nuclear material after bankruptcy. Even though the damage of radiation leakage is very low, loss or careless management of nuclear material causes confusion. Thus, developing a control and management system for SQNM is essential. This paper discusses the present condition and prospect of control and management SQNM in Korea

Country Presentation on Illicit Trafficking of Nuclear Materials

International Nuclear Information System (INIS)

Mwandime, C.

2010-01-01

Assess the role of various agences in Kenya in fighting illicit traficking of nuclear materials. These includes the police, customs, National Council for Science and Technology, Radiation and Protection Board. Gives incidences of trafficking of various materials in Kenya and related activities like the 1998 terrorist attack of American Embassy in Nairobi and the Kikambala Tourist Hotel in Mombasa

Light-refractory radiation shielding materials using diatomites and zeolites

International Nuclear Information System (INIS)

Murakami, Hideki

2005-01-01

It has been recently shown that diatomites and zeolites have some useful characteristics for radiation shielding materials. In this study, the availability of these materials for unexpected accidents in the nuclear sites is examined. The diatomites and zeolites, compared to existing shielding materials, have superior characteristics; low density and light weight, low in radiation-induced problem, high-heat resistance, remain unaltered by the addition of an acid except hydrofluoric acid, porous and large specific surface area, and also excellent water-absorbing property. These porous materials could also expand the shielding energy range applied and be used for fast- and thermal-neutrons, and γ ray. In addition, these materials are easy to store for long periods of time against emergency because of their natural rocks. From the examinations, it is cleared that diatomites and zeolites have excellent properties as radiation shielding materials for emergency use. (author)

Reality of dielectric materials in special environment with radiation and others

International Nuclear Information System (INIS)

1993-01-01

In this report, the results of investigation by the expert committee on the title problem in the Institute of Electrical Engineers of Japan from April, 1989 to March, 1992 are summarized. The objectives were to collect the data on the deterioration of dielectric and insulation materials in the special environment including radiation, to investigate the deterioration mechanism, and to grasp the state of development of the materials which can withstand special environment. The actual conditions of temperature, humidity and radiation in nuclear reactors, nuclear fuel cycle facilities, spaceships, accelerator facilities and nuclear fusion experiment facilities are reported. As the new materials which can withstand special environment, the properties of aromatic engineering plastics such as polyimide, PEEK and others, no-halogen incombustible materials, thermoplastic polyurethane, ethylene propylene rubber, cross-linked polyethylene, ceramics, high temperature superconductors, fiber-reinforced composite materials, silica glass and quartz optical fibers are shown. The factors of material deterioration, the method of forecasting lifetime and the examples are explained. The new methods of measuring material properties such as ion microprobe, positron annihilation, scanning tunnel microscopes, optical detection magnetic resonance and so on are explained. (K.I.)

Radiation effects on two-dimensional materials

Energy Technology Data Exchange (ETDEWEB)

Walker, R.C. II; Robinson, J.A. [Department of Materials Science, Penn State, University Park, PA (United States); Center for Two-Dimensional Layered Materials, Penn State, University Park, PA (United States); Shi, T. [Department of Mechanical and Nuclear Engineering, Penn State, University Park, PA (United States); Department of Nuclear Engineering and Radiological Sciences, University of Michigan, Ann Arbor, MI (United States); Silva, E.C. [GlobalFoundries, Malta, NY (United States); Jovanovic, I. [Department of Nuclear Engineering and Radiological Sciences, University of Michigan, Ann Arbor, MI (United States)

2016-12-15

The effects of electromagnetic and particle irradiation on two-dimensional materials (2DMs) are discussed in this review. Radiation creates defects that impact the structure and electronic performance of materials. Determining the impact of these defects is important for developing 2DM-based devices for use in high-radiation environments, such as space or nuclear reactors. As such, most experimental studies have been focused on determining total ionizing dose damage to 2DMs and devices. Total dose experiments using X-rays, gamma rays, electrons, protons, and heavy ions are summarized in this review. We briefly discuss the possibility of investigating single event effects in 2DMs based on initial ion beam irradiation experiments and the development of 2DM-based integrated circuits. Additionally, beneficial uses of irradiation such as ion implantation to dope materials or electron-beam and helium-beam etching to shape materials have begun to be used on 2DMs and are reviewed as well. For non-ionizing radiation, such as low-energy photons, we review the literature on 2DM-based photo-detection from terahertz to UV. The majority of photo-detecting devices operate in the visible and UV range, and for this reason they are the focus of this review. However, we review the progress in developing 2DMs for detecting infrared and terahertz radiation. (copyright 2016 WILEY-VCH Verlag GmbH and Co. KGaA, Weinheim)

Nuclear safety and radiation protection report of Blayais nuclear facilities - 2012

International Nuclear Information System (INIS)

2013-01-01

This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 86 and 110). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2012, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix. (J.S.)

Nuclear safety and radiation protection report of Civaux nuclear facilities - 2012

International Nuclear Information System (INIS)

2013-01-01

This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 158 and 159). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2012, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix. (J.S.)

Nuclear safety and radiation protection report of Golfech nuclear facilities - 2012

International Nuclear Information System (INIS)

2013-01-01

This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 135 and 142). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2012, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix. (J.S.)

Nuclear safety and radiation protection report of Tricastin nuclear facilities - 2012

International Nuclear Information System (INIS)

2013-01-01

This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the Tricastin NPPs (INBs no. 87 and 88). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2012, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix. (J.S.)

Nuclear safety and radiation protection report of Penly nuclear facilities - 2012

International Nuclear Information System (INIS)

2013-01-01

This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 136 and 140). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2012, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix. (J.S.)

Nuclear safety and radiation protection report of Cattenom nuclear facilities - 2012

International Nuclear Information System (INIS)

2013-01-01

This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 124, 125, 126 and 137). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2012, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix. (J.S.)

Nuclear safety and radiation protection report of Chooz nuclear facilities - 2012

International Nuclear Information System (INIS)

2013-01-01

This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 139, 144 and 163 (under dismantling)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2012, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix. (J.S.)

Nuclear safety and radiation protection report of Flamanville nuclear facilities - 2012

International Nuclear Information System (INIS)

2013-01-01

This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 108, 109 and 167 (under construction)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2012, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix. (J.S.)

Nuclear safety and radiation protection report of Fessenheim nuclear facilities - 2012

International Nuclear Information System (INIS)

2013-01-01

This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INB no. 75). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2012, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix. (J.S.)

Development of advanced materials and devices for nuclear radiation measurements

International Nuclear Information System (INIS)

Gadkari, S.C.

2015-01-01

Single crystals of technologically important materials are grown in the Crystal Technology Section of the Technical Physics Division, BARC. These crystals find applications as scintillators and dosimeters in nuclear radiation detection/measurements. Scintillator crystals of some advanced materials like cerium doped Gd 3 Ga 3 Al 2 O 12 , Lu 2 SiO 5 , YAIO 3 etc and some conventional materials such as Bi 4 Ge 3 O 12 , CsI:Tl, NaI:Tl, etc have been grown from melts using the Czochralski and Bridgman techniques. Portable gamma-ray spectrometers that work from a USB port of a laptop have been developed using the grown scintillator crystals. In recent years there has been a flurry of research activities on materials containing Li 6 , B 10 , etc that have large capture cross-sections for neutrons to develop solid state detectors for neutrons. For this purpose single crystals of cerium doped Li 6 Y(BO 3 ) 3 and silver doped Li 2 B 4 O 7 have been developed. Optical, thermo-luminescence, photo-luminescence and scintillation properties of these crystals have been investigated with a view to develop detectors and dosimeters. The Li 2 B 4 O 7 :Ag is a tissue equivalent material (Z eff = 7.3 close to 7.4 of tissue) useful in the personal and medical dosimetry applications. As the emission of Ag + lies in the UV region (267 nm), a customized TL measurement set-up has been developed using a solar blind PMT that enabled the measurement of very low doses below 5 μGy and linearity up to 100 Gy. Films of CsI:TI in the 10 nm to 3 μm thickness range were deposited on silicon substrates using the physical vapor deposition technique under vacuum conditions. The deposited films investigated using SEM and AFM revealed a columnar growth behavior with a preferential orientation along <200>. The growth of single crystals from melts, recent efforts in the development of detectors and results of experiments conducted to detect thermal neutrons are described. (author)

Nuclear and radiation studies and environmental concerns

International Nuclear Information System (INIS)

McEwan, A.C.

1998-01-01

Over the three days 22-24 September 1998 a Science Forum was convened under the general heading of 'Nuclear technology in relation to water resources and the aquatic environment' at the International Atomic Energy Agency, Vienna. Some points of interest, or points of more particular relevance to radiation protection, are noted from the five sessions of the Forum: Session 1: water resources; Session 2: sea transport of radioactive and nuclear materials; Session 3: monitoring radioactivity in the aquatic environment; Session 4: nuclear technology in relation to waste resources and the aquatic environment, Session 5: impact assessment. (author)

Radiation shielding properties of a novel cement–basalt mixture for nuclear energy applications

Energy Technology Data Exchange (ETDEWEB)

Ipbüker, Cagatay; Nulk, Helena; Gulik, Volodymyr [University of Tartu, Institute of Physics (Estonia); Biland, Alex [HHK Technologies, Houston (United States); Tkaczyk, Alan Henry, E-mail: alan@ut.ee [University of Tartu, Institute of Physics (Estonia)

2015-04-01

Highlights: • Basalt fiber is a relatively cheap material that can be used as reinforcement. • Gamma-ray attenuation remains relatively stable with addition of basalt fiber. • Neutron attenuation remains relatively stable with addition of basalt fiber. • Cement–basalt mixture has a good potential for use in nuclear energy applications. - Abstract: The radiation shielding properties of a new proposed building material, a novel cement–basalt fiber mixture (CBM), are investigated. The authors analyze the possibility of this material to be a viable substitute to outgoing materials in nuclear energy applications, which will lead to a further sustained development of nuclear energy in the future. This computational study involves four types of concrete with various amounts of basalt fiber in them. The gamma-ray shielding characteristics of proposed CBM material are investigated with the help of WinXCom program, whereas the neutron shielding characteristics are computed by the Serpent code. For gamma-ray shielding, we find that the attenuation coefficients of concretes with basalt fibers are not notably influenced by the addition of fibers. For neutron shielding, additional basalt fiber in mixture presents negligible effect on neutron radiation shielding. With respect to radiation shielding, it can be concluded that basalt fibers have good potential as an addition to heavyweight concrete for nuclear energy applications.

Radiation shielding properties of a novel cement–basalt mixture for nuclear energy applications

International Nuclear Information System (INIS)

Ipbüker, Cagatay; Nulk, Helena; Gulik, Volodymyr; Biland, Alex; Tkaczyk, Alan Henry

2015-01-01

Highlights: • Basalt fiber is a relatively cheap material that can be used as reinforcement. • Gamma-ray attenuation remains relatively stable with addition of basalt fiber. • Neutron attenuation remains relatively stable with addition of basalt fiber. • Cement–basalt mixture has a good potential for use in nuclear energy applications. - Abstract: The radiation shielding properties of a new proposed building material, a novel cement–basalt fiber mixture (CBM), are investigated. The authors analyze the possibility of this material to be a viable substitute to outgoing materials in nuclear energy applications, which will lead to a further sustained development of nuclear energy in the future. This computational study involves four types of concrete with various amounts of basalt fiber in them. The gamma-ray shielding characteristics of proposed CBM material are investigated with the help of WinXCom program, whereas the neutron shielding characteristics are computed by the Serpent code. For gamma-ray shielding, we find that the attenuation coefficients of concretes with basalt fibers are not notably influenced by the addition of fibers. For neutron shielding, additional basalt fiber in mixture presents negligible effect on neutron radiation shielding. With respect to radiation shielding, it can be concluded that basalt fibers have good potential as an addition to heavyweight concrete for nuclear energy applications

Comprehensive nuclear materials

CERN Document Server

Allen, Todd; Stoller, Roger; Yamanaka, Shinsuke

2012-01-01

Comprehensive Nuclear Materials encapsulates a panorama of fundamental information on the vast variety of materials employed in the broad field of nuclear technology. The work addresses, in five volumes, 3,400 pages and over 120 chapter-length articles, the full panorama of historical and contemporary international research in nuclear materials, from Actinides to Zirconium alloys, from the worlds' leading scientists and engineers. It synthesizes the most pertinent research to support the selection, assessment, validation and engineering of materials in extreme nuclear environments. The work discusses the major classes of materials suitable for usage in nuclear fission, fusion reactors and high power accelerators, and for diverse functions in fuels, cladding, moderator and control materials, structural, functional, and waste materials.

New technologies for monitoring nuclear materials

International Nuclear Information System (INIS)

Moran, B.W.

1993-01-01

This paper describes new technologies for monitoring the continued presence of nuclear materials that are being evaluated in Oak Ridge, Tennessee, to reduce the effort, cost, and employee exposures associated with conducting nuclear material inventories. These technologies also show promise for the international safeguarding of process systems and nuclear materials in storage, including spent fuels. The identified systems are based on innovative technologies that were not developed for safeguards applications. These advanced technologies include passive and active sensor systems based on optical materials, inexpensive solid-state radiation detectors, dimensional surface characterization, and digital color imagery. The passive sensor systems use specialized scintillator materials coupled to optical-fiber technologies that not only are capable of measuring radioactive emissions but also are capable of measuring or monitoring pressure, weight, temperature, and source location. Small, durable solid-state gamma-ray detection devices, whose components are estimated to cost less than $25 per unit, can be implemented in a variety of configurations and can be adapted to enhance existing monitoring systems. Variations in detector design have produced significantly different system capabilities. Dimensional surface characterization and digital color imaging are applications of developed technologies that are capable of motion detection, item surveillance, and unique identification of items

Post-graduate course on radiation protection and nuclear safety. Vol. 1,2

International Nuclear Information System (INIS)

1998-01-01

The course handbook on radiation protection and nuclear safety containing two parts some was prepared mainly by scientists of the Nuclear Regulatory Authority (ARN) of the Argentine Republic, under the auspices of the International Atomic Energy Agency. The contents o this handbook have the principals aspects: radiation detection, radio dosimetry, biological effects of the ionizing radiation, occupational exposure, environmental effects, contamination and decontamination, radioactive waste management, transport of radioactive materials, medical and industrial applications and the Argentine regulatory system

Nuclear safety and radiation protection report of the Tricastin operational hot base nuclear facilities - 2013

International Nuclear Information System (INIS)

2014-01-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the Tricastin operational hot base facility (INB no. 157, Bollene, Vaucluse (FR)), a nuclear workshop for storage and maintenance and qualification operations on some EdF equipments. Then, the nuclear safety and radiation protection measures taken regarding the facility are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2013, if some, are reported as well as the effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facility is presented and sorted by type of waste, quantities and type of conditioning. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions

Effect of radiation resistance additives for insulation materials

International Nuclear Information System (INIS)

Yamamoto, Yasuaki; Yagyu, Hideki; Seguchi, Tadao.

1988-01-01

For the electric wires and cables used in radiation environment such as nuclear power stations and fuel reprocessing facilities, the properties of excellent radiation resistance are required. For these insulators and sheath materials, ethylene propylene rubber, polyethylene and other polymers have been used, but it cannot be said that they always have good radiation resistance. However, it has been well known that radiation resistance can be improved with small amount of additives, and heat resistance and burning retarding property as well as radiation resistance are given to the insulators of wires and cables for nuclear facilities by mixing various additives. In this research, the measuring method for quantitatively determining the effect of Anti-rad (radiation resistant additive) was examined. Through the measurement of gel fraction, radical formation and decomposed gas generation, the effect of Anti-rad protecting polymers from radiation deterioration was examined from the viewpoint of chemical reaction. The experimental method and the results are reported. The radiation energy for cutting C-H coupling is polymers is dispersed by Anti-rad, and the probability of cutting is lowered. Anti-rad catches and extinguishes radicals that start oxidation reaction. (K.I.)

Radiation doses from the transport of radioactive materials

International Nuclear Information System (INIS)

Shaw, K.B.; Holyoak, B.

1983-01-01

A summary is given of a study on radiation exposure resulting from the transport of radioactive materials within the United Kingdom. It was concluded that the transport of technetium generators for hospital use accounts for about 49% of the occupational exposure for the normal transport of radioactive materials. Other isotopes for medical and industrial use contribute about 38% of the occupational exposure and the remainder can be attributed to transportation as a result of the nuclear fuel cycle including the transport of irradiated nuclear fuel. The occupational collective dose for all modes of transport is estimated at 1 man Sv y -1 . (UK)

Damage-Tolerant, Lightweight, High-Temperature Radiator for Nuclear Powered Spacecraft

Data.gov (United States)

National Aeronautics and Space Administration — Game-changing propulsion systems are often enabled by novel designs using advanced materials. Radiator performance dictates power output for nuclear electric...

The regulations concerning the uses of nuclear fuel materials

International Nuclear Information System (INIS)

1978-01-01

The Regulations are established on the basis of ''The law for the regulations of nuclear source materials, nuclear fuel materials and reactors'' and the ''Provisions concerning the usage of nuclear fuel materials'' in the Enforcement Ordinance of the Law, to enforce such provisions. Terms are explained, such as exposure radiation dose, cumulative dose, control area, surrounding inspection area, persons engaging in works, area for incoming and outgoing of materials, batch, real stocks, effective value and main measuring points. In the applications for the permission to use nuclear fuel materials, the expected period and quantity of usage of each kind of such materials and the other party and the method of selling, lending and returning spent fuel or the process of disposal of such fuel must be written. Explanations concerning the technical ability required for the usage of nuclear fuel materials shall be attached to the applications. Applications shall be filed for the inspection of facilities for use, in which the name and the address of the applicant, the name and the address of the factory or the establishment, the range of the facilities for use, the maximum quantity of nuclear fuel materials to be used or stocked, and the date, the place and the kind of the expected inspection are written. Prescriptions cover the records to be held, safety regulations, the technical standards for usage, the disposal, transport and storage of nuclear fuel materials and the reports to be filed. (Okada, K.)

Corrosion degradation of materials in nuclear reactors and its control

International Nuclear Information System (INIS)

Kain, Vivekanand

2016-01-01

As in every industry, nuclear industry also faces the challenge of corrosion degradation due to the exposure of the materials to the working environment. The aggressiveness of the environment is enhanced by the presence of radiation and high temperature and high-pressure environment. Radiation has influence on both the materials (changes in microstructure and microchemistry) and the aqueous environment (radiolysis producing oxidizing conditions). A survey of all the light water reactors in the world showed that stress corrosion cracking (SCC) and flow accelerated corrosion (FAC) account for more than two third of all the corrosion degradation cases. This paper visits these two forms of corrosion in nuclear power plants and illustrates cases from Indian nuclear power plants. Remedial measures against these two forms of corrosion that are possible to be employed and the actual measures employed in Indian nuclear power plants are discussed. Key features of SCC in different types of nuclear power plants are discussed. Main reasons for irradiation assisted stress corrosion cracking (IASCC) are presented and discussed. The signature patterns of single and dual phase FAC captured from components replaced from Indian nuclear power plants are presented. The development of a correlation between the scallop size and rate of single phase FAC - based on the database developed in Indian nuclear power plants is presented. Based on these two forms of degradation in nuclear reactors, design of materials that would resist these forms of degradation is presented. (author)

Nuclear safety and radiation protection report of the basic nuclear facilities of the Tricastin nuclear power plant - 2010

International Nuclear Information System (INIS)

2011-06-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Tricastin nuclear power plant (INB 87 and 88, Saint-Paul-Trois-Chateaux, Drome (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

International conference on security of material. Measures to prevent, intercept and respond to illicit uses of nuclear material and radioactive sources. Book of extended synopses

International Nuclear Information System (INIS)

2001-10-01

The papers cover the subjects relating to the trafficking of highly enriched nuclear materials, less radioactive, radioactive materials, radiations sources, prevention of crime, capabilities of preventing smuggling, radiation detection devices that are or should be applied on borders. Different aspects of physical protection, security and safety of nuclear materials in a number of countries are discussed. A number of papers are devoted to detectors, and measuring methods

International conference on security of material. Measures to prevent, intercept and respond to illicit uses of nuclear material and radioactive sources. Book of extended synopses

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-10-01

The papers cover the subjects relating to the trafficking of highly enriched nuclear materials, less radioactive, radioactive materials, radiations sources, prevention of crime, capabilities of preventing smuggling, radiation detection devices that are or should be applied on borders. Different aspects of physical protection, security and safety of nuclear materials in a number of countries are discussed. A number of papers are devoted to detectors, and measuring methods.

Actions of radiation protection in the collection of discarded radioactive material

International Nuclear Information System (INIS)

Neri, E.P.M.; Silva, F.C.A. da

2017-01-01

Brazil has approximately 2000 radiative facilities that use radiation sources in their processes and are controlled by The Brazilian Nuclear Energy Commission - CNEN through standards, authorizations and inspections. These radioactive materials, whether in the form of waste or radioactive source, used in medical, industrial, research, etc. are sometimes discarded and found in inappropriate places, such as garbage dumps, industrial waste, streets, squares, etc. found by urban cleaning professionals without the proper knowledge of them. The work presents the radiation protection actions required for the safe collection of radioactive material to be performed by these professionals. According to the type of radioactive material the main actions of radiation protection are, among others: recognition of a radioactive material; correct use of personal protective equipment to contain possible radiation contamination; implementation of an area control etc. In order for the actions of recognition and collection of discarded radioactive material to be effective, there is a need to implement a training program in radiation protection for urban cleaning professionals

Nuclear safety and radiation protection report of the Flamanville nuclear facilities - 2011

International Nuclear Information System (INIS)

2012-01-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Flamanville nuclear power plant (Manche (FR)): 2 PWR reactors in operation (INB 108 and 109), and 1 PWR under construction (Flamanville 3, INB 167). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2011, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, water consumption and waste management at Flamanville 3 construction site) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Nuclear safety and radiation protection report of the Flamanville nuclear facilities - 2010

International Nuclear Information System (INIS)

2011-06-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Flamanville nuclear power plant (Manche (FR)): 2 PWR reactors in operation (INB 108 and 109), and 1 PWR under construction (Flamanville 3, INB 167). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, water consumption and waste management at Flamanville 3 construction site) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Nuclear safety and radiation protection report of the Chooz nuclear facilities - 2010

International Nuclear Information System (INIS)

2011-06-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Chooz nuclear power plant (Ardennes (FR)): 2 PWR reactors in operation (Chooz B, INB 139 and 144) and one partially dismantled PWR reactor (Chooz A, INB 163). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Nuclear safety and radiation protection report of the Cruas-Meysse nuclear facilities - 2011

International Nuclear Information System (INIS)

2012-01-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Cruas-Meysse nuclear power plant (INB 111 and 112, Ardeche (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2011, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Nuclear safety and radiation protection report of the Creys-Malville nuclear facilities - 2012

International Nuclear Information System (INIS)

2013-01-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the partially dismantled facilities of the Creys-Malville nuclear power plant (also known as Superphenix power plant, INB no. 91, Creys-Mepieu - Isere (FR)) and the other fuel and waste storage facilities of the site (INB no. 141). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities. The incidents and accidents which occurred in 2012, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions

Nuclear safety and radiation protection report of the Cruas-Meysse nuclear facilities - 2010

International Nuclear Information System (INIS)

2011-06-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Cruas-Meysse nuclear power plant (INB 111 and 112, Ardeche (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Nuclear safety and radiation protection report of the Creys-Malville nuclear facilities - 2011

International Nuclear Information System (INIS)

2012-01-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the partially dismantled facilities of the Creys-Malville nuclear power plant (also known as Superphenix power plant, INB no. 91, Creys-Mepieu - Isere (FR)) and the other fuel and waste storage facilities of the site (INB no. 141). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities. The incidents and accidents which occurred in 2011, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Nuclear and radiation safety policy

International Nuclear Information System (INIS)

Mikus, T; Strycek, E.

1998-01-01

Slovenske elektrarne (SE) is a producer of electricity and heat, including from nuclear fuel source. The board of SE is ultimately responsible for nuclear and radiation safety matters. In this leaflet main principles of maintaining nuclear and radiation safety of the Company SE are explained

Regulations concerning the transport of nuclear fuel materials outside the works or the enterprise

International Nuclear Information System (INIS)

1981-01-01

This rule is established under the provisions of the law concerning the regulation of nuclear raw materials, nuclear fuel materials and nuclear reactors and the ordinance for its execution, and to enforce the law. Basic terms are defined, such as vehicle transport, simplified transport, nuclear fuel transport goods, exclusive loading, worker, cumulative dose and exposure radiation dose. Nuclear fuel transport goods are classified into types of L, A, BM and BU according to their radioactivities. Radiation dose rate shall not exceed 0.5 milli-rem an hour on the surface of the type L, and 200 milli-rem an hour on the surface of the type A. For the type BM, the rate shall not surpass 1,000 milli-rem an hour at the distance of 1 meter from the surface in the special test conditions. The transport goods of fissile materials must not reach criticality on the way, but also shall conform to the stipulated technical standards. The particular things contaminated by nuclear fuel materials can be transported without specifying as nuclear fuel transport goods, and their radiation dose rate shall not go beyond 0.5 milli-rem an hour on the surface. The transport by special measures, the technical standards of simplified transport and measures to be taken in danger in transit are defined, respectively.(Okada, K.)

Detection of nuclear radiations

International Nuclear Information System (INIS)

Tanarro Sanz, A.

1967-01-01

A summary of the lectures about the ordinary detectors of nuclear radiations explained by the author in the courses of Nuclear Engineering held at the J.E.N. up to the date of publication is given. Those lectures are considered to be a necessary introduction to Nuclear Instrumentation and Applied Electronics to Nuclear Engineering so it has been intended to underline those characteristics of radiation detectors that must be taken in consideration in choosing or designing the electronic equipment associated to them in order to take advantage of each detector possibilities. (Author)

Detection of nuclear radiations

International Nuclear Information System (INIS)

Tanarro Sanz, A.

1959-01-01

A summary of the lectures about the ordinary detectors of nuclear radiations given by the author in the Courses of Introduction to Nuclear Engineering held at the JEN up to the date of publication is given. Those lectures are considered to be a necessary introduction to Nuclear Instrumentation and Applied electronics to Nuclear Engineering so it has been intent to underline those characteristics of radiation detectors that must be taken in consideration in choosing or designing the electronic equipment associated to them in order to take advantage of each detector possibilities. (Author) 8 refs

Fieldable Nuclear Material Identification System

International Nuclear Information System (INIS)

Radle, James E.; Archer, Daniel E.; Carter, Robert J.; Mullens, James Allen; Mihalczo, John T.; Britton, Charles L. Jr.; Lind, Randall F.; Wright, Michael C.

2010-01-01

The Fieldable Nuclear Material Identification System (FNMIS), funded by the NA-241 Office of Dismantlement and Transparency, provides information to determine the material attributes and identity of heavily shielded nuclear objects. This information will provide future treaty participants with verifiable information required by the treaty regime. The neutron interrogation technology uses a combination of information from induced fission neutron radiation and transmitted neutron imaging information to provide high confidence that the shielded item is consistent with the host's declaration. The combination of material identification information and the shape and configuration of the item are very difficult to spoof. When used at various points in the warhead dismantlement sequence, the information complimented by tags and seals can be used to track subassembly and piece part information as the disassembly occurs. The neutron transmission imaging has been developed during the last seven years and the signature analysis over the last several decades. The FNMIS is the culmination of the effort to put the technology in a usable configuration for potential treaty verification purposes.

Transportation of nuclear materials

International Nuclear Information System (INIS)

Brobst, W.A.

1977-01-01

Twenty years of almost accident-free transport of nuclear materials is pointed to as evidence of a fundamentally correct approach to the problems involved. The increased volume and new technical problems in the future will require extension of these good practices in both regulations and packaging. The general principles of safety in the transport of radioactive materials are discussed first, followed by the transport of spent fuel and of radioactive waste. The security and physical protection of nuclear shipments is then treated. In discussing future problems, the question of public understanding and acceptance is taken first, thereafter transport safeguards and the technical bases for the safety regulations. There is also said to be a need for a new technology for spent fuel casks, while a re-examination of the IAEA transport standards for radiation doses is recommended. The IAEA regulations regarding quality assurance are said to be incomplete, and more information is required on correlations between engineering analysis, scale model testing and full scale crash testing. Transport stresses on contents need to be considered while administrative controls have been neglected. (JIW)

Calibration of radiation monitors at nuclear power plants

International Nuclear Information System (INIS)

Boudreau, L.; Miller, A.D.; Naughton, M.D.

1994-03-01

This work was performed to provide guidance to the utilities in the primary and secondary calibration of the radiation monitoring systems (RMS) installed in nuclear power plants. These systems are installed in nuclear power plants to monitor ongoing processes, identify changing radiation fields, predict and limit personnel radiation exposures and measure and control discharge of radioactive materials to the environment. RMS are checked and calibrated on a continuing basis to ensure their precision and accuracy. This report discusses various approaches towards primary and secondary calibrations of the RMS equipment in light of accepted practices at typical power plants and recent interpretations of regulatory guidance. Detailed calibration techniques and overall system responses, trends, and practices are discussed. Industry, utility, and regulatory sources were contacted to create an overall consensus of the most reasonable approaches to optimizing the performance of this equipment

Robot development for nuclear material processing

International Nuclear Information System (INIS)

Pedrotti, L.R.; Armantrout, G.A.; Allen, D.C.; Sievers, R.H. Sr.

1991-07-01

The Department of Energy is seeking to modernize its special nuclear material (SNM) production facilities and concurrently reduce radiation exposures and process and incidental radioactive waste generated. As part of this program, Lawrence Livermore National Laboratory (LLNL) lead team is developing and adapting generic and specific applications of commercial robotic technologies to SNM pyrochemical processing and other operations. A working gantry robot within a sealed processing glove box and a telerobot control test bed are manifestations of this effort. This paper describes the development challenges and progress in adapting processing, robotic, and nuclear safety technologies to the application. 3 figs

Radiations effects on polymeric materials used in CERN particles accelerators

International Nuclear Information System (INIS)

Tavlet, M.

1997-01-01

For fundamental research on the basis structure of matter, the European Organization for Nuclear Research (CERN) operates several high-energy particle accelerators around which materials and components are exposed to ionizing radiation. To ensure a safe and reliable operation, the radiation behaviour of most of the components is systematically tested prior to their selection. The long-term radiation-test programme allows to assess the component lifetime in the environment or our accelerators where the absorbed doses are continuously recorded. This article presents organic materials in use at CERN, and some recent results are given on their behaviour under irradiation. (authors)

Decommissioning and material recycling. Radiation risk management issues

International Nuclear Information System (INIS)

Dodd, D.H.

1996-09-01

Once nuclear fuel cycle facilities have permanently stopped operations they have to be decommissioned. The decommissioning of a nuclear facility involves the surveillance and dismantling of the facility systems and buildings, the management of the materials resulting from the dismantling activities and the release of the site for further use. The management of radiation risks associated with these activities plays an important role in the decommissioning process. Existing legislation covers many aspects of the decommissioning process. However, in most countries with nuclear power programmes legislation with respect to decommissioning is incomplete. In particular this is true in the Netherlands, where government policy with respect to decommissioning is still in development. Therefore a study was performed to obtain an overview of the radiation risk management issues associated with decommissioning and the status of the relevant legislation. This report describes the results of that study. It is concluded that future work at the Netherlands Energy Research Foundation on decommissioning and radiation risk management issues should concentrate on surveillance and dismantling activities and on criteria for site release. (orig.)

A Statistical Model for Generating a Population of Unclassified Objects and Radiation Signatures Spanning Nuclear Threats

International Nuclear Information System (INIS)

Nelson, K.; Sokkappa, P.

2008-01-01

This report describes an approach for generating a simulated population of plausible nuclear threat radiation signatures spanning a range of variability that could be encountered by radiation detection systems. In this approach, we develop a statistical model for generating random instances of smuggled nuclear material. The model is based on physics principles and bounding cases rather than on intelligence information or actual threat device designs. For this initial stage of work, we focus on random models using fissile material and do not address scenarios using non-fissile materials. The model has several uses. It may be used as a component in a radiation detection system performance simulation to generate threat samples for injection studies. It may also be used to generate a threat population to be used for training classification algorithms. In addition, we intend to use this model to generate an unclassified 'benchmark' threat population that can be openly shared with other organizations, including vendors, for use in radiation detection systems performance studies and algorithm development and evaluation activities. We assume that a quantity of fissile material is being smuggled into the country for final assembly and that shielding may have been placed around the fissile material. In terms of radiation signature, a nuclear weapon is basically a quantity of fissile material surrounded by various layers of shielding. Thus, our model of smuggled material is expected to span the space of potential nuclear weapon signatures as well. For computational efficiency, we use a generic 1-dimensional spherical model consisting of a fissile material core surrounded by various layers of shielding. The shielding layers and their configuration are defined such that the model can represent the potential range of attenuation and scattering that might occur. The materials in each layer and the associated parameters are selected from probability distributions that span the

Atomistic Simulations of Small-scale Materials Tests of Nuclear Materials

International Nuclear Information System (INIS)

Shin, Chan Sun; Jin, Hyung Ha; Kwon, Jun Hyun

2012-01-01

Degradation of materials properties under neutron irradiation is one of the key issues affecting the lifetime of nuclear reactors. Evaluating the property changes of materials due to irradiations and understanding the role of microstructural changes on mechanical properties are required for ensuring reliable and safe operation of a nuclear reactor. However, high dose of neuron irradiation capabilities are rather limited and it is difficult to discriminate various factors affecting the property changes of materials. Ion beam irradiation can be used to investigate radiation damage to materials in a controlled way, but has the main limitation of small penetration depth in the length scale of micro meters. Over the past decade, the interest in the investigations of size-dependent mechanical properties has promoted the development of various small-scale materials tests, e.g. nanoindentation and micro/nano-pillar compression tests. Small-scale materials tests can address the issue of the limitation of small penetration depth of ion irradiation. In this paper, we present small-scale materials tests (experiments and simulation) which are applied to study the size and irradiation effects on mechanical properties. We have performed molecular dynamics simulations of nanoindentation and nanopillar compression tests. These atomistic simulations are expected to significantly contribute to the investigation of the fundamental deformation mechanism of small scale irradiated materials

Rattling nucleons: New developments in active interrogation of special nuclear material

International Nuclear Information System (INIS)

Runkle, Robert C.; Chichester, David L.; Thompson, Scott J.

2012-01-01

Active interrogation is a vigorous area of research and development due to its promise of offering detection and characterization capabilities of special nuclear material in environments where passive detection fails. The primary value added by active methods is the capability to penetrate shielding - special nuclear material itself, incidental materials, or intentional shielding - and advocates hope that active interrogation will provide a solution to the problem of detecting shielded uranium, which is at present the greatest obstacle to interdiction efforts. The technique also provides a unique benefit for quantifying nuclear material in high background-radiation environments, an area important for nuclear material safeguards and material accountancy. Progress has been made in the field of active interrogation on several fronts, most notably in the arenas of source development, systems integration, and the integration and exploitation of multiple fission and non-fission signatures. But penetration of interrogating radiation often comes at a cost, not only in terms of finance and dose but also in terms of induced backgrounds, system complexity, and extended measurement times (including set up and acquisition). These costs make the calculus for deciding to implement active interrogation more subtle than may be apparent. The purpose of this review is thus to examine existing interrogation methods, compare and contrast their attributes and limitations, and identify missions where active interrogation may hold the most promise.

Radiation protection in nuclear medicine

International Nuclear Information System (INIS)

Corstens, F.

1989-01-01

Aspects of radiation protection in nuclear medicine and the role of the Dutch Society for Nuclear Medicine in these are discussed. With an effective dose-equivalence of averaged 3 mSv per year per nuclear medical examination and about 200.000 examinations per year in the Netherlands, nuclear medicine contributes only to a small degree to the total averaged radiation dose by medical treating. Nevertheless from the beginning, besides to protection of environment and personnel, much attention has been spent by nuclear physicians to dose reduction with patients. Replacing of relatively long living radionuclides like 131 I by short living radionuclides like 99m Tc is an example. In her education and acknowledgement policy the Dutch Society for Nuclear Medicine spends much attention to aspects of radiation reduction. (author). 3 tabs

Nuclear safety and radiation protection report of the Paluel nuclear facilities - 2014

International Nuclear Information System (INIS)

2015-01-01

This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 103, 104, 114 and 115). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2014, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

Nuclear safety and radiation protection report of the Penly nuclear facilities - 2014

International Nuclear Information System (INIS)

2015-01-01

This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 136 and 140). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2014, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

Nuclear safety and radiation protection report of the Paluel nuclear facilities - 2013

International Nuclear Information System (INIS)

2014-01-01

This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 103, 104, 114 and 115). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2013, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

Nuclear safety and radiation protection report of the Civaux nuclear facilities - 2014

International Nuclear Information System (INIS)

2015-01-01

This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 158 and 159). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2014, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

Nuclear safety and radiation protection report of Cruas-Meysse nuclear facilities - 2012

International Nuclear Information System (INIS)

2013-01-01

This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 111 and 112). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2012, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix. (J.S.)

Nuclear safety and radiation protection report of the Penly nuclear facilities - 2013

International Nuclear Information System (INIS)

2014-01-01

This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 136 and 140). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2013, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

Nuclear safety and radiation protection report of the Fessenheim nuclear facilities - 2014

International Nuclear Information System (INIS)

2015-01-01

This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INB no. 75). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2014, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

Nuclear safety and radiation protection report of the Golfech nuclear facilities - 2014

International Nuclear Information System (INIS)

2015-01-01

This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 135 and 142). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2014, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

Nuclear safety and radiation protection report of the Civaux nuclear facilities - 2013

International Nuclear Information System (INIS)

2014-01-01

This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 158 and 159). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2013, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

Nuclear safety and radiation protection report of the Flamanville nuclear facilities - 2013

International Nuclear Information System (INIS)

2014-01-01

This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 108, 109 and 167 (under construction)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2013, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

Nuclear safety and radiation protection report of the Chooz nuclear facilities - 2014

International Nuclear Information System (INIS)

2015-01-01

This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 139, 144 and 163 (under dismantling)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2014, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

Nuclear safety and radiation protection report of the Cattenom nuclear facilities - 2013

International Nuclear Information System (INIS)

2014-01-01

This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 124, 125, 126 and 137). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2013, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

Nuclear safety and radiation protection report of the Chooz nuclear facilities - 2013

International Nuclear Information System (INIS)

2014-01-01

This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 139, 144 and 163 (under dismantling)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2013, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

Nuclear safety and radiation protection report of the Blayais nuclear facilities - 2013

International Nuclear Information System (INIS)

2014-01-01

This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 86 and 110). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2013, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

Nuclear safety and radiation protection report of the Cattenom nuclear facilities - 2014

International Nuclear Information System (INIS)

2015-01-01

This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 124, 125, 126 and 137). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2014, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

Nuclear safety and radiation protection report of the Flamanville nuclear facilities - 2014

International Nuclear Information System (INIS)

2015-01-01

This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 108, 109 and 167 (under construction)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2014, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

Dynamic nuclear polarization of irradiated target materials

International Nuclear Information System (INIS)

Seely, M.L.

1982-01-01

Polarized nucleon targets used in high energy physics experiments usually employ the method of dynamic nuclear polarization (DNP) to polarize the protons or deuterons in an alcohol. DNP requires the presence of paramagnetic centers, which are customarily provided by a chemical dopant. These chemically doped targets have a relatively low polarizable nucleon content and suffer from loss of polarization when subjected to high doses of ionizing radiation. If the paramagnetic centers formed when the target is irradiated can be used in the DNP process, it becomes possible to produce targets using materials which have a relatively high polarizable nucleon content, but which are not easily doped by chemical means. Furthermore, the polarization of such targets may be much more radiation resistant. Dynamic nuclear polarization in ammonia, deuterated ammonia, ammonium hydroxide, methylamine, borane ammonia, butonal, ethane and lithium borohydride has been studied. These studies were conducted at the Stanford Linear Accelerator Center using the Yale-SLAC polarized target system. Results indicate that the use of ammonia and deuterated ammonia as polarized target materials would make significant increases in polarized target performance possible

Radiation hardened equipment and material data base

International Nuclear Information System (INIS)

Sumita, Kenji; Yamaoka, Hitoshi; Kakuta, Tsunemi; Shono, Yoshihiko; Nakamura, Tetsuo; Nakase, Yoshiaki; Furuta, Junichiro.

1988-01-01

In order to collect and put in order the results regarding radiation-withstanding equipment and materials, the Osaka Nuclear Science Association organized the committee composed of the experts in various fields in fiscal year 1986 for the purpose of building up the data base, and began the activity. From the trend of the research and development and the usefulness for the future, the fields of collecting data were decided as organic materials, optical fibers, semiconductor elements and compound semiconductors. By fiscal year 1987, the building-up of the prototype data base was aimed at, and system configuration, the making of the formats on the items and attributes of collected data, the action test of the system and so on were carried out. Under the background of the upgrading of LWRs, the development of FBRs and nuclear fusion reactors, the construction of a reprocessing plant and a low level waste storage facility, and the progress of various advanced technologies, the research on the equipment and materials having excellent radiation resistance and the development for heightening the performance have been carried out in many places separately, accordingly the activity for building up the prototype data base was begun, and about 600 cases were collected. (Kako, I.)

E-Alerts: Nuclear science and technology (radiation shielding, protection, and safety). E-mail newsletter

International Nuclear Information System (INIS)

1999-01-01

Topics include: Shielding design, nuclear radiation transport properties of materials, decontamination; Container design and transportation requirements for radioactive materials; and Fallout shelters

Development of flame retardant, radiation resistant insulating materials

Energy Technology Data Exchange (ETDEWEB)

Hagiwara, M.

1984-01-01

On the cables used for nuclear power stations, in particular those ranked as IE class, flame retardation test, simulated LOCA environment test, radiation resistance test and so on are imposed. The results of the evaluation of performance by these tests largely depend on the insulating materials mainly made of polymers. Ethylene propylene copolymer rubber has been widely used as cable insulator because of its electrical characteristics, workability, economy and relatively good radiation resistance, but it is combustible, therefore, in the practical use, it is necessary to make it fire resistant. The author et al. have advanced the research on the molecular design of new fire retarding materials, and successfully developed acenaphthylene bromide condensate, which is not only fire resistant but also effective for improving radiation resistance. The condition of flame retardant, radiation resistant auxiliary agents is explained, and there are additive type and reaction type in fire retarding materials. The synthesis of acenaphthylene bromide condensate and its effect of giving flame retardant and radiation resistant properties are reported. The characteristics of the cables insulated with the flame retardant ethylene propylene rubber containing acenaphthylene bromide condensate were tested, and the results are shown. (Kako, I.).

Radiation effects issues related to US DOE site remediation and nuclear waste storage

International Nuclear Information System (INIS)

Weber, W.J.; Ewing, R.C.

1994-10-01

Site restoration activities at DOE facilities and the permanent disposal of nuclear waste generated at the same DOE facilities involve working with and within various types and levels of radiation fields. Radionuclide decay and the associated radiation fields lead to physical and chemical changes that can degrade or enhance material properties. This paper reviews the impact of radiation fields on site restoration activities and on the release rate of radionuclides to the biosphere from nuclear waste forms

Nuclear safety and radiation protection report of the CNPE EDF nuclear facilities of Tricastin - 2011

International Nuclear Information System (INIS)

2012-01-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Tricastin nuclear power plant (INB 87 and 88, Saint-Paul-Trois-Chateaux, Drome (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2011, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Nuclear safety and radiation protection report of the Saint-Alban-Saint-Maurice nuclear facilities - 2011

International Nuclear Information System (INIS)

2012-01-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Saint-Alban-Saint-Maurice nuclear power plant (INB 119 and 120, Isere (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2011, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Nuclear safety and radiation protection report of the Saint-Alban-Saint-Maurice nuclear facilities - 2010

International Nuclear Information System (INIS)

2011-06-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Saint-Alban-Saint-Maurice nuclear power plant (INB 119 and 120, Isere (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Report on the Workshop on Accelerated Nuclear Energy Materials Development

Energy Technology Data Exchange (ETDEWEB)

King, Wayne E. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Allen, Todd [Univ. of Wisconsin, Madison, WI (United States); Arsenlis, Tom [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Bench, Graham [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Bulatov, Vasily [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Fluss, Michael [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Klein, Richard [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); McMahon, Donn [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Middleton, Carolin [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Morley, Maureen [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Pasamehmetoglu, Kemal [Idaho National Lab. (INL), Idaho Falls, ID (United States); Turchi, Patrice [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Was, Gary [Univ. of Michigan, Ann Arbor, MI (United States)

2010-05-11

This document reports on the Office of Nuclear Energy’s (NE’s) Workshop on Accelerated Nuclear Energy Materials Development held May 11, 2010, in Washington, DC. The purpose of the workshop was twofold: (1) to provide feedback on an initiative to use uncertainty quantification (UQ) to integrate theory, simulation, and modeling with accelerated experimentation to predict the behavior of materials and fuels in an irradiation environment and thereby accelerate the lengthy materials design and qualification process; and (2) to provide feedback on and refinement to five topical areas to develop predictive models for fuels and cladding and new radiation-tolerant materials. The goal of the workshop was to gather technical feedback with respect to the Office of Nuclear Energy’s research and development while also identifying and highlighting crosscutting capability and applicability of the initiative to other federal offices, including the Department of Energy’s (DOE’s) National Nuclear Security Administration (NNSA), Nuclear Regulatory Commission (NRC), DOE Office of Basic Energy Sciences (BES), DOE Office of Fusion Energy Sciences (FES), and Naval Reactors. The goals of the initiative are twofold: (1) develop time- and length-scale transcending models that predict material properties using UQ to effectively integrate theory, simulation, and modeling with accelerated experiments; and (2) design and develop new radiation-tolerant materials using the knowledge gained and methodologies created to shorten the development and qualification time and reduce cost. The initiative is crosscutting and has synergy with industry and other federal offices including Naval Reactors, NRC, FES, BES, and the Office of Advanced Scientific Computing Research (ASCR). It is distinguished by its use of uncertainty quantification to effectively integrate theory, simulation, and modeling with high-dose experimental capabilities. The initiative aims to bring the methodology that is being

Radiation protection in nuclear facilities

International Nuclear Information System (INIS)

Piechowski, J.; Lochard, J.; Lefaure, Ch.; Schieber, C.; Schneider, Th; Lecomte, J.F.; Delmont, D.; Boitel, S.; Le Fauconnier, J.P.; Sugier, A; Zerbib, J.C.; Barbey, P.

1998-01-01

Close ties exist between nuclear safety and radiation protection. Nuclear safety is made up of all the arrangements taken to prevent accidents occurring in nuclear facilities, these accidents would certainly involved a radiological aspect. Radiation protection is made up of all the arrangements taken to evaluate and reduce the impact of radiation on workers or population in normal situations or in case of accident. In the fifties the management of radiological hazards was based on the quest for minimal or even zero risk. This formulation could lead to call some activities in question whereas the benefits for the whole society were evident. Now a new attitude more aware of the real risks and of no wasting resources prevails. This attitude is based on the ALARA principle whose purpose is to maintain the exposure to radiation as low as reasonably achievable taking into account social and economic concerns. This document regroups articles illustrating different aspects of the radiation protection in nuclear facilities such as a research center, a waste vitrification workshop and a nuclear power plant. The surveillance of radiological impacts of nuclear sites on environment is examined, a point is made about the pending epidemiologic studies concerning La Hague complex. (A.C.)

Nuclear safety and radiation protection report of the Nogent-sur-Seine nuclear facilities - 2011

International Nuclear Information System (INIS)

2012-01-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Nogent-sur-Seine nuclear power plant (INB 129 and 130, Aube (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2011, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Nuclear safety and radiation protection report of the Dampierre-en-Burly nuclear facilities - 2011

International Nuclear Information System (INIS)

2012-01-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Dampierre-en-Burly nuclear power plant (INB 84 and 85, Loiret, 45 (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2011, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Nuclear safety and radiation protection report of the Dampierre-en-Burly nuclear facilities - 2010

International Nuclear Information System (INIS)

2011-06-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Dampierre-en-Burly nuclear power plant (INB 84 and 85, Loiret, 45 (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Nuclear safety and radiation protection report of the Nogent-sur-Seine nuclear facilities - 2010

International Nuclear Information System (INIS)

2011-06-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Nogent-sur-Seine nuclear power plant (INB 129 and 130, Aube (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Nuclear safety and radiation protection report of the Belleville-sur-Loire nuclear facilities - 2011

International Nuclear Information System (INIS)

2012-01-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Belleville-sur-Loire nuclear power plant (INB no. 127 - Belleville 1 and no. 128 - Belleville 2, Belleville-sur-Loire and Sury-pres-Lere - Cher (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities. The incidents and accidents which occurred in 2011, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Nuclear safety and radiation protection report of the Bugey nuclear facilities - 2010

International Nuclear Information System (INIS)

2011-06-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Bugey nuclear power plant (Ain (FR)): 4 PWR reactors in operation (INB 78 and 89), one partially dismantled graphite-gas reactor (INB 45), an inter-regional fuel storage facility (MIR, INB 102), and a radioactive waste storage and conditioning facility under construction (ICEDA, INB 173). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Detection of nuclear radiations; Deteccion de Radiaciones nucleares

Energy Technology Data Exchange (ETDEWEB)

Tanarro Sanz, A

1967-07-01

A summary of the lectures about the ordinary detectors of nuclear radiations explained by the author in the courses of Nuclear Engineering held at the J.E.N. up to the date of publication is given. Those lectures are considered to be a necessary introduction to Nuclear Instrumentation and Applied Electronics to Nuclear Engineering so it has been intended to underline those characteristics of radiation detectors that must be taken in consideration in choosing or designing the electronic equipment associated to them in order to take advantage of each detector possibilities. (Author)

Detection of nuclear radiations; Detectores de radiaciones nucleares

Energy Technology Data Exchange (ETDEWEB)

Tanarro Sanz, A

1959-07-01

A summary of the lectures about the ordinary detectors of nuclear radiations given by the author in the Courses of Introduction to Nuclear Engineering held at the JEN up to the date of publication is given. Those lectures are considered to be a necessary introduction to Nuclear Instrumentation and Applied electronics to Nuclear Engineering so it has been intent to underline those characteristics of radiation detectors that must be taken in consideration in choosing or designing the electronic equipment associated to them in order to take advantage of each detector possibilities. (Author) 8 refs.

Chambers nuclear energy and radiation dictionary

International Nuclear Information System (INIS)

Walker, P.M.B.

1992-01-01

This Dictionary is designed to make it easier for those who are concerned about nuclear power and radiation to learn more about nuclear energy and to come to an informed opinion. The first two of the 11 chapters which precede the dictionary proper describe the properties of the atomic nucleus which make nuclear energy possible and then the problems which have to be overcome in harnessing this energy. The next two chapters discuss the many different kinds of power stations which rely on fission and then the methods of fusion which may produce power in the next century. There are then two chapters on nuclear safety and on the production and enrichment of uranium fuel, together with methods for its eventual disposal. These are followed by a chapter on nuclear bombs of various kinds and one on how nuclear and other forms of radiation can be detected. There is then a chapter which relates the radiation resulting from nuclear fission to other kinds of radiation. The next chapter discusses some basic biology particularly cancer. Finally, the biological effects of radiation are described before comparing the amounts of man-made radiation to that which comes naturally from outer space and from the rocks beneath us. This then leads to the radiation limits which are determined by the various regulartory authorities and the kinds of evidence upon which their decisions are based. (Author)

Calculations to support design of a nuclear material tracking system

International Nuclear Information System (INIS)

Carter, L.L.; Eggers, R.F.; Williams, T.L.

1991-01-01

The Westinghouse Hanford Company is developing a nuclear material tracking system called NTRAK for the US Department of Energy at the Savannah River site. The NTRAK system is designed to determine the position and approximate magnitude of packages of special nuclear material (SNM) moving through a nuclear plant. The NTRAK accomplishes this by using special assemblies of detectors called modules to measure the gamma radiation emitted by the SNM. After measurement, raw data are processed to determine the direction to and position of the gamma-ray source. In order for the NTRAK method of SNM tracking to work, the gamma-ray signal at the detector modules must be at least four standard deviations above background. This paper addresses the use of the Monte Carlo computer code for neutron and photon transport (MCNP) to (a) predict the radiation emitted by plutonium oxide sources and (b) predict the counting rate of NaI detectors measuring those sources

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)

Device for separating, purifying and recovering nuclear fuel material, impurities and materials from impurity-containing nuclear fuel materials or nuclear fuel containing material

International Nuclear Information System (INIS)

Sato, Ryuichi; Kamei, Yoshinobu; Watanabe, Tsuneo; Tanaka, Shigeru.

1988-01-01

Purpose: To separate, purify and recover nuclear fuel materials, impurities and materials with no formation of liquid wastes. Constitution: Oxidizing atmosphere gases are introduced from both ends of a heating furnace. Vessels containing impurity-containing nuclear fuel substances or nuclear fuel substance-containing material are continuously disposed movably from one end to the other of the heating furnace. Then, impurity oxides or material oxides selectively evaporated from the impurity-containing nuclear fuel substances or nuclear fuel substance-containing materials are entrained in the oxidizing atmosphere gas and the gases are led out externally from a discharge port opened at the intermediate portion of the heating furnace, filters are disposed to the exit to solidify and capture the nuclear fuel substances and traps are disposed behind the filters to solidify and capture the oxides by spontaneous air cooling or water cooling. (Sekiya, K.)

Influence of nuclear radiation and laser beams on optical fibers and components

Directory of Open Access Journals (Sweden)

Pantelić Slađana N.

2011-01-01

Full Text Available The influence of nuclear radiation and particles has been the object of investigation for a long time. For new materials and systems the research should be continued. Human activities in various environments, including space, call for more detailed research. The role of fibers in contemporary communications, medicine, and industry increases. Fibers, their connections and fused optics components have one type of tasks - the transmission of information and power. The other type of tasks is reserved for fiber lasers: quantum generators and amplifiers. The third type of tasks is for fiber sensors, including high energy nuclear physics. In this paper we present some chosen topics in the mentioned areas as well as our experiments with nuclear radiation and laser beams to fiber and bulk materials of various nature (glass, polymer, metallic, etc..

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

Structural materials for Gen-IV nuclear reactors: Challenges and opportunities

Science.gov (United States)

Murty, K. L.; Charit, I.

2008-12-01

Generation-IV reactor design concepts envisioned thus far cater toward a common goal of providing safer, longer lasting, proliferation-resistant and economically viable nuclear power plants. The foremost consideration in the successful development and deployment of Gen-IV reactor systems is the performance and reliability issues involving structural materials for both in-core and out-of-core applications. The structural materials need to endure much higher temperatures, higher neutron doses and extremely corrosive environment, which are beyond the experience of the current nuclear power plants. Materials under active consideration for use in different reactor components include various ferritic/martensitic steels, austenitic stainless steels, nickel-base superalloys, ceramics, composites, etc. This paper presents a summary of various Gen-IV reactor concepts, with emphasis on the structural materials issues depending on the specific application areas. This paper also discusses the challenges involved in using the existing materials under both service and off-normal conditions. Tasks become increasingly complex due to the operation of various fundamental phenomena like radiation-induced segregation, radiation-enhanced diffusion, precipitation, interactions between impurity elements and radiation-produced defects, swelling, helium generation and so forth. Further, high temperature capability (e.g. creep properties) of these materials is a critical, performance-limiting factor. It is demonstrated that novel alloy and microstructural design approaches coupled with new materials processing and fabrication techniques may mitigate the challenges, and the optimum system performance may be achieved under much demanding conditions.

Nuclear safety and radiation protection report of EdF's Tricastin operational hot base nuclear facilities (BCOT) - 2010

International Nuclear Information System (INIS)

2011-06-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the Tricastin operational hot base facility (INB no. 157, Bollene, Vaucluse (FR)), a nuclear workshop for storage and maintenance and qualification operations on some EdF equipments. Then, the nuclear safety and radiation protection measures taken regarding the facility are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, if some, are reported as well as the effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facility is presented and sorted by type of waste, quantities and type of conditioning. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Development of measures to deal with illicit trafficking of nuclear materials in Ghana

International Nuclear Information System (INIS)

Schandorf, C.; Amoako, J.K.; Asiamah, S.D.

2001-01-01

Full text: The world has now become a global village as such no country can isolate itself from global trends. Reported cases of illicit trafficking in nuclear materials have focused international attention on ways to combat an emerging phenomenon of the 1990's. Of the 324 confirmed cases of illicit trafficking nearly 130 involved individuals trying to illegally sell radioactive materials used in medicine or industry whose unauthorized use or movement poses a danger to public health. Some other cases have involved samples of weapons-grade materials confiscated from individuals. These incidents have raised public and governmental concerns. This has prompted stronger efforts to prevent illicit nuclear trafficking by state authorities, including collaboration and co-operation with international organizational such as the IAEA. The IAEA has established the Illicit Trafficking Database Programme and is encouraging all Member States to participate and to report all incidents of illicit trafficking in nuclear materials and other radioactive materials and other radioactive sources that come to their notice. From the data available from the Regulatory Authority Information System (RAIS), Ghana, there are 344 highly enriched uranium fuel elements (998.2g) in use in the 30kW Research Reactor, (GHARR-1) and 80 radioactive materials in use in medicine, history, research and teaching. The reactor has been subjected to safeguards inspections by IAEA on regular basis. Additionally there have been on the average about nine authorized imports of radioactive into the country in the past seven years. Unlawful use of nuclear materials, through criminal or terrorist activities, may pose a proliferation treat, while unlawful use of radiation poses risks to the public. Ghana has therefore decided to established an effective counter measure against illicit trafficking in nuclear and other materials which might pose both proliferation threat as well as radiological risk to the public and

Nuclear radiation sensors and monitoring following a nuclear or radiological emergencies

International Nuclear Information System (INIS)

Bhatnagar, P.K.

2009-01-01

Management of Nuclear and Radiological Emergencies arising from Radiological Dispersive Device (RDD), Improvised Nuclear Devices (IND), Nuclear Reactors/Power plants and Nuclear War require measurement of ionizing radiations and radioactivity on an enhanced scale relative to the levels encountered in peaceful uses of ionizing radiations and radioactivity. It is heartening that since Hiroshima, Nagasaki nuclear disaster, the world has been quiet but since early 2000 there has been a fear of certain devices to be used by terrorists, which could lead to panic, and disaster due to dispersal of radioactivity by RDD, IND. Nuclear attack would lead to blast, thermal, initial nuclear radiation, nuclear fall out leading to gamma and neutron dose, dose rates in range from few R, R/h to kR, kR/h, and determinations of k Bq or higher order. Such situations have been visualized at national levels and National Disaster Management Authority NDMA has been established and Disaster Management Act 2005 has come into existence. NDMA has prepared guidelines for Nuclear and radiological emergency management highlighting preparedness, mitigation, response, capacity building, etc. Critical point in all these issues is detection of emergency, quick intimation to the concerned for action in shortest possible time. Upper most requirement by those involved in pursuing action, is radiation sensor based radiation monitors for personnel, area, and to assess contamination due to radioactivity.This presentation briefly describes the Indian scenario in the development of the radiation sensors and the sensor-based radiation monitors. (author)

Nuclear radiation sensors and monitoring following a nuclear or radiological emergencies

Energy Technology Data Exchange (ETDEWEB)

Bhatnagar, P K [Defence Laboratory, Jodhpur (India)

2009-01-15

Management of Nuclear and Radiological Emergencies arising from Radiological Dispersive Device (RDD), Improvised Nuclear Devices (IND), Nuclear Reactors/Power plants and Nuclear War require measurement of ionizing radiations and radioactivity on an enhanced scale relative to the levels encountered in peaceful uses of ionizing radiations and radioactivity. It is heartening that since Hiroshima, Nagasaki nuclear disaster, the world has been quiet but since early 2000 there has been a fear of certain devices to be used by terrorists, which could lead to panic, and disaster due to dispersal of radioactivity by RDD, IND. Nuclear attack would lead to blast, thermal, initial nuclear radiation, nuclear fall out leading to gamma and neutron dose, dose rates in range from few R, R/h to kR, kR/h, and determinations of k Bq or higher order. Such situations have been visualized at national levels and National Disaster Management Authority NDMA has been established and Disaster Management Act 2005 has come into existence. NDMA has prepared guidelines for Nuclear and radiological emergency management highlighting preparedness, mitigation, response, capacity building, etc. Critical point in all these issues is detection of emergency, quick intimation to the concerned for action in shortest possible time. Upper most requirement by those involved in pursuing action, is radiation sensor based radiation monitors for personnel, area, and to assess contamination due to radioactivity.This presentation briefly describes the Indian scenario in the development of the radiation sensors and the sensor-based radiation monitors. (author)

10 CFR 74.51 - Nuclear material control and accounting for strategic special nuclear material.

Science.gov (United States)

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false Nuclear material control and accounting for strategic special nuclear material. 74.51 Section 74.51 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) MATERIAL CONTROL AND ACCOUNTING OF SPECIAL NUCLEAR MATERIAL Formula Quantities of Strategic Special Nuclear...

Radiation dosimetry for medical management in nuclear/radiological disaster

International Nuclear Information System (INIS)

Narayan, Pradeep

2012-01-01

; quartz, sand, stones and man made materials such as glasses, bricks, tiles and ceramics from the close proximity of exposed individual can be examined using TL techniques for estimating the radiation doses to the public. TL techniques have been employed to these materials after exposing them with gamma radiation and the results have been found promising. The current trends in methodologies and techniques of radiation dosimetry for medical management of nuclear/radiological disaster will be presented. (author)

Verification of the behavior of insulating materials under ionizing radiation

International Nuclear Information System (INIS)

Reis, Joao C. Marques dos; Rezende, Aurimar de P.; Menzel, Silvio C.

2009-01-01

To analyze the behavior of specifics electrical insulating materials and components under ionizing radiation, a test program was developed to verify the overall effects of general electrical equipment under high radiation fields conditions. The main objective is for maintenance purposes, in the substitution of electrical components installed in the reactor building of the Angra 1 nuclear power plant. Knowing the characteristics of electrical insulating materials available in the country and determining by tests their ability to withstand the ionizing radiation effects, is feasible to implement specific maintenance services of electrical equipment, maintaining the same level of quality and safety for the specified application. This procedure reduces the time and also costs of maintenance services, in comparison with materials acquired or services performed abroad. The isolating materials and components of electrical equipment should be specified, manufactured and qualified to withstand aggressive environmental conditions in the reactor building during the normal operation and postulated accident. Additional tests should be conducted to verify the conditions of the aged material by ionizing radiation. Examples of additional tests: dielectric strength, tensile strength and elongation and impact resistance. (author)

The Radiation Safety Information Computational Center (RSICC): A Resource for Nuclear Science Applications

International Nuclear Information System (INIS)

Kirk, Bernadette Lugue

2009-01-01

The Radiation Safety Information Computational Center (RSICC) has been in existence since 1963. RSICC collects, organizes, evaluates and disseminates technical information (software and nuclear data) involving the transport of neutral and charged particle radiation, and shielding and protection from the radiation associated with: nuclear weapons and materials, fission and fusion reactors, outer space, accelerators, medical facilities, and nuclear waste management. RSICC serves over 12,000 scientists and engineers from about 100 countries. An important activity of RSICC is its participation in international efforts on computational and experimental benchmarks. An example is the Shielding Integral Benchmarks Archival Database (SINBAD), which includes shielding benchmarks for fission, fusion and accelerators. RSICC is funded by the United States Department of Energy, Department of Homeland Security and Nuclear Regulatory Commission.

National conference on radiation safety of nuclear power plants and their environmental impacts

International Nuclear Information System (INIS)

Moravek, J.

1989-01-01

The first national conference on radiation safety of nuclear power plants and their environmental impacts was held in Tale (CS), 12 to 15 October, 1987 with the participation of 201 Czechoslovak specialists representing central authorities, research institutes, institutions of higher education, power plants in operation and under construction, water management and hygiene inspection and some production sectors, specialists from Hungary, Poland and the GDR. The participants heard 110 papers. The conference agenda comprised keynote papers presented in plenary session and five specialist sessions: 1. Radiation control of discharges and their surroundings. 2. Monitoring and evaluation of the radiation situation in nuclear power plants. 3. Equipment for monitoring the nuclear power plant and its environs. 4. Mathematical modelling and assessment of the nuclear power plant radiation environmental impact. 5. Evaluation of sources and of the transport of radioactive materials inside the power plant and the minimization of the nuclear power plant's environmental impact. (Z.M.)

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)

Radiation physics for nuclear medicine

CERN Document Server

Hoeschen, Christoph

2011-01-01

The field of nuclear medicine is expanding rapidly, with the development of exciting new diagnostic methods and treatments. This growth is closely associated with significant advances in radiation physics. In this book, acknowledged experts explain the basic principles of radiation physics in relation to nuclear medicine and examine important novel approaches in the field. The first section is devoted to what might be termed the "building blocks" of nuclear medicine, including the mechanisms of interaction between radiation and matter and Monte Carlo codes. In subsequent sections, radiation sources for medical applications, radiopharmaceutical development and production, and radiation detectors are discussed in detail. New frontiers are then explored, including improved algorithms for image reconstruction, biokinetic models, and voxel phantoms for internal dosimetry. Both trainees and experienced practitioners and researchers will find this book to be an invaluable source of up-to-date information.

ASN report of the status of nuclear safety and radiation protection in France in 2012

International Nuclear Information System (INIS)

Chevet, Pierre-Franck; Delmestre, Alain; Bardet, Marie-Christine; Covard, Fabienne; Landrin, Sophie

2013-01-01

After a presentation of the French Nuclear Safety Authority (ASN), its missions, some key figures illustrating its activities and its organisation, this report proposes an overview of marking events and of actions undertaken by the ASN after the Fukushima accident. Then, the report proposes a detailed and commented overview of actions undertaken by the ASN in different fields and domains: nuclear activities, principles and actors of nuclear safety and radiation protection control, regulation, control of nuclear activities and of exposures to ionizing radiations, radiological and post-accidental emergency situations, public information and transparency, international relationships, regional overview of nuclear safety and radiation protection. The last part addresses activities controlled by the ASN: medical use of ionizing radiations, industrial, research and veterinary uses and source safety, transport of radioactive materials, electronuclear plants, installations related to nuclear fuel cycle, nuclear research and other nuclear installations, safety of dismantling of base nuclear installations, radioactive wastes and polluted sites

Nuclear safety and radiation protection report of Belleville-Sur-Loire nuclear facilities - 2012

International Nuclear Information System (INIS)

2013-01-01

This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 127 and 128). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2012, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix. (J.S.)

Nuclear safety and radiation protection report of the Cruas-Meysse nuclear facilities - 2014

International Nuclear Information System (INIS)

2015-01-01

This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 111 and 112). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2014, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

Nuclear safety and radiation protection report of Dampierre-En-Burly nuclear facilities - 2012

International Nuclear Information System (INIS)

2013-01-01

This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 84 and 85). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2012, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix. (J.S.)

Nuclear safety and radiation protection report of Nogent-Sur-Seine nuclear facilities - 2012

International Nuclear Information System (INIS)

2013-01-01

This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 129 and 130). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2012, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix. (J.S.)

Assessment of Radiation Embrittlement in Nuclear Reactor Pressure Vessel Surrogate Materials

Science.gov (United States)

Balzar, Davor

2010-10-01

The radiation-enhanced formation of small (1-2 nm) copper-rich precipitates (CRPs) is critical for the occurrence of embrittlement in nuclear-reactor pressure vessels. Small CRPs are coherent with the bcc matrix, which causes local matrix strain and interaction with the dislocation strain fields, thus impeding dislocation mobility. As CRPs grow, there is a critical size at which a phase transformation occurs, whereby the CRPs are no longer coherent with the matrix, and the strain is relieved. Diffraction-line-broadening analysis (DLBA) and small-angle neutron scattering (SANS) were used to characterize the precipitate formation in surrogate ferritic reactor-pressure vessel steels. The materials were aged for different times at elevated temperature to produce a series of specimens with different degrees of copper precipitation. SANS measurements showed that the precipitate size distribution broadens and shifts toward larger sizes as a function of ageing time. Mechanical hardness showed an increase with ageing time, followed by a decrease, which can be associated with the reduction in the number density as well as the loss of coherency at larger sizes. Inhomogeneous strain correlated with mechanical hardness.

Design of radiation shields in nuclear reactor core

International Nuclear Information System (INIS)

Mousavi Shirazi, A.; Daneshvar, Sh.; Aghanajafi, C.; Jahanfarnia, Gh.; Rahgoshay, M.

2008-01-01

This article consists of designing radiation shields in the core of nuclear reactors to control and restrain the harmful nuclear radiations in the nuclear reactor cores. The radiation shields protect the loss of energy. caused by nuclear radiation in a nuclear reactor core and consequently, they cause to increase the efficiency of the reactor and decrease the risk of being under harmful radiations for the staff. In order to design these shields, by making advantages of the O ppenheim Electrical Network m ethod, the structure of the shields are physically simulated and by obtaining a special algorithm, the amount of optimized energy caused by nuclear radiations, is calculated

Radiation hazards in the nuclear medicine

International Nuclear Information System (INIS)

Roo, M.J.K. de

1981-01-01

After a survey of the actual situation of nuclear medicine in Belgium, the evolution of nuclear medicine is studied with regard to quantitative aspects (tracerquantities, number of radioisotopic explorations, number of certified doctors) and qualitative aspects (use of short living isotopes emitting low energy radiation, introduction of in vitro tests). Taking these data into consideration, the exposure of nuclear medicine staff by external or internal radiation is evaluated. From this study it appears that the radiation exposure of the personnel of nuclear medicine departments remains low if proper manipulation methods and simple protective devices are used and if there is an efficient collaboration with an active health physics department or radiation control organism. (author)

Integrated nuclear and radiation protection systems

International Nuclear Information System (INIS)

Oprea, I.; Oprea, M.; Stoica, V.; Cerga, V.; Pirvu, V.; Badea, E.

1993-01-01

A multifunctional radiation monitoring equipment, flexible and capable to meet virtually environmental radiation monitoring, activity measurement and computational requirements, for nuclear laboratories has been designed. It can be used as a radiation protection system, for radionuclide measurement in isotope laboratories, nuclear technology, health physics and nuclear medicine, nuclear power stations and nuclear industry. The equipment is able to measure, transmit and record gamma dose rate and isotope activities. Other parameters and functions are optionally available, such as: self-contained alarm level, system self-test, dose integrator, syringe volume calculation for a given dose corrected for decay, calibration factor, 99 Mo assays performing and background subtraction

Heavy ion linear accelerator for radiation damage studies of materials

Energy Technology Data Exchange (ETDEWEB)

Kutsaev, Sergey V.; Mustapha, Brahim; Ostroumov, Peter N.; Nolen, Jerry; Barcikowski, Albert; Pellin, Michael; Yacout, Abdellatif

2017-03-01

A new eXtreme MATerial (XMAT) research facility is being proposed at Argonne National Laboratory to enable rapid in situ mesoscale bulk analysis of ion radiation damage in advanced materials and nuclear fuels. This facility combines a new heavy-ion accelerator with the existing high-energy X-ray analysis capability of the Argonne Advanced Photon Source. The heavy-ion accelerator and target complex will enable experimenters to emulate the environment of a nuclear reactor making possible the study of fission fragment damage in materials. Material scientists will be able to use the measured material parameters to validate computer simulation codes and extrapolate the response of the material in a nuclear reactor environment. Utilizing a new heavy-ion accelerator will provide the appropriate energies and intensities to study these effects with beam intensities which allow experiments to run over hours or days instead of years. The XMAT facility will use a CW heavy-ion accelerator capable of providing beams of any stable isotope with adjustable energy up to 1.2 MeV/u for U-238(50+) and 1.7 MeV for protons. This energy is crucial to the design since it well mimics fission fragments that provide the major portion of the damage in nuclear fuels. The energy also allows damage to be created far from the surface of the material allowing bulk radiation damage effects to be investigated. The XMAT ion linac includes an electron cyclotron resonance ion source, a normal-conducting radio-frequency quadrupole and four normal-conducting multi-gap quarter-wave resonators operating at 60.625 MHz. This paper presents the 3D multi-physics design and analysis of the accelerating structures and beam dynamics studies of the linac.

Heavy ion linear accelerator for radiation damage studies of materials.

Science.gov (United States)

Kutsaev, Sergey V; Mustapha, Brahim; Ostroumov, Peter N; Nolen, Jerry; Barcikowski, Albert; Pellin, Michael; Yacout, Abdellatif

2017-03-01

A new eXtreme MATerial (XMAT) research facility is being proposed at Argonne National Laboratory to enable rapid in situ mesoscale bulk analysis of ion radiation damage in advanced materials and nuclear fuels. This facility combines a new heavy-ion accelerator with the existing high-energy X-ray analysis capability of the Argonne Advanced Photon Source. The heavy-ion accelerator and target complex will enable experimenters to emulate the environment of a nuclear reactor making possible the study of fission fragment damage in materials. Material scientists will be able to use the measured material parameters to validate computer simulation codes and extrapolate the response of the material in a nuclear reactor environment. Utilizing a new heavy-ion accelerator will provide the appropriate energies and intensities to study these effects with beam intensities which allow experiments to run over hours or days instead of years. The XMAT facility will use a CW heavy-ion accelerator capable of providing beams of any stable isotope with adjustable energy up to 1.2 MeV/u for 238 U 50+ and 1.7 MeV for protons. This energy is crucial to the design since it well mimics fission fragments that provide the major portion of the damage in nuclear fuels. The energy also allows damage to be created far from the surface of the material allowing bulk radiation damage effects to be investigated. The XMAT ion linac includes an electron cyclotron resonance ion source, a normal-conducting radio-frequency quadrupole and four normal-conducting multi-gap quarter-wave resonators operating at 60.625 MHz. This paper presents the 3D multi-physics design and analysis of the accelerating structures and beam dynamics studies of the linac.

Experiment of radiation-resistant materials for nuclear powers generating station

International Nuclear Information System (INIS)

Choe, J.H.; Lee, C.K.; Kong, Y.K.; Chang, H.S.

1981-01-01

The properties of polyethylene materials exhibit good insulation and radiation resistance, but exhibit poor flame resistance. Flame retardant properties of the polyethylene were improved by the radiation induced grafting, coating or cross-linking. When the various flame retardants were fixed onto polyethylene, the amount of fixation in grafting or coating was increased with the increase of radiation dosages. In the case of grafting, it is necessary for high grafting yield that the polyethylene films were swelled before irradiation with γ-rays or electron beams. It is the suitable method for the fixation of flame retardant that polyethylene samples were blended with various flame retardants at 125 0 C and then blended polymers were crosslinked by the electron beams at room temperature

Containing and discarding method for radiation contaminated materials and radiation contaminated material containing composite member

International Nuclear Information System (INIS)

Akagawa, Katsuhiko.

1995-01-01

A container for high level radiation contaminated materials is loaded in an outer container in a state of forming a gap between the outer container and a container wall, low level radiation contaminated materials are filled to the gap between the container of the radiation contaminated materials and the container wall, and then the outer container is sealed. In addition, the thickness of the layer of the low level radiation contaminated materials is made substantially uniform. Then, since radiation rays from the container of the radiation contaminated materials are decayed by the layer of the low level radiation contaminated materials at the periphery of the container and the level of the radiation rays emitted from the outer container is extremely reduced than in a case where the entire amount of high level radiation contaminated materials are filled, the level is suppressed to an extent somewhat higher than the level in the case where the entire amount of the low level radiation contaminated materials are filled. Accordingly, the management corresponds to that for the low level radiation contaminated materials, and the steps for the management and the entire volume thereof are reduced than in a case where the high level radiation contaminated materials and the low level radiation contaminated materials are sealed separately. (N.H.)

Computational Modeling of Radiation Phenomenon in SiC for Nuclear Applications

Science.gov (United States)

Ko, Hyunseok

Silicon carbide (SiC) material has been investigated for promising nuclear materials owing to its superior thermo-mechanical properties, and low neutron cross-section. While the interest in SiC has been increasing, the lack of fundamental understanding in many radiation phenomena is an important issue. More specifically, these phenomena in SiC include the fission gas transport, radiation induced defects and its evolution, radiation effects on the mechanical stability, matrix brittleness of SiC composites, and low thermal conductivities of SiC composites. To better design SiC and SiC composite materials for various nuclear applications, understanding each phenomenon and its significance under specific reactor conditions is important. In this thesis, we used various modeling approaches to understand the fundamental radiation phenomena in SiC for nuclear applications in three aspects: (a) fission product diffusion through SiC, (b) optimization of thermodynamic stable self-interstitial atom clusters, (c) interface effect in SiC composite and their change upon radiation. In (a) fission product transport work, we proposed that Ag/Cs diffusion in high energy grain boundaries may be the upper boundary in unirradiated SiC at relevant temperature, and radiation enhanced diffusion is responsible for fast diffusion measured in post-irradiated fuel particles. For (b) the self-interstitial cluster work, thermodynamically stable clusters are identified as a function of cluster size, shape, and compositions using a genetic algorithm. We found that there are compositional and configurational transitions for stable clusters as the cluster size increases. For (c) the interface effect in SiC composite, we investigated recently proposed interface, which is CNT reinforced SiC composite. The analytical model suggests that CNT/SiC composites have attractive mechanical and thermal properties, and these fortify the argument that SiC composites are good candidate materials for the cladding

Radiation processing program at the Malaysian Nuclear Agency

International Nuclear Information System (INIS)

Khairul Zaman Hj. Mohd Dahlan

2008-01-01

Radiation processing technology has been proven to enhance industrial efficiency and productivity, improve product quality and competitiveness. For many years, varieties of radiation crosslinkable materials based on synthetic polymers have been studied at the Malaysian Nuclear Agency either in the form of thermoplastic resins, polymer blends or composites. At present, effort is focused towards developing new materials based on natural polymers such as natural rubber and rubber based products, palm oil and palm oil based products and polysaccharide. Hydrogel based on sago starch has been developed and commercialized for face mask. As for wound dressing application, sago hydrogel is still subjected to the clinical evaluation. Sago starch has also been modified for biodegradable products such as bio-film and bio-foam for packaging purposes. On the other hand palm oil based acrylate resins have been synthesized at the Nuclear Malaysia for pressure sensitive adhesive and printing ink applications. Meanwhile, natural rubber is used in a polymer blend and composites for automotive components. All of these products are at various stages of commercialization. (author)

Nuclear safety and radiation protection report of the Bugey nuclear facilities - 2013

International Nuclear Information System (INIS)

2014-01-01

This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the facilities (INBs no. 78, 89 (NPPs in operation), 465 (NPP under deconstruction), 102 (fuel storage facility), and 173 (radioactive waste conditioning and storage facility under construction)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2013, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

Nuclear safety and radiation protection report of the Bugey nuclear facilities - 2014

International Nuclear Information System (INIS)

2015-01-01

This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the facilities (INBs no. 78, 89 (NPPs in operation), 465 (NPP under deconstruction), 102 (fuel storage facility), and 173 (radioactive waste conditioning and storage facility under construction)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2014, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

Australian Radiation Protection and Nuclear Safety Regulations 1999

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-11-01

This document contains statutory rules made under the Australian Radiation and Nuclear Safety Act 1998 defining how specified standards to be observed, practices and procedures to be followed and measures to be taken by controlled persons in relation to activities relating to controlled facilities, as well as in relation to dealings with controlled apparatus or controlled material

Australian Radiation Protection and Nuclear Safety Regulations 1999

International Nuclear Information System (INIS)

1999-01-01

This document contains statutory rules made under the Australian Radiation and Nuclear Safety Act 1998 defining how specified standards to be observed, practices and procedures to be followed and measures to be taken by controlled persons in relation to activities relating to controlled facilities, as well as in relation to dealings with controlled apparatus or controlled material

Introduction to workshop on radiation effects in nuclear waste materials

International Nuclear Information System (INIS)

Matzke, H.

1988-01-01

The workshop consisted of an invited lecture for REI-4, treating radiation damage in nuclear fuels as well as giving an introduction to the field of damage in waste matrices, of invited and contributed lectures to the workshop and to REI as well as of discussions and round table meetings. The contributions available as manuscripts are included on the following pages of these proceedings. At the end, a short summary with recommendations for future work has been added. It is hoped that the stimulating discussions of the workshop will help to continue the work in the field of radiation effects in waste matrices in an effective way. The organizer believes that there are good reasons for this hope and he thanks all scientists who contributed to the success of the workshop, as well as members of the organizing committee of REI-4 for their help. (orig.)

Investigating mechanical behavior and radiation resistant of fuel rods clad in nuclear power plant

International Nuclear Information System (INIS)

Sedgh Kerdar, A.

1999-01-01

The important factors for selection of material for use in nuclear reactors is similar to those for other engineering applications. There are however other parameters which are of importance when materials are going to be used in high radiation environments. These parameters are compatibility in intense nuclear radiation field, high resistance against corrosion and other characteristics such as thermal conductivity, machinability and suitable welding properties. This factors discussed in chapter one. In additions to the materials used as fuel, moderator, controls, etc., which have clear and stringent nuclear requirements, other materials may be necessary in a reactor to provide structural strength and other desired properties. For a materials used in a reactor core, the single most important property is its capacity for neutron absorption. Other properties, such as temperature and radiation stability, mechanical strength, corrosion resistance, etc., also receive much attention in selecting material for a specific application. Obviously, far more can be said about each of the potential metals than is possible in chapter two. We shall limit our attention to those metals of current nuclear interest, i.e., aluminium, beryllium magnesium, zirconium, austenitic stainless steels, nickel base alloys, and in factory metals (Nb and Mo). Interactions between matter and different radiations like Neutrons, protons, Gamma , Beta and Alpha rays in nuclear reactors induced important changes in properties of materials.There are five mechanism responsible for radiation induced changes in solids: ionization, vacancy formation, interstitial formation, creation of impurities caused by nuclear reactions and displacements spikes under the local thermal environment. Due to presence of many electrons in metals ionization does not play a major role in metals only the other four mechanisms are relevant to metals and their alloys. Generally speaking formation of many vacancies and

Safeguards for special nuclear materials

International Nuclear Information System (INIS)

Carlson, R.L.

1979-12-01

Safeguards, accountability, and nuclear materials are defined. The accuracy of measuring nuclear materials is discussed. The use of computers in nuclear materials accounting is described. Measures taken to physically protect nuclear materials are described

Role of visualization of nuclear radiation in public education on atomic energy. Visualization of natural nuclear radiation using a cloud chamber

International Nuclear Information System (INIS)

Kaneko, Junichi H.; Fujita, Fumiyuki; Narabayashi, Tadashi

2008-01-01

Nuclear radiation is indispensable tool, i.e., medical diagnostic systems and industrial nondestructive measurement systems, for our life. On the other hand, ordinary people sometimes have bad image for nuclear radiation. To improve this undesirable situation, many individuals and groups keep holding public educational meeting on nuclear radiation. For this purpose, visualization of natural nuclear radiation by a cloud chamber is very effective way; participants feel existence of nuclear radiation directly. In this talk, public educational activity of Hokkaido University and Japan Atomic Energy Society Hokkaido branch will be reported. (author)

Radiation effects on ion exchange materials

Energy Technology Data Exchange (ETDEWEB)

Gangwer, T.E.; Goldstein, M.; Pillay, K.K.S.

1977-11-01

An extensive literature review and data compilation has been completed on the radiation-damage of ion exchange resins. The primary goal of the study has been to review the available literature on ion exchange materials used in, as well as those with potential for use in, the nuclear fuel and waste reprocessing areas. The physical and chemical properties of ion exchangers are reviewed. Experimental parameters useful in characterizing the effects of radiation on synthetic ion exchange resins are identified or defined. In compiling the diverse types of data, an effort was made to present the experimental data or experimentally based parameters in a format that would be useful for inter-comparing radiation effects on resins. When subject to radiation there are various general trends or qualitative effects displayed by the different types of resins. These radiation-trends and effects have been formulated into qualitative statements. The present day level of understanding of the behavior of resins under ionizing radiation is too limited to justify quantitative predictive modeling. The limitations and deficiencies of the literature are discussed and the experimentation needed to achieve quantitative modeling are outlined. 14 figs., 108 references.

Radiation effects on ion exchange materials

International Nuclear Information System (INIS)

Gangwer, T.E.; Goldstein, M.; Pillay, K.K.S.

1977-11-01

An extensive literature review and data compilation has been completed on the radiation-damage of ion exchange resins. The primary goal of the study has been to review the available literature on ion exchange materials used in, as well as those with potential for use in, the nuclear fuel and waste reprocessing areas. The physical and chemical properties of ion exchangers are reviewed. Experimental parameters useful in characterizing the effects of radiation on synthetic ion exchange resins are identified or defined. In compiling the diverse types of data, an effort was made to present the experimental data or experimentally based parameters in a format that would be useful for inter-comparing radiation effects on resins. When subject to radiation there are various general trends or qualitative effects displayed by the different types of resins. These radiation-trends and effects have been formulated into qualitative statements. The present day level of understanding of the behavior of resins under ionizing radiation is too limited to justify quantitative predictive modeling. The limitations and deficiencies of the literature are discussed and the experimentation needed to achieve quantitative modeling are outlined. 14 figs., 108 references

Radiation-hardened micro-electronics for nuclear instrumentation

International Nuclear Information System (INIS)

Van Uffelen, M.

2007-01-01

The successful development and deployment of future fission and thermonuclear fusion reactors depends to a large extent on the advances of different enabling technologies. Not only the materials need to be custom engineered but also the instrumentation, the electronics and the communication equipment need to support operation in this harsh environment, with expected radiation levels during maintenance up to several MGy. Indeed, there are yet no commercially available electronic devices available off-the-shelf which demonstrated a satisfying operation at these extremely high radiation levels. The main goal of this task is to identify commercially available radiation tolerant technologies, and to design dedicated and integrated electronic circuits, using radiation hardening techniques, both at the topological and architectural level. Within a stepwise approach, we first design circuits with discrete components and look for an equivalent integrated technology. This will enable us to develop innovative instrumentation and communication tools for the next generation of nuclear reactors, where both radiation hardening and miniaturization play a dominant role

Lightweight Damage Tolerant, High-Temperature Radiators for Nuclear Power and Propulsion

Science.gov (United States)

Craven, Paul D.; SanSoucie, Michael P.

2015-01-01

NASA is increasingly emphasizing exploration to bodies beyond near-Earth orbit. New propulsion systems and new spacecraft are being built for these missions. As the target bodies get further out from Earth, high energy density systems, e.g., nuclear fusion, for propulsion and power will be advantageous. The mass and size of these systems, including supporting systems such as the heat exchange system, including thermal radiators, will need to be as small as possible. Conventional heat exchange systems are a significant portion of the total thermal management mass and size. Nuclear electric propulsion (NEP) is a promising option for high-speed, in-space travel due to the high energy density of nuclear fission power sources and efficient electric thrusters. Heat from the reactor is converted to power for use in propulsion or for system power. The heat not used in the power conversion is then radiated to space as shown in figure 1. Advanced power conversion technologies will require high operating temperatures and would benefit from lightweight radiator materials. Radiator performance dictates power output for nuclear electric propulsion systems. Pitch-based carbon fiber materials have the potential to offer significant improvements in operating temperature, thermal conductivity, and mass. These properties combine to allow significant decreases in the total mass of the radiators and significant increases in the operating temperature of the fins. A Center-funded project at NASA Marshall Space Flight Center has shown that high thermal conductivity, woven carbon fiber fins with no matrix material, can be used to dissipate waste heat from NEP systems and because of high specific power (kW/kg), will require less mass and possibly less total area than standard metal and composite radiator fins for radiating the same amount of heat. This project uses an innovative approach to reduce the mass and size required for the thermal radiators to the point that in-space NEP and power

Usage and conditions of radiation protection of nuclear meters in Brazil

International Nuclear Information System (INIS)

Guimarães, E.F.; Silva, F.C.A. da

2017-01-01

The industries of mining, pulp, oil, etc. which require a quality control in the processes, use the nuclear meters with sealed radioactive sources coupled to a radiation detector that generate accurate and fast answers regarding the level, thickness, density and humidity of different types of materials. Nuclear meters are classified as fixed or portable and use transmission, backscatter or reactive systems. As they use radioactive sources with various ranges of activities, they are classified by the International Atomic Energy Agency - AIEA as Category 3 and 4, of medium and low radiological risk, and must therefore have a suitable level of radiation protection for safe use in the installation. The Brazilian National Energy Commission - CNEN controls approximately 500 authorized facilities with nuclear meters. The paper technically describes the nuclear meters and the radiological protection procedures that must be followed for the safety of the IOEs (occupationally exposed individuals) and individuals from the public, based on the specific nuclear meter test program for CNEN radiation protection supervisor. The professionals who handle these nuclear meters should be aware of the radiological risk to their own protection and to individuals in the public. For safe operation with nuclear meters, a number of requirements must be observed according to the type and need of the installation

Gamma-ray identification of nuclear weapon materials

International Nuclear Information System (INIS)

Gosnell, T. B.; Hall, J. M.; Jam, C. L.; Knapp, D. A.; Koenig, Z. M.; Luke, S. J.; Pohl, B. A.; Schach Wittenau, A. von; Wolford, J. K.

1997-01-01

There has been an accelerating national interest in countering nuclear smuggling. This has caused a corresponding expansion of interest in the use of gamma-ray spectrometers for checkpoint monitoring, nuclear search, and within networks of nuclear and collateral sensors. All of these are fieldable instruments--ranging from large, fixed portal monitors to hand-held and remote monitoring equipment. For operational reasons, detectors with widely varying energy resolution and detection efficiency will be employed. In many instances, such instruments must be sensitive to weak signals, always capable of recognizing the gamma-ray signatures from nuclear weapons materials (NWM), often largely insensitive to spectral alteration by radiation transport through intervening materials, capable of real-time implementation, and able to discriminate against signals from commonly encountered legitimate gamma-ray sources, such as radiopharmaceuticals. Several decades of experience in classified programs have shown that all of these properties are not easily achieved and successful approaches were of limited scope--such as the detection of plutonium only. This project was originally planned as a two-year LDRD-ER. Since funding for 1997 was not sustained, this is a report of the first year's progress

Efforts of Uzbekistan to prevent nuclear terrorism and smuggling of radioactive and nuclear materials

International Nuclear Information System (INIS)

Petrenko, V.D.; Karimov, Yu.N.; Podkovirin, A.I.; Shipilov, N.N.; Yuldashev, B.S.; Fazylov, M.I.

2005-01-01

Uzbekistan is located on the cross-roads from the north-Russia, Western Europe-to the south-Afghanistan, Iran, Iraq and others. The appearance of terrorist organizations urged some Asian countries to make the nuclear weapons, the making the task of stopping the transportation of nuclear materials and technologies from the north (from countries possessing nuclear weapon) to the south (to countries desiring to have weapons and its components) a reality. To resolve this problem, on the main transportation routes, 'Yantar' stationary radiation monitors of Russian production were installed, and development and production of monitors of our own make was started. This paper covers these works as well as those on preventing possible terrorist attacks on nuclear objects of Uzbekistan

Nuclear safety and radiation protection report of the Belleville-sur-Loire nuclear facilities - 2013

International Nuclear Information System (INIS)

2014-01-01

This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 127 and 128). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2013, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

Nuclear safety and radiation protection report of the Belleville-sur-Loire nuclear facilities - 2014

International Nuclear Information System (INIS)

2015-01-01

This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 127 and 128). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2014, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

Nuclear safety and radiation protection report of the Dampierre-en-Burly nuclear facilities - 2013

International Nuclear Information System (INIS)

2014-01-01

This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 84 and 85). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2013, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

Nuclear safety and radiation protection report of Saint-Alban Saint-Maurice nuclear facilities - 2012

International Nuclear Information System (INIS)

2013-01-01

This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 119 and 120). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2012, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix. (J.S.)

Nuclear safety and radiation protection report of the Nogent-sur-Seine nuclear facilities - 2013

International Nuclear Information System (INIS)

2014-01-01

This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 129 and 130). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2013, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

Nuclear safety and radiation protection report of the Dampierre-en-Burly nuclear facilities - 2014

International Nuclear Information System (INIS)

2015-01-01

This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 84 and 85). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2014, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix

Nuclear material control systems for nuclear power plants

International Nuclear Information System (INIS)

1975-06-01

Paragraph 70.51(c) of 10 CFR Part 70 requires each licensee who is authorized to possess at any one time special nuclear material in a quantity exceeding one effective kilogram to establish, maintain, and follow written material control and accounting procedures that are sufficient to enable the licensee to account for the special nuclear material in his possession under license. While other paragraphs and sections of Part 70 provide specific requirements for nuclear material control systems for fuel cycle plants, such detailed requirements are not included for nuclear power reactors. This guide identifies elements acceptable to the NRC staff for a nuclear material control system for nuclear power reactors. (U.S.)

Experimental Studies of Carbon Nanotube Materials for Space Radiators

Science.gov (United States)

SanSoucie, MIchael P.; Rogers, Jan R.; Craven, Paul D.; Hyers, Robert W.

2012-01-01

Game ]changing propulsion systems are often enabled by novel designs using advanced materials. Radiator performance dictates power output for nuclear electric propulsion (NEP) systems. Carbon nanotubes (CNT) and carbon fiber materials have the potential to offer significant improvements in thermal conductivity and mass properties. A test apparatus was developed to test advanced radiator designs. This test apparatus uses a resistance heater inside a graphite tube. Metallic tubes can be slipped over the graphite tube to simulate a heat pipe. Several sub ]scale test articles were fabricated using CNT cloth and pitch ]based carbon fibers, which were bonded to a metallic tube using an active braze material. The test articles were heated up to 600 C and an infrared (IR) camera captured the results. The test apparatus and experimental results are presented here.

Radiation tests at cryogenic temperature on selected organic materials for LHC

International Nuclear Information System (INIS)

Humer, K.; Weber, H.W.; Szeless, B.; Tavlet, M.

1997-01-01

Future multi-TeV particle accelerators like the CERN Large Hadron Collider (LHC) will use superconducting magnets in which organic materials will be exposed to high radiation levels at temperatures as low as 2 K. A representative selection of organic materials comprising insulating films, cable insulations, epoxy resins and composites were exposed to neutron and gamma radiation of a nuclear reactor. Depending on the type of materials, the integrated radiation doses varied between 180 kGy and 155 MGy. During irradiation, the samples were kept close to the boiling temperature of liquid nitrogen, i.e. at 80 K, and thereafter stored in liquid nitrogen and transferred at the same temperature into the testing device for measurement of tensile and flexural strength. Tests were carried out on the same materials at similar dose rates at room temperature, and the results are compared with the ones obtained at cryogenic temperature. They show that within the selected dose range, a number of organic materials are suitable for use in radiation fields of the LHC at cryogenic temperature

Radiation embrittlement of Spanish nuclear reactor pressure vessel steels

International Nuclear Information System (INIS)

Bros, J.; Ballesteros, A.; Lopez, A.

1993-01-01

Commercial pressurized water reactor (PWR) and boiling water reactor (BWR) nuclear power plants contain a series of pressure vessel steel surveillance capsules as the principal means of monitoring radiation effects on the pressure vessel. Changes in fracture toughness are more severe in surveillance capsules than in reactor vessel materials because of their proximity of the reactor core. Therefore, it is possible to predict changes in fracture toughness of the reactor vessel materials. This paper describes the status of the reactor vessel surveillance program relating to Spanish nuclear power plants. To date, twelve capsules have been removed and analyzed from seven of the nine Spanish reactors in operation. The results obtained from the analysis of these capsules are compared with the predictions of the Nuclear Regulatory Commission (NRC) Regulatory Guide 1.99, Rev. 2, by means of measured and expected increase of the nil-ductility transition reference temperature (RT NDT ). The comparison is made considering the different variables normally included in the studies of radiation response of reactor pressure vessel materials, such as copper content of steel, level of neutron fluence above 1 MeV, base metal or weld metal, and so forth. The surveillance data have been used for determining the adjusted reference temperatures and upper shelf energies at any time. The results have shown that the seven pressure vessels are in excellent condition to continue operating with safety against brittle fracture beyond the design life, without the need to recuperate the degraded properties of the materials by annealing of the vessel

Radiation chemistry from basics to applications in material and life sciences

International Nuclear Information System (INIS)

Belloni, J.; Mostafavi, M.; Douki, Th.; Spotheim-Maurizot, M.

2008-01-01

This book gives a progress report on the many and original contributions of radiation chemistry to the fundamental knowledge of the vast domain of chemical reactions and its applications. Radiation chemistry techniques indeed make it possible to elucidate detailed physicochemical mechanisms in inorganic and organic chemistry (including in space) and in biochemistry. Moreover, this comprehension is applied in materials science to precisely control syntheses by radiation, such as radiopolymerization, radio-grafting, specific treatment of surfaces (textiles, paintings, inks,..), synthesis of complex nano-materials, degradation of environmental pollutants and radioresistance of materials for nuclear reactors. In life sciences, the study of the effects of radiation on bio-macromolecules (DNA, proteins, lipids) not only permits the comprehension of normal or pathological biological mechanisms, but also the improvement of our health. In particular, many advances in cancer radiotherapy, in the radioprotection of nuclear workers and the general population, as well as in the treatment of diseases and the radiosterilization of drugs, could be obtained thanks to this research. Abundantly illustrated and written in English by top international specialists who have taken care to render the subjects accessible, this work will greatly interest those curious about a scientific field that is new to them and students attracted by the original and multidisciplinary aspects of the field. At a time when radiation chemistry research is experiencing spectacular development in numerous countries, this book will attract newcomers to the field. (authors)

Calculation of isodose curves from initial neutron radiation of a hypothetical nuclear explosion using Monte Carlo Method

International Nuclear Information System (INIS)

Medeiros, Marcos P.C.; Rebello, Wilson F.; Andrade, Edson R.; Silva, Ademir X.

2015-01-01

Nuclear explosions are usually described in terms of its total yield and associated shock wave, thermal radiation and nuclear radiation effects. The nuclear radiation produced in such events has several components, consisting mainly of alpha and beta particles, neutrinos, X-rays, neutrons and gamma rays. For practical purposes, the radiation from a nuclear explosion is divided into i nitial nuclear radiation , referring to what is issued within one minute after the detonation, and 'residual nuclear radiation' covering everything else. The initial nuclear radiation can also be split between 'instantaneous or 'prompt' radiation, which involves neutrons and gamma rays from fission and from interactions between neutrons and nuclei of surrounding materials, and 'delayed' radiation, comprising emissions from the decay of fission products and from interactions of neutrons with nuclei of the air. This work aims at presenting isodose curves calculations at ground level by Monte Carlo simulation, allowing risk assessment and consequences modeling in radiation protection context. The isodose curves are related to neutrons produced by the prompt nuclear radiation from a hypothetical nuclear explosion with a total yield of 20 KT. Neutron fluency and emission spectrum were based on data available in the literature. Doses were calculated in the form of ambient dose equivalent due to neutrons H*(10) n - . (author)

Calculation of isodose curves from initial neutron radiation of a hypothetical nuclear explosion using Monte Carlo Method

Energy Technology Data Exchange (ETDEWEB)

Medeiros, Marcos P.C.; Rebello, Wilson F.; Andrade, Edson R., E-mail: rebello@ime.eb.br, E-mail: daltongirao@yahoo.com.br [Instituto Militar de Engenharia (IME), Rio de Janeiro, RJ (Brazil). Secao de Engenharia Nuclear; Silva, Ademir X., E-mail: ademir@nuclear.ufrj.br [Corrdenacao dos Programas de Pos-Graduacao em Egenharia (COPPE/UFRJ), Rio de Janeiro, RJ (Brazil). Programa de Engenharia Nuclear

2015-07-01

Nuclear explosions are usually described in terms of its total yield and associated shock wave, thermal radiation and nuclear radiation effects. The nuclear radiation produced in such events has several components, consisting mainly of alpha and beta particles, neutrinos, X-rays, neutrons and gamma rays. For practical purposes, the radiation from a nuclear explosion is divided into {sup i}nitial nuclear radiation{sup ,} referring to what is issued within one minute after the detonation, and 'residual nuclear radiation' covering everything else. The initial nuclear radiation can also be split between 'instantaneous or 'prompt' radiation, which involves neutrons and gamma rays from fission and from interactions between neutrons and nuclei of surrounding materials, and 'delayed' radiation, comprising emissions from the decay of fission products and from interactions of neutrons with nuclei of the air. This work aims at presenting isodose curves calculations at ground level by Monte Carlo simulation, allowing risk assessment and consequences modeling in radiation protection context. The isodose curves are related to neutrons produced by the prompt nuclear radiation from a hypothetical nuclear explosion with a total yield of 20 KT. Neutron fluency and emission spectrum were based on data available in the literature. Doses were calculated in the form of ambient dose equivalent due to neutrons H*(10){sub n}{sup -}. (author)

10 CFR 74.41 - Nuclear material control and accounting for special nuclear material of moderate strategic...

Science.gov (United States)

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false Nuclear material control and accounting for special nuclear material of moderate strategic significance. 74.41 Section 74.41 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) MATERIAL CONTROL AND ACCOUNTING OF SPECIAL NUCLEAR MATERIAL Special Nuclear Material...

ASN report on the status of nuclear safety and radiation protection in France in 2015. Extracts

International Nuclear Information System (INIS)

2016-01-01

After a recall of ASN missions, key figures and organisation, an overview of main events for 2015, and a presentation of the French law related to energy transition for a green growth, a first part of this huge document presents actions undertaken by the ASN in 2015 in different fields: ionizing radiations and risks for health and the environment, principles and actors of control of nuclear safety and radiation protection, regulation, control of nuclear activities and of exposures to ionizing radiations, emergency radiological and post-accidental situations, public information transparency and participation, international relationships, regional overview of nuclear safety and radiation protection. The second part addresses activities controlled by the ASN: medical uses of ionizing radiations, industrial, research and veterinary uses and source safety, transportation of radioactive materials, EDF nuclear power plants, installations related to nuclear fuel cycle, various industrial and research installations, safety of basic nuclear installation dismantling, radioactive wastes and polluted sites and soils

Materials of All-Polish Symposium Nuclear Techniques in Industry, Medicine, Agriculture and Environment Protection

International Nuclear Information System (INIS)

1998-01-01

The All-Polish Symposium Nuclear Techniques in Industry, Medicine, Agriculture and Environment Protection is cyclic (in 3 year period) conference being a broad review of state of art and development of all nuclear branches cooperated with industry and other branches of national economy and public life in Poland. The conference has been divided in one plenary session and 8 problem sessions as follow: Radiation technologies of flue gas purification; radiation technologies in food and cosmetic industry; application of nuclear techniques in environmental studies and earth science; radiometric methods in material engineering; isotope tracers in biological studies and medical diagnostics; radiometric industrial measuring systems; radiation detectors and device; nuclear methods in cultural objects examination. The poster section as well as small exhibition have been also organised

Patient absorbed dose and radiation risk in nuclear medicine

International Nuclear Information System (INIS)

Hetherington, E.; Cochrane, P.

1992-01-01

Since the introduction of technetium-99m labelled radiopharmaceuticals used as imaging agents in the nuclear medicine departments of Australian hospitals, patients have voiced concern about the effect of having radioactive materials injected into their bodies. The danger of X-ray exposure is widely known and well accepted, as is exposure to ultrasound, computed tomography scans and other imaging techniques. However, radioactivity is an unknown, and fear of the unknown can occasionally lead to patients refusing to undergo a nuclear medicine procedure. The authors emphasised that the radiation dose to a patient from a typical procedure would depend on the patient's medical history and treatment; the average dose being approximately 50 times the exposure received from the natural environmental background radiation. Furthermore, over an extended period the body can repair most minor damage caused by radiation, just as the body can repair the damage caused by sunburn resulting from too much exposure to sunlight. The risk of genetic effects as a result of a medical radiation dose is than very small

Nuclear radiation detectors

International Nuclear Information System (INIS)

Kapoor, S.S.; Ramamurthy, V.S.

1986-01-01

The present monograph is intended to treat the commonly used detectors in the field of nuclear physics covering important developments of the recent years. After a general introduction, a brief account of interaction of radiation with matter relevant to the processes in radiation detection is given in Chapter II. In addition to the ionization chamber, proportional counters and Geiger Mueller counters, several gas-filled detectors of advanced design such as those recently developed for heavy ion physics and other types of studies have been covered in Chapter III. Semiconductor detectors are dealt with in Chapter IV. The scintillation detectors which function by sensing the photons emitted by the luminescence process during the interaction of the impinging radiation with the scintillation detector medium are described in Chapter V. The topic of neutron detectors is covered in Chapter VI, as in this case the emphasis is more on the method of neutron detection rather than on detector type. Electronic instrumentation related to signal pulse processing dealt with in Chapter VII. The track etch detectors based on the visualization of the track of the impinging charge particle have also been briefly covered in the last chapter. The scope of this monograph is confined to detectors commonly used in low and medium energy nuclear physics research and applications of nuclear techniques. The monograph is intended for post-graduate students and those beginning to work with the radiation detectors. (author)

Nuclear energy and radiation

International Nuclear Information System (INIS)

Myers, D.K.; Johnson, J.R.

1980-01-01

Both the light water reactor and the Canadian heavy water reactor systems produce electricity cheaply and efficiently. They produce some fissionable byproducts, which can be recycled to extend energy sources many-fold. Besides the production of electrical power, the nuclear industry produces various radioistopes used for treatment of cancer, in diagnostic procedures in nuclear medicine, in ionization smoke detectors, and as radioactive tracers with various technological applications including the study of the mechanisms of life. The increment in environmental radiation levels resulting from operation of nuclear power reactors represents a very small fraction of the radiation levels to which we are all exposed from natural sources, and of the average radiation exposures resulting from diagnostic procedures in the healing arts. The total health hazard of the complete nuclear power cycle is generally agreed to be smaller than the hazards associated with the generation of an equal amount of electricity from most other currently available sources of energy. The hazards from energy production in terms of shortened life expectancy are much smaller in all cases than the resulting increase in health and life expectancy. (auth)

Active neutron technique for detecting attempted special nuclear material diversion

International Nuclear Information System (INIS)

Smith, G.W.; Rice, L.G. III.

1979-01-01

The identification of special nuclear material (SNM) diversion is necessary if SNM inventory control is to be maintained at nuclear facilities. (Special nuclear materials are defined for this purpose as either 235 U of 239 Pu.) Direct SNM identification by the detection of natural decay or fission radiation is inadequate if the SNM is concealed by appropriate shielding. The active neutron interrogation technique described combines direct SNM identification by delayed fission neutron (DFN) detection with implied SNM detection by the identification of materials capable of shielding SNM from direct detection. This technique is being developed for application in an unattended material/equipment portal through which items such as electronic instruments, packages, tool boxes, etc., will pass. The volume of this portal will be 41-cm wide, 53-cm high and 76-cm deep. The objective of this technique is to identify an attempted diversion of at least 20 grams of SNM with a measurement time of 30 seconds

REVIEW OF EQUIPMENT USED IN RUSSIAN PRACTICE FOR ACCOUNTING MEASUREMENTS OF NUCLEAR MATERIALS

International Nuclear Information System (INIS)

NEYMOTIN, L.

1999-01-01

The objective of this work was to analyze instrumentation and methodologies used at Russian nuclear facilities for measurement of item nuclear materials, materials in bulk form, and waste streams; specify possibilities for the application of accounting measurements; and develop recommendations for improvement. The major steps and results: Representative conversion, enrichment (gas centrifuge), fuel fabrication, spent fuel reprocessing, and chemical-metallurgical production facilities in Russia were selected; Full lists of nuclear materials were prepared; Information about measurement methods and instrumentation for each type of nuclear material were gathered; and Recommendations on methodological and instrumentation support of accounting measurements for all types of materials were formulated. The analysis showed that the existing measurement methods and instrumentation serve mostly to support the technological process control and nuclear and radiation safety control. Requirements for these applications are lower than requirements for MC and A applications. To improve the state of MC and A at Russian nuclear facilities, significant changes in instrumentation support will be required, specifically in weighing equipment, volume measurements, and destructive and non-destructive analysis equipment, along with certified reference materials

Report by the ASN on the situation of nuclear safety and radiation protection in France in 2013

International Nuclear Information System (INIS)

Chevet, Pierre-Franck; Delmestre, Alain; Bardet, Marie-Christine; Covard, Fabienne; Javay, Olivier

2014-01-01

In its first chapters, this huge report presents the various actions undertaken by the ASN. It proposes a detailed overview of the issue of ionizing radiations and risks for health and for the environment in the field of nuclear activities, presents and comments the principles and actors of the control of nuclear safety and of radiation protection, presents the different elements of the legal framework, describes and comments the control of nuclear activities and of exposures to ionizing radiations. The next chapters address the actions controlled by the ASN: radiological and post-accidental radiological situations, present measures related to public information and transparency, overview of international relationships, regional overview of nuclear safety and radiation protection, medical use of ionizing radiations, industrial, research and veterinary uses and the issue of source safety, the issue of radioactive material transportation. Issues of nuclear safety and radiation protection are then discussed for electronuclear plants, for installations dedicated to the nuclear fuel cycle, for various research and industrial nuclear installations, for the dismantling of base nuclear installations, and for radioactive wastes and polluted sites and soils

Nuclear safety and radiation protection report of the Saint-Laurent-des-Eaux nuclear facilities - 2011

International Nuclear Information System (INIS)

2012-01-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Saint-Laurent-des-Eaux nuclear power plant (Saint-Laurent-Nouan (FR)): 2 partially dismantled graphite-gas reactors and a graphite sleeves storage silo (INB 46 and 74), and 2 PWR reactors in operation (INB 100). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2011, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Nuclear safety and radiation protection report of the Saint-Laurent-des-Eaux nuclear facilities - 2010

International Nuclear Information System (INIS)

2011-06-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Saint-Laurent-des-Eaux nuclear power plant (Saint-Laurent-Nouan (FR)): 2 partially dismantled graphite-gas reactors and a graphite sleeves storage silo (INB 46 and 74), and 2 PWR reactors in operation (INB 100). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Science, society, and America's nuclear waste: Unit 2, Ionizing radiation

International Nuclear Information System (INIS)

1992-01-01

''Science, Society and America's Nuclear Waste'' is a four-unit secondary curriculum. It is intended to provide information about scientific and societal issues related to the management of spent nuclear fuel from generation of electricity at nuclear powerplants and high-level radioactive waste from US national defense activities. The curriculum, supporting classroom activities, and teaching materials present a brief discussion of energy and electricity generation, including that produced at nuclear powerplants; information on sources, amounts, location, and characteristics of spent nuclear fuel and high-level radioactive waste; sources, types and effects of radiation; US policy for managing and disposing of spent nuclear fuel and high-level radioactive waste and what other countries are doing; and the components of the nuclear waste management system

Radiation protecting clothing materials

International Nuclear Information System (INIS)

Mio, Kotaro; Ijiri, Yasuo.

1986-01-01

Purpose: To provide radiation protecting clothing materials excellent in mechanical strength, corrosion resistance, flexibility and flexing strength. Constitution: The radiation protecting clothing materials according to this invention has pure lead sheets comprising a thin pure lead foil of 50 to 150 μm and radiation resistant organic materials, for example, polyethylene with high neutron shielding effect disposed to one or both surfaces thereof. The material are excellent in the repeating bending fatigue and mechanical strength, corrosion resistance and flexibility and, accordingly, radiation protecting clothings prepared by using them along or laminating them also possess these excellent characteristics. Further, they are excellent in the handlability, particularly, durability to the repeated holding and extension, as well as are preferable in the physical movability and feeling upon putting. The clothing materials may be cut into an appropriate size, or stitched into clothings made by radiation-resistant materials. In this case, pure lead sheets are used in lamination. (Horiuchi, T.)

Reporting nuclear power plant operation to the Finnish Centre for Radiation and Nuclear Safety

International Nuclear Information System (INIS)

1997-01-01

The Finnish Centre for Radiation and Nuclear safety (STUK) is the authority in Finland responsible for controlling the safety of the use of nuclear energy. The control includes, among other things, inspection of documents, reports and other clarification submitted to the STUK, and also independent safety analyses and inspections at the plant site. The guide presents what reports and notifications of the operation of the nuclear facilities are required and how they shall be submitted to the STUK. The guide does not cover reports to be submitted on nuclear material safeguards addressed in the guide YVL 6.10. Guide YVL 6.11 presents reporting related to the physical protection of nuclear power plants. Monitoring and reporting of occupational exposure at nuclear power plants is presented in the guide YVL 7.10 and reporting on radiological control in the environment of nuclear power plants in the guide YVL 7.8

Classification of scrap material from nuclear power plants as acceptable for recirculation

International Nuclear Information System (INIS)

Bergman, C.

1983-06-01

The Swedish National Institute of Radiation Protection has in a principal decision accepted that scrap material from nuclear power plants, that contains or may contain radioactive material, can be recirculated. The document is an English translation of the background material for the Board meeting decision and gives some guide-lines for the authority when dealing with this questions. (author)

Radiation protection during operation of nuclear power plants

International Nuclear Information System (INIS)

1983-01-01

This Guide describes a Radiation Protection Programme for nuclear power plants. It includes: (1) An outline of the basic principles as well as practical aspects of the programme; (2) A description of the responsibilities of the operating organization to establish an effective programme based upon these principles; (3) A description of the administrative and technical measures to establish and implement the programme. This Guide also deals with the operational aspects to be considered by the operating organization in reviewing design in order to facilitate implementation of the Radiation Protection Programme. This Guide covers the requirements for a Radiation Protection Programme for all operational states of the nuclear power plant. It also includes guidelines for handling planned special exposures and for coping with unplanned exposures and contamination of personnel, areas, and equipment. Additional information concerning emergency situations involving releases of radioactive materials is given in Safety Guides 50-SG-O6, ''Preparedness of the Operating Organization (Licensee) for Emergencies at Nuclear Power Plants'', and 50-SG-G6, ''Preparedness of Public Authorities for Emergencies at Nuclear Power Plants''. This Guide covers the principles of dose limitation to site personnel and to the public, but it does not include detailed instructions on the techniques used for the actual measurement and evaluation of the exposures. This Guide does not include detailed instructions on environmental surveys, but it does mention principal steps in environmental monitoring which may be required for confirmation of the acceptability of radioactive discharges

Radiation protection in nuclear medicine

Energy Technology Data Exchange (ETDEWEB)

Volodin, V; Hanson, G P

1993-12-31

The goal of this Chapter is to give a general outline of the essential principles and procedures for radiation protection in a nuclear medicine department where radionuclides are used for diagnosis and therapy. More detailed recommendations regarding radiation protection in nuclear medicine are given in the publications of the International Commission on Radiation Protection (ICRP, publications 25, 57, 60) and in ILO/IAEA/WHO Manual on Radiation Protection in Hospitals and General Practice (Volume 2: Unsealed Sources, WHO, Geneva, 1975), on which this Chapter is based. This chapter is not intended to replace the above-mentioned international recommendations on radiation protection, as well as existing national regulations on this subject, but intended only to provide guidance for implementing these recommendations in clinical practice

Radiation protection in nuclear medicine

International Nuclear Information System (INIS)

Volodin, V.; Hanson, G.P.

1992-01-01

The goal of this Chapter is to give a general outline of the essential principles and procedures for radiation protection in a nuclear medicine department where radionuclides are used for diagnosis and therapy. More detailed recommendations regarding radiation protection in nuclear medicine are given in the publications of the International Commission on Radiation Protection (ICRP, publications 25, 57, 60) and in ILO/IAEA/WHO Manual on Radiation Protection in Hospitals and General Practice (Volume 2: Unsealed Sources, WHO, Geneva, 1975), on which this Chapter is based. This chapter is not intended to replace the above-mentioned international recommendations on radiation protection, as well as existing national regulations on this subject, but intended only to provide guidance for implementing these recommendations in clinical practice

Radiation effects in technologies of semiconductor materials and devises

International Nuclear Information System (INIS)

Korshunov, F.P.; Bogatyrev, Yu.V.; Lastovskij, S.B.; Marchenko, I.G.; Zhdanovich, N.E.

2003-01-01

In the paper were considered the physical basics and practical results of using of penetrating radiations in technologies of nuclear transmutation of semiconductor materials (Si, GaAs) as well as in production of semiconductor devices including high-power silicon diodes, thyristors and transistors. It is shown the high efficiency of radiation technology for increasing of electronic device speed, exclusion of technological operations such as gold or platinum diffusions, increase of quality, decrease of prime cost and increase of good-to-bad device ratio yield

Global nuclear material monitoring with NDA and C/S data through integrated facility monitoring

International Nuclear Information System (INIS)

Howell, J.A.; Menlove, H.O.; Argo, P.; Goulding, C.; Klosterbuer, S.; Halbig, J.

1996-01-01

This paper focuses on a flexible, integrated demonstration of a monitoring approach for nuclear material monitoring. This includes aspects of item signature identification, perimeter portal monitoring, advanced data analysis, and communication as a part of an unattended continuous monitoring system in an operating nuclear facility. Advanced analysis is applied to the integrated nondestructive assay and containment and surveillance data that are synchronized in time. End result will be the foundation for a cost-effective monitoring system that could provide the necessary transparency even in areas that are denied to foreign nationals of both US and Russia should these processes and materials come under full-scope safeguards or bilateral agreements. Monitoring systems of this kind have the potential to provide additional benefits including improved nuclear facility security and safeguards and lower personnel radiation exposures. Demonstration facilities in this paper include VTRAP-prototype, Los Alamos Critical Assemblies Facility, Kazakhstan BM-350 Reactor monitor, DUPIC radiation monitoring, and JOYO and MONJU radiation monitoring

Specialty glass development for radiation shielding windows and nuclear waste immobilization

International Nuclear Information System (INIS)

Mandal, S.; Ghorui, S.; Roy Chowdhury, A.; Sen, R.; Chakraborty, A.K.; Sen, S.; Maiti, H.S.

2015-01-01

The technology of two important varieties of specialty glasses, namely high density Radiation Shielding Window (RSW) glass and specialty glass beads of borosilicate composition have been successfully developed in CGCRI with an aim to meet the countries requirement. Radiation Shielding Windows used in nuclear installations, are viewing devices, which allow direct viewing into radioactive areas while still providing adequate protection to the operating personnel. The glass blocks are stabilized against damage from radiation by introducing cerium in definite proportions. Considering the essentially of developing an indigenous technology to make the country self-sufficient for this critical item, CGCRI has taken up a major programme to develop high lead containing glasses required for RSWs under a MoD with BARC. On the other hand, the specialty glass bead of specific composition and properties is a critical material required for management of radioactive waste in a closed nuclear fuel cycle that is followed by India. During reprocessing of the spent nuclear fuel, high level radio-active liquid waste (HLW) is produced containing unwanted radio isotopes some of which remain radioactive for thousands of years. The need is to immobilize them within a molecular structure so that they will not come out and be released to the ambience and thereby needs to be resolved if nuclear power is to make a significant contribution to the country's power requirement. Borosilicate glass has emerged as the material of choice for immobilization due to its unique random network structure

Radiation protection databases of nuclear safety regulatory authority

International Nuclear Information System (INIS)

Janzekovic, H.; Vokal, B.; Krizman, M.

2003-01-01

Radiation protection and nuclear safety of nuclear installations have a common objective, protection against ionising radiation. The operational safety of a nuclear power plant is evaluated using performance indicators as for instance collective radiation exposure, unit capability factor, unplanned capability loss factor, etc. As stated by WANO (World Association of Nuclear Operators) the performance indicators are 'a management tool so each operator can monitor its own performance and progress, set challenging goals for improvement and consistently compare performance with that of other plants or industry'. In order to make the analysis of the performance indicators feasible to an operator as well as to regulatory authorities a suitable database should be created based on the data related to a facility or facilities. Moreover, the international bodies found out that the comparison of radiation protection in nuclear facilities in different countries could be feasible only if the databases with well defined parameters are established. The article will briefly describe the development of international databases regarding radiation protection related to nuclear facilities. The issues related to the possible development of the efficient radiation protection control of a nuclear facility based on experience of the Slovenian Nuclear Safety Administration will be presented. (author)

Integrated Radiation Transport and Nuclear Fuel Performance for Assembly-Level Simulations

Energy Technology Data Exchange (ETDEWEB)

Clarno, Kevin T [ORNL; Hamilton, Steven P [ORNL; Philip, Bobby [ORNL; Berrill, Mark A [ORNL; Sampath, Rahul S [ORNL; Allu, Srikanth [ORNL; Pugmire, Dave [ORNL; Dilts, Gary [Los Alamos National Laboratory (LANL); Banfield, James E [ORNL

2012-02-01

The Advanced Multi-Physics (AMP) Nuclear Fuel Performance code (AMPFuel) is focused on predicting the temperature and strain within a nuclear fuel assembly to evaluate the performance and safety of existing and advanced nuclear fuel bundles within existing and advanced nuclear reactors. AMPFuel was extended to include an integrated nuclear fuel assembly capability for (one-way) coupled radiation transport and nuclear fuel assembly thermo-mechanics. This capability is the initial step toward incorporating an improved predictive nuclear fuel assembly modeling capability to accurately account for source-terms and boundary conditions of traditional (single-pin) nuclear fuel performance simulation, such as the neutron flux distribution, coolant conditions, and assembly mechanical stresses. A novel scheme is introduced for transferring the power distribution from the Scale/Denovo (Denovo) radiation transport code (structured, Cartesian mesh with smeared materials within each cell) to AMPFuel (unstructured, hexagonal mesh with a single material within each cell), allowing the use of a relatively coarse spatial mesh (10 million elements) for the radiation transport and a fine spatial mesh (3.3 billion elements) for thermo-mechanics with very little loss of accuracy. In addition, a new nuclear fuel-specific preconditioner was developed to account for the high aspect ratio of each fuel pin (12 feet axially, but 1 4 inches in diameter) with many individual fuel regions (pellets). With this novel capability, AMPFuel was used to model an entire 17 17 pressurized water reactor fuel assembly with many of the features resolved in three dimensions (for thermo-mechanics and/or neutronics), including the fuel, gap, and cladding of each of the 264 fuel pins; the 25 guide tubes; the top and bottom structural regions; and the upper and lower (neutron) reflector regions. The final, full assembly calculation was executed on Jaguar using 40,000 cores in under 10 hours to model over 162

Research on crisis communication of nuclear and radiation safety

International Nuclear Information System (INIS)

Cao Yali; Zhang Ying

2013-01-01

Insufficient public cognition of nuclear and radiation safety and absence of effective method to handle crisis lead to common crisis events of nuclear and radiation safety, which brings about unfavorable impact on the sound development of nuclear energy exploring and application of nuclear technology. This paper, based on crisis communication theory, analyzed the effect of current situation on nuclear and radiation safety crisis, discussed how to handle crisis, and tried to explore the effective strategies for nuclear and radiation safety crisis handling. (authors)

Nuclear radiation application to nanotechnology

International Nuclear Information System (INIS)

Chakarvarti, S.K.

2012-01-01

Out of the numerous uses and applications of nuclear radiation, in particular heavy ions, the interaction of radiation with materials have culminated into a gamut of fine tools and technologies for taming the synergetic potential of the interaction. One such field of the immense importance is nanotechnology through nuclear radiation via use of ion-crafted polymeric membranes- so called 'Template Synthesis'. This talk will be addressed to the users of membranes - organic (polymeric) in general, formed through irradiation of polymeric foils with heavy and energetic ions followed by chemical processing leading finally to what is known as 'Track Etch Membranes (TEMs)', and present the review of the innovative uses of these membranes from filtration to electro-kinetic based applications and nano-/micro fabrication of devices- the potent aspect of emerging technologies. The emphasis would be on the dependence of useful and novel usages including applications in nano devices' fabrication. A membrane, with its most comprehensive and clear definition, is an intervening phase separating two phases and/or acting as an active or passive barrier to the transport of matter between phases. The very existence of a membrane relies upon the functionality domain of the pores contained therein. The geometrical traits and morphology of the pore ensembles dictate the applications, which any membrane can serve to. There are variety of membranes being developed and used in myriad of applications in diverse fields of science and technology. The range of commercially available membrane materials is quiet diverse and varies widely in terms of composition, and physical structure. The creation of pores, whether through natural self-assembling phenomenon or man-made processes, might itself be an issue of interest but these are the pore-traits which are fundamentally more important, whether the membrane is being used for sieving-one of the ever most important applications the mankind has been

Auditing nuclear materials statements

International Nuclear Information System (INIS)

Anon.

1973-01-01

A standard that may be used as a guide for persons making independent examinations of nuclear materials statements or reports regarding inventory quantities on hand, receipts, production, shipment, losses, etc. is presented. The objective of the examination of nuclear materials statements by the independent auditor is the expression of an opinion on the fairness with which the statements present the nuclear materials position of a nuclear materials facility and the movement of such inventory materials for the period under review. The opinion is based upon an examination made in accordance with auditing criteria, including an evaluation of internal control, a test of recorded transactions, and a review of measured discards and materials unaccounted for (MUF). The standard draws heavily upon financial auditing standards and procedures published by the American Institute of Certified Public Accountants

Microcomputer based shelf system to monitor special nuclear materials in storage

International Nuclear Information System (INIS)

Nicholson, N.; Kuckertz, T.H.; Ethridge, C.D.

1980-01-01

Diversion of special nuclear material has become a matter of grave concern in recent years. Large quantities of this material are kept in long-term storage and must be inventoried periodically, resulting in a time-consuming activity that exposes personnel to additional radiation. A system that provides continuous surveillance of stored special nuclear materials has been developed. A shelf monitor has been designed using a single component microcomputer to collect data from a Geiger Muller tube that monitors gamma emissions and a scale that monitors the total weight of the special nuclear material and its container. A network of these shelf monitors reports their acquired data to a minicomputer for analysis and storage. Because a large number of these monitors is likely to be needed in most storage facilities, one objective of this program has been to develop a low cost but reliable monitor

Nuclear safety and radiation protection report of the Saint-Alban Saint-Maurice nuclear facilities - 2014

International Nuclear Information System (INIS)

2015-01-01

This safety report was established in accordance with articles L. 125-15 and L. 125-16 of the French environmental code. It presents, first, the NPPs (INBs no. 119 and 120). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2014, if any, are reported as well as the radioactive and non-radioactive effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facility are presented (type of waste, quantities, conditioning process). The document concludes with a presentation of the actions of communication and public information made by the direction of the facility. A glossary and the list of recommendations from the Committees for health, safety and working conditions are given in appendix