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Sample records for computerized materials protection

  1. Computerized materials protection, control, and accountability

    International Nuclear Information System (INIS)

    Whiteson, R.; Seitz, S.; Landry, R.P.; Hadden, M.L.; Painter, J.A.

    1997-01-01

    The proliferation of nuclear weapons, along with the technical knowledge and materials needed to make these weapons, is an enduring problem of international urgency. Current international nuclear nonproliferation efforts are aimed at deterring, detecting, and responding to proliferation of weapons of mass destruction. These safeguards efforts are being implemented by applying preeminent science and technology to the management and control of nuclear materials. By strengthening systems of nuclear material protection, control, and accountability (MPC and A), one can reduce the threat of nuclear weapons proliferation. Two major programs of international cooperation are now underway to achieve this goal. The first is between the US Department of Energy (DOE) and the Institutes of the Russian Federation (Laboratory-to-Laboratory Program), and the second is between the US Government and Governments of the former Soviet Republics (Government-to-Government Program). As part of these programs, the DOE is working with facilities to assist them in implementing computerized MPC and A systems. This work is a collaboration between computer scientists and safeguards experts in both the US and the new Republics. The US is making available technology and expertise to enable Russian experts to build on computerized MPC and A software developed in the US. This paper describes the joint efforts of these international teams to develop sophisticated computerized MPC and A systems using modern computer hardware and software technology. These systems are being customized to meet the site-specific needs of each facility

  2. Safeguarding nuclear materials in the former Soviet Republics through computerized materials protection, control and accountability

    International Nuclear Information System (INIS)

    Roumiantsev, A.N.; Ostroumov, Y.A.; Whiteson, R.; Seitz, S.L.; Landry, R.P.; Martinez, B.J.; Boor, M.G.; Anderson, L.K.; Gary, S.P.

    1997-01-01

    The threat of nuclear weapons proliferation is a problem of global concern. International efforts at nonproliferation focus on preventing acquisition of weapons-grade nuclear materials by unauthorized states, organizations, or individuals. Nonproliferation can best be accomplished through international cooperation in the application of advanced science and technology to the management and control of nuclear materials. Computerized systems for nuclear material protection, control, and accountability (MPC and A) are a vital component of integrated nuclear safeguards programs. This paper describes the progress of scientists in the United States and former Soviet Republics in creating customized, computerized MPC and A systems. The authors discuss implementation of the Core Material Accountability System (CoreMAS), which was developed at Los Alamos National Laboratory by the US Department of Energy and incorporates, in condensed and integrated form, the most valuable experience gained by US nuclear enterprises in accounting for and controlling nuclear materials. The CoreMAS approach and corresponding software package have been made available to sites internationally. CoreMAS provides methods to evaluate their existing systems and to examine advantages and disadvantages of customizing CoreMAS or improving their own existing systems. The sites can also address crucial issues of software assurance, data security, and system performance; compare operational experiences at sites with functioning computerized systems; and reasonably evaluate future efforts. The goal of the CoreMAS project is to introduce facilities at sites all over the world to modern international MPC and A practices and to help them implement effective, modern, computerized MPC and A systems to account for their nuclear materials, and thus reduce the likelihood of theft or diversion. Sites are assisted with MPC and A concepts and the implementation of an effective computerized MPC and A system

  3. Computerized materials protection, control, and accountability at the Institute of Physics and Power Engineering

    International Nuclear Information System (INIS)

    Efimenko, V.; Goryunov, V.; Ilyantsev, A.

    1998-01-01

    As part of a multifaceted approach to protecting its nuclear materials, The Institute of Physics and Power Engineering (IPPE) at Obninsk, Russia, has been computerizing its materials protection, control, and accountability capabilities. This is being accomplished in collaboration with the CoreMAS team at Los Alamos National Laboratory. Such international cooperation in applying advanced science and technology to managing and controlling nuclear materials will help reduce the threat of nuclear weapons proliferation by preventing acquisition of weapons-grade nuclear materials by unauthorized individuals, organizations, or states. One important characteristic of IPPE is that it encompasses several facilities that manage nuclear materials, and three of these facilities already operate their own independent (or independently developed) computerized accounting systems. This paper focuses on the importance of compatibility between the computerized accountability systems at the facilities, the ability of the individual systems to communicate with a single site-wide system, and the necessity of coordination between facilities in designing and developing computerized systems. The authors believe that the lessons learned at IPPE in coordinating these efforts have wide-ranging significance for other sites with multiple facilities

  4. Computerized reactor protection and safety related systems in nuclear power plants. Proceedings of a specialists' meeting. Working material

    International Nuclear Information System (INIS)

    1998-01-01

    Though the majority of existing control and protection systems in nuclear power plants use old analogue technology and design philosophy, the use of computers in safety and safety related systems is becoming a current practice. The Specialists Meeting on ''Computerized Reactor Protection and Safety Related Systems in Nuclear Power Plants'' was organized by IAEA (jointly by the Division of Nuclear Power and the Fuel Cycle and the Division of Nuclear Installation Safety), in co-operation with Paks Nuclear Power Plant in Hungary and was held from 27-29 October 1997 in Budapest, Hungary. The meeting focused on computerized safety systems under refurbishment, software reliability issues, licensing experiences and experiences in implemented computerized safety and safety related systems. Within a meeting programme a technical visit to Paks NPP was organized. The objective of the meeting was to provide an international forum for the presentation and discussion on R and D, in-plant experiences in I and C important to safety, backfits and arguments for and reservations against the digital safety systems. The meeting was attended by 70 participants from 16 countries representing NPPs and utility organizations, design/engineering, research and development, and regulatory organizations. In the course of 4 sessions 25 technical presentations were made. The present volume contains the papers presented by national delegates and the conclusions drawn from the final general discussion

  5. Diversity in computerized reactor protection systems

    International Nuclear Information System (INIS)

    Fischer, H.D.; Piel, L.

    1999-01-01

    Based on engineering judgement, the most important measures to increase the independency of redundant trains of a computerized safety instrumentation and control system (I and C) in a nuclear power plant are evaluated with respect to practical applications. This paper will contribute to an objective discussion on the necessary and justifiable arrangement of diversity in a computerized safety I and C system. Important conclusions are: - (i) diverse equipment may be used to control dependent failures only if measures necessary for designing, licensing, and operating a computerized safety I and C system homogeneous in equipment are neither technically nor economically feasible; - (ii) the considerable large operating experience in France with a non-diverse equipment digital reactor protection system does not call for equipment diversity. Although there are no generally accepted methods, the licensing authority is still required to take into account dependent failures in a probabilistic safety analysis; - (ii) the frequency of postulated initiating events implies which I and C functionality should be implemented on diverse equipment. Using non-safety I and C equipment in addition to safety I and C equipment is attractive because its necessary unavailability to control an initiating event in teamwork with the safety I and C equipment is estimated to range from 0.01 to 0.1. This can be achieved by operational experience

  6. Computerized reactor pressure vessel materials information system

    International Nuclear Information System (INIS)

    Strosnider, J.; Monserrate, C.; Kenworthy, L.D.; Tether, C.D.

    1980-10-01

    A computerized information system for storage and retrieval of reactor pressure vessel materials data was established, as part of Task Action Plan A-11, Reactor Vessel Materials Toughness. Data stored in the system are necessary for evaluating the resistance of reactor pressure vessels to flaw-induced fracture. This report includes (1) a description of the information system; (2) guidance on accessing the system; and (3) a user's manual for the system

  7. Computerized materials data at EPRI

    International Nuclear Information System (INIS)

    Gilman, J.

    1985-01-01

    In this paper an overview of the development of materials database systems is given as well as brief descriptions of several databases built by the Electric Power Research Institute (EPRI) for the Nuclear Power Industry. A number of important lessons about databases have been learned by EPRI and will be discussed. A schematic outline of the major steps in developing a database is given in figure 6. For materials properties in general, the process begins with raw data from laboratory tests which are recorded by a variety of media which may or may not be machine-readable. After compilation, which often requires manual transcription, checking, and reformatting, the assembled data are loaded into a database. Associated with the database is computer software that allows for sorting, searching, etc., and is called the database management system. In addition, other software can provide statistical analysis and graphical displays

  8. Modernizing computerized nuclear material accounting systems

    International Nuclear Information System (INIS)

    Erkkila, B.H.; Claborn, J.

    1995-01-01

    DOE Orders and draft orders for nuclear material control and accountability address a complete material control and accountability (MC and A) program for all DOE contractors processing, using, or storing nuclear materials. A critical element of an MC and A program is the accounting system used to track and record all inventories of nuclear material and movements of materials in those inventories. Most DOE facilities use computerized accounting systems to facilitate the task of accounting for all their inventory of nuclear materials. Many facilities still use a mixture of a manual paper system with a computerized system. Also, facilities may use multiple systems to support information needed for MC and A. For real-time accounting it is desirable to implement a single integrated data base management system for a variety of users. In addition to accountability needs, waste management, material management, and production operations must be supported. Information in these systems can also support criticality safety and other safety issues. Modern networked microcomputers provide extensive processing and reporting capabilities that single mainframe computer systems struggle with. This paper describes an approach being developed at Los Alamos to address these problems

  9. Computerized real-time materials accountability system for safeguards material control

    International Nuclear Information System (INIS)

    Spencer, W.F.; Affel, R.G.; Austin, H.C.; Nichols, J.P.; Stoutt, B.H.; Wachter, J.W.

    1975-01-01

    A real-time, computer-based system is described which provides safeguards material control at the Oak Ridge National Laboratory. Originally installed in 1972 to provide computerized real-time fissile materials accountability for criticality control purposes, the system has been expanded to provide accountability of all source and nuclear materials (SNM) and to utilize the on-line inventory files in support of the Laboratory physical protection and surveillance procedures. (auth)

  10. Computerized access to materials data. A progress report

    International Nuclear Information System (INIS)

    Rumble, J. Jr.

    1985-01-01

    As the effort to build a comprehensive computerized materials data system grows, it becomes more obvious that the benefits will be far-reaching. During this workshop, the enthusiasm of the participants grew steadily until the questions became not''What,'' but ''When?''. The engineering community within the United States has banded together many times to advance progress in engineering capability. The computerized materials data system requires such an effort, and the rewards will be substantial. Chapter 3 identifies changes in the use of materials data in the Nuclear Power Industry. Chapter 4 describes the EPRI experience in building computerized materials databases. In Chapter 5, the National Materials Property Data Network is discussed. The next four chapters present summaries of the workshop discussions and its conclusions. Chapter 6 discusses the content of the proposed system, Chapter 7 its size and the data sources, and Chapter 8 the user interfaces and system capabilities. In Chapter 9, ways of making further progress are outlined

  11. E/Z MAS: An easy-to-use computerized materials control and accountability system

    International Nuclear Information System (INIS)

    Anderson, L.K.; Boor, M.G.; Hurford, J.M.; Landry, R.P.; Martinez, B.J.; Solem, A.M.; Whiteson, R.; Zardecki, A.

    1998-01-01

    Nuclear facilities that handle and process nuclear materials are required to track their nuclear holdings and to keep adequate records that manage and control the inventory of those holdings. The complexity of a system that does this job is directly proportional to the complexity of the facility's operations. This paper describes an approach to computerized materials protection, control, and accountability (MPC and A) that was introduced by Los Alamos National Laboratory (LANL) in the fall of 1997. This new system, E/Z MAS, is the latest addition to the LANL suite of computerized MPC and A tools, which also includes the CoreMAS system. E/Z MAS was initially designed to address the needs of those facilities that have small to modest MPC and A needs but has been expanded to provide full functionality for any facility. The system name, E/Z MAS, reflects the system's easy-to-use characteristics, which include ease of installation and ease of software maintenance. Both CoreMAS and E/Z MAS have been provided to facilities in the Former Soviet Union to assist them in implementing a computerized MPC and A system that meets their needs. In this paper the authors will address the functionality of CoreMAS and E/Z MAS, and an argument in favor of intranet-based material control and accountability will be advanced

  12. Computerization of nuclear material accounting and control at storage facilities of RT-1 plant, PA Mayak

    International Nuclear Information System (INIS)

    Krakhmal'nik, V.I.; Menshchikov, Yu.L.; Mozhaev, D.A.

    1999-01-01

    Computerized system for nuclear material (NM) accounting and control at RT-1 plant is being created on the basis of advanced engineering and programming tools, which give a possibility to ensure prompt access to the information required, to unify the accounting and report documentation, make statistical processing of the data, and trace the NM transfers in the chain of its storage at facilities of RT-1 plant. Currently, the accounting is performed in parallel, both by the old methods and with computerized system. The following functions are performed by the system at the current stage: input of data on the end product's (plutonium dioxide) quantitative and qualitative composition; data input on the localization of containers with finished products at storage facilities of the plant and the product's temporary characteristics; selective verification of the data on containers and batches, according to the criteria prespecified by the user; data protection against unauthorized access; data archiving; report documents formation and providing [ru

  13. 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.)

  14. Material for radioactive protection

    Science.gov (United States)

    Taylor, R.S.; Boyer, N.W.

    A boron containing burn resistant, low-level radiation protection material useful, for example, as a liner for radioactive waste disposal and storage, a component for neutron absorber, and a shield for a neutron source is described. The material is basically composed of borax in the range of 25 to 50%, coal tar in the range of 25 to 37.5%, with the remainder being an epoxy resin mix. A preferred composition is 50% borax, 25% coal tar and 25% epoxy resin. The material is not susceptible to burning and is about 1/5 the cost of existing radiation protection material utilized in similar applications.

  15. Implementing of the nuclear materials accounting and control computerized system at JINR

    International Nuclear Information System (INIS)

    Dobryanskij, V.M.; Kalyakin, N.N.; Koltin, G.P.; Samojlov, V.N.; Cheker, A.V.; Shestakov, B.A.

    2000-01-01

    The results of the development of the computerized nuclear materials accounting system at the Joint Institute for Nuclear Research (JINR) are submitted. This work was carried out under Russian-American Nuclear Materials Protection, Control and Accounting (MPCandA) Program. The System was implemented at the Institute, it was attested to work with sensitive information. The computerized information nuclear materials accounting and control system, named MTIS (Materials Tracking Information System), is intended for the automated accounting of the nuclear materials used in JINR, tracking their moving, changes of their inventory amounts, preparation of the required documentation, and also for information support of the measures spent in the JINR on MPCandA program. MTIS can prepare reports for federal level and can also generate data to be reported for internal purposes. MTIS includes as one of the subsystems a program module to prepare reporting information to the Federal Information System (FIS). The system MTIS provides control of access to the database (DB), protection of the information against the non-authorized access, division of the data into the sensitive and non-sensitive data. (author)

  16. Analysis of concrete material through gamma ray computerized tomography

    International Nuclear Information System (INIS)

    Oliveira Junior, J.M. de

    2004-01-01

    Computerized Tomography (CT) refers to the cross sectional imaging of an object from both transmission or reflection data collected by illuminating the object from many different directions. The most important contribution of CT is to greatly improve abilities to distinguish regions with different gamma ray transmittance and to separate over-lying structures. The mathematical problem of the CT imaging is that of estimating an image from its projections. These projections can represent, for example, the linear attenuation coefficient of γ-rays along the path of the ray. In this work we will present some new results obtained by using tomographic techniques to analyze column samples of concrete to check the distribution of various materials and structural problems. These concrete samples were made using different proportions of stone, sand and cement. Another set of samples with different proportions of sand and cement were also used to verify the outcome from the CT analysis and the differences between them. Those samples were prepared at the Material Laboratory of Faculdade de Engenharia de Sorocaba, following the same procedures used in real case of concrete tests. The projections used in this work was obtained by Mini Computerized Tomograph of Uniso (MTCU), located at the Experimental Nuclear Physics Laboratory at University of Sorocaba. This tomograph operates with a gamma ray source of 241 Am (photons of 60 keV and 100 mCi of intensity) and a NaI(Tl) solid state detector. The system features translation and rotation scanning modes, a 100 mm effective field of view, and 1 mm spatial resolution. The image reconstruction problem is solved using Discrete Filtered Backprojection (FBP). (author)

  17. Radiation protection in computerized tomography diagnostics; Strahlenschutz in der Computertomografie

    Energy Technology Data Exchange (ETDEWEB)

    Grust, Andreas [Radiologie am Hauptbahnhof, Duesseldorf (Germany)

    2012-11-01

    The essential advantage of computerized tomography (CT) compared to projecting radiographic techniques is the display of organs free of superposition using a 3D data set and additional enhanced contrast resolution. CT is a mostly objective and examination-independent technique that has developed towards an indispensable tool for tumor diagnostics and traumatology. With respect to the total amount of X-ray diagnostic examinations CT is a rather seldom used technique, nevertheless causing a disproportionately high amount of the collective effective dose of the German population. This disadvantage triggers the necessity to work on a radiation dose reduction. The author discusses the issues X-ray tube current reduction, layer thickness, pitch factor, scan length, dose modulation, adaptive collimation, and iterative reconstruction.

  18. Comparison, with regard to safety, between a hard-wired reactor protection system and a computerized protection system. Pt. 1

    International Nuclear Information System (INIS)

    Buettner, W.E.

    1976-07-01

    The study compares a conventional hard-wired dynamic reactor protection system with a computerized protection system. In the comparison, only the unequivocally safety-oriented protection actions are considered. In the first part, the different structures of both systems and the method of verification for their functional safety will be described. In the second part, the mean unavailability in case of demand for both systems under defined conditions will be determined. (orig.) [de

  19. Outline of a computerized nuclear material accounting system applicable to nuclear power reactors

    International Nuclear Information System (INIS)

    Handshuh, J.W.

    1975-01-01

    A computerized nuclear material accounting system is described which enables a utility to account for its material throughout the entire fuel cycle. From input of transactions, the system records and reports inventories and transactions by accounts which the user may establish for discrete locations, item control areas, further subdivisions, and material types. Account numbers are designed so that accounts and records are automatically sorted in the order desired. The system also generates the Material Status Reports for the Nuclear Regulatory Commission

  20. Safety-technical comparison of a hard-wired dynamic reactor protection system with a computerized alternative. Pt. 2

    International Nuclear Information System (INIS)

    Buettner, W.E.

    1978-03-01

    The investigation presented here compares a conventional hard-wired dynamic reactor protection system with a computerized alternative. For both systems the spurious trip probability is determined, i.e. the probability of a false release of one or more protection actions due to failures. The mean unavailability is also determined for those not distinctly safety-oriented protection actions of the computerized protection system which are released via the open circuit current principle. This is because system breakdowns prevent the release of those protection actions in case of demand. The advantages and disadvantages of either type of system are viewed against each other. (orig.) [de

  1. Test and evaluation of computerized nuclear material accounting methods. Final report

    International Nuclear Information System (INIS)

    1995-01-01

    In accordance with the definition of a Material Balance Area (MBA) as a well-defined geographical area involving an Integral operation, the building housing the BFS-1 and BFS-1 critical facilities is considered to consist of one MBA. The BFS materials are in the form of small disks clad in stainless steel and each disk with nuclear material has its own serial number. Fissile material disks in the BFS MBA can be located at three key monitoring points: BFS-1 facility, BFS-2 facility and main storage of BFS fissile materials (storage 1). When used in the BFS-1 or BFS-2 critical facilities, the fissile material disks are loaded in tubes (fuel rods) forming critical assembly cores. The following specific features of the BFS MBA should be taken into account for the purpose of computerized accounting of nuclear material: (1) very large number of nuclear material items (about 70,000 fissile material items); and (2) periodically very intensive shuffling of nuclear material items. Requirements for the computerized system are determined by basic objectives of nuclear material accounting: (1) providing accurate information on the identity and location of all items in the BFS material balance area; (2) providing accurate information on location and identity of tamper-indicating devices; (3) tracking nuclear material inventories; (4) issuing periodic reports; (5) assisting with the detection of material gains or losses; (6) providing a history of nuclear material transactions; (7) preventing unauthorized access to the system and data falsification. In August 1995, the prototype computerized accounting system was installed on the BFS facility for trial operation. Information on two nuclear material types was entered into the data base: weapon-grade plutonium metal and 36% enriched uranium dioxide. The total number of the weapon-grade plutonium disks is 12,690 and the total number of the uranium dioxide disks is 1,700

  2. Computerized transportation model for the NRC Physical Protection Project. Versions I and II

    International Nuclear Information System (INIS)

    Anderson, G.M.

    1978-01-01

    Details on two versions of a computerized model for the transportation system of the NRC Physical Protection Project are presented. The Version I model permits scheduling of all types of transport units associated with a truck fleet, including truck trailers, truck tractors, escort vehicles and crews. A fixed-fleet itinerary construction process is used in which iterations on fleet size are required until the service requirements are satisfied. The Version II model adds an aircraft mode capability and provides for a more efficient non-fixed-fleet itinerary generation process. Test results using both versions are included

  3. Computerized nuclear material database management system for power reactors

    International Nuclear Information System (INIS)

    Cheng Binghao; Zhu Rongbao; Liu Daming; Cao Bin; Liu Ling; Tan Yajun; Jiang Jincai

    1994-01-01

    The software packages for nuclear material database management for power reactors are described. The database structure, data flow and model for management of the database are analysed. Also mentioned are the main functions and characterizations of the software packages, which are successfully installed and used at both the Daya Bay Nuclear Power Plant and the Qinshan Nuclear Power Plant for the purposed of handling nuclear material database automatically

  4. Interactive Computerized Based Training, In Radiation Protection at NRC-Negev

    International Nuclear Information System (INIS)

    Sberlo, E.; Krumbein, H.; Ankri, D.; Ben-Shachar, B.; Laichter, Y.; Weizer, G.; Adorarn, D.

    1999-01-01

    According to the rules of safety at the working places in Israel, all radiation employees in Israel should receive once a year a refreshing course in several areas of safety. At the NRC-Negev there are two kinds of radiation employees: the ''hot area'' employees, who work in an environment of radioactive materials or radiation machines and the ''old area'' employees (all the other employees in the NRC-Negev). One of the main goals of the Department of Human Resources Development and Training at the NRC-Negev was to organize safety refresher courses. All ''hot area'' employees received a training program of two days in safety subjects, each year. The ''cold area'' employees received the same course, each second year. The former training program included several lectures in radiation protection, health physics, biological effects of ionizing radiation, etc., as well as same lectures in industrial safety, fast aid, fee fighting, emergency procedures, etc. The safety refresher courses were given by Rental lectures. There were a lot of disadvantages in these frontal lectures: The lecturers are employees of the NRCN who had to stop their routine work in order to lecture; the lecturers had to carry out identical training for each course for a large group of workers; there was a lack of testing methods or any other certification for the employees. Recently, seven safety courseware were developed by the NRC-Negev and the CET (Centre for Educational Technology), in order to perform these safety refresher courses. The courseware are based on an interactive computerized training including tutorials and quiz. The tutorial is an interactive course in each subject. The employee gets a simple and clear explanation (including pictures). After each Morial there is a quiz which includes 7 American style questions. The first two courseware are for all the employees, the next 4 courseware for the ''hot area'' employees, and the seventh for the ''cold area'' employees (the seventh is a

  5. Feasibility study--computerized application of the hazardous material regulations

    International Nuclear Information System (INIS)

    Ferrada, J.J.; Green, V.M.; Rawl, R.R.

    1992-09-01

    The feasibility of developing a full expert system for transportation and packaging of hazardous and radioactive materials was initiated within the framework of three subtasks: (1) analysis of commercial packages related to regulation scanning, (2) analysis of computer languages to develop the expert system, and (3) development of expert system prototypes. The strategy to develop the latter subtask was to first,develop modules to capture the knowledge of different areas of transportation and packaging and second, to analyze the feasibility of appending these different modules in one final full package. The individual modules development contemplated one prototype for transporting and packaging of radioactive material and another for transporting hazardous chemical materials. In the event that it is not feasible to link these two packages, the modules can always be used as stand-alone tools, or linked as a single package with some restrictions in their applicability. The work done during this fiscal year has focused on developing a prototype for transporting radioactive materials

  6. Computerized early warning tool for material demand forecast

    NARCIS (Netherlands)

    Zhang, Wei

    2007-01-01

    One way to manage the material flows in supply chain is based on the purchase orders and the demand forecast for the next company in the chain. ASML in Veldhoven is a world leader in manufacturing lithography systems for the semiconductor industry. Within the company, a SAP system supports the

  7. Process information displays from a computerized nuclear materials control and accounting system

    International Nuclear Information System (INIS)

    Ellis, J.H.

    1981-11-01

    A computerized nuclear materials control and accounting system is being developed for an LWR spent fuel reprocessing facility. This system directly accesses process instrument readings, sample analyses, and outputs of various on-line analytical instruments. In this paper, methods of processing and displaying this information in ways that aid in the efficient, timely, and safe control of the chemical processes of the facility are described

  8. Physical protection of nuclear material

    International Nuclear Information System (INIS)

    1975-01-01

    Full text: An Advisory Group met to consider the up-dating and extension of the Recommendations for the Physical Protection of Nuclear Material, produced in 1972. Twenty-seven experts from 11 countries and EURATOM were present. Growing concern has been expressed in many countries that nuclear material may one day be used for acts of sabotage or terrorism. Serious attention is therefore being given to the need for States to develop national systems for the physical protection of nuclear materials during use, storage and transport throughout the nuclear fuel cycle which should minimize risks of sabotage or theft. The revised Recommendations formulated by the Advisory Group include new definitions of the objectives of national systems of physical protection and proposals for minimizing possibilities of unauthorized removal and sabotage to nuclear facilities. The Recommendations also describe administrative or organizational steps to be taken for this purpose and the essential technical requirements of physical protection for various types and locations of nuclear material, e.g., the setting up of protected areas, the use of physical barriers and alarms, the need for security survey, and the need of advance arrangements between the States concerned in case of international transportation, among others. (author)

  9. Development of a generic, computerized nuclear material accountability system: NucMAS

    International Nuclear Information System (INIS)

    Cornell, M.D.; O'Leary, J.M.

    1987-01-01

    The application NucMAS provides basic computerized accountability functions for the Savannah River Plant (SRP) Separations Department Material Balance Areas (MBA's). These functions include data entry, data management, calculations, and report generation. NucMAS can be used both for routine reporting to the SRP central Material Control and Accounting (MC and A) system and for rapid ad hoc queries in emergency situations. The system is designed to work with any process handling one or more of the 17 accountable nuclear materials specified by the Department of Energy (DOE). It relies on user-supplied configuration data to drive data prompts, report headings, data validations, and calculations

  10. Development and trial operation of a site-wide computerized material accounting system at Kurchatov Institute

    Energy Technology Data Exchange (ETDEWEB)

    Roumiantsev, A.N.; Ostroumov, Y.A.; Yevstropov, A.V. [Kurchatov Institute RRC, Moscow (Russian Federation)] [and others

    1997-11-01

    Since August 1994 Kurchatov Institute in cooperation with several US Department of Energy Laboratories has been developing a site-wide computerized material accounting system for nuclear materials. In 1994 a prototype system was put into trial operation at two Kurchatov facilities. Evaluation of this prototype led to the development of a new computerized material accounting system named KI-MACS, which has been operational since 1996. This system is a site-wide local secure computer network with centralized database capable of dealing with strictly confidential data and performing near-real time accountancy. It utilizes a Microsoft Windows NT operating system with SQL Server and Visual Basic, and has a `star`-like network architecture. KI-MACS is capable of dealing with materials in itemized and bulk form, and can perform statistical evaluations of measurements and material balance. KI-MACS is fully integrated with bar code equipment, electronic scales, gamma-ray spectrometers and an Active Well Coincidence Counter, thus providing almost on-line evaluation and utilization of results of measurements, item identification and accounting. At present KI-MACS is being used in Physical Inventory Taking at the Kurchatov Central Storage Facility, and by the end of 1997 will be installed at twelve Kurchatov nuclear facilities.

  11. Development and trial operation of a site-wide computerized material accounting system at Kurchatov Institute

    International Nuclear Information System (INIS)

    Roumiantsev, A.N.; Ostroumov, Y.A.; Yevstropov, A.V.

    1997-01-01

    Since August 1994 Kurchatov Institute in cooperation with several US Department of Energy Laboratories has been developing a site-wide computerized material accounting system for nuclear materials. In 1994 a prototype system was put into trial operation at two Kurchatov facilities. Evaluation of this prototype led to the development of a new computerized material accounting system named KI-MACS, which has been operational since 1996. This system is a site-wide local secure computer network with centralized database capable of dealing with strictly confidential data and performing near-real time accountancy. It utilizes a Microsoft Windows NT operating system with SQL Server and Visual Basic, and has a 'star'-like network architecture. KI-MACS is capable of dealing with materials in itemized and bulk form, and can perform statistical evaluations of measurements and material balance. KI-MACS is fully integrated with bar code equipment, electronic scales, gamma-ray spectrometers and an Active Well Coincidence Counter, thus providing almost on-line evaluation and utilization of results of measurements, item identification and accounting. At present KI-MACS is being used in Physical Inventory Taking at the Kurchatov Central Storage Facility, and by the end of 1997 will be installed at twelve Kurchatov nuclear facilities

  12. Sensitivity studies using the TRNSM 2 computerized model for the NRC physical protection project. Final report

    International Nuclear Information System (INIS)

    Anderson, G.M.

    1979-08-01

    A computerized model of the transportation system for shipment of nuclear fuel cycle materials is required to investigate the effects on fleet size, fleet composition and efficiency of fleet utilization resulting from changes in a variety of physical and regulatory factors, including shipping requirements, security regulations, work rules, maintenance requirements, and vehicle capacities. Such a model has been developed which provides a capability for complete sizing requirements studies of a combined aircraft and truck fleet. This report presents the results of a series of sensitivity studies performed using this model. These studies include the effects of the intinerary optimization criteria, work rules, and maintenance policies. These results demonstrate the effectiveness and versatility of the model for investigating the effects of a wide variety of physical and regulatory factors on the transportation fleet

  13. Development of a computerized nuclear materials control and accounting system for a fuel reprocessing plant

    International Nuclear Information System (INIS)

    Crawford, J.M.; Ehinger, M.H.; Joseph, C.; Madeen, M.L.

    1979-07-01

    A computerized nuclear materials control and accounting system (CNMCAS) for a fuel reprocessing plant is being developed by Allied-General Nuclear Services at the Barnwell Nuclear Fuel Plant. Development work includes on-line demonstration of near real-time measurement, measurement control, accounting, and processing monitoring/process surveillance activities during test process runs using natural uranium. A technique for estimating in-process inventory is also being developed. This paper describes development work performed and planned, plus significant design features required to integrate CNMCAS into an advanced safeguards system

  14. Development of a computerized nuclear materials control and accounting system for a fuel reprocessing plant

    International Nuclear Information System (INIS)

    Crawford, J.M.; Ehinger, M.H.; Joseph, C.; Madeen, M.L.

    1979-01-01

    A computerized nuclear materials control and accounting system (CNMCAS) for a fuel reprocessing plant is being developed by Allied-General Nuclear Services at the Barnwell Nuclear Fuel Plant. Development work includes on-line demonstration of near real-time measurement, measurement control, accounting, and processing monitoring/process surveillance activities during test process runs using natural uranium. A technique for estimating in-process inventory is also being developed. This paper describes development work performed and planned, plus significant design features required to integrate CNMCAS into an advanced safeguards system. 2 refs

  15. New developments in protective materials

    International Nuclear Information System (INIS)

    Mirick, W.

    1987-01-01

    Linemen who must work in close proximity to high voltage circuits utilize various types of protective equipment to minimize risks of injury due to electrical shock or other hazards. Tools are available which sometimes allow the linemen to work at a relatively safe distance from potential sources of danger. However, these tools may not be appropriate in all instances and, in fact, work often may be better conducted by hand using insulated clothing and accessories. Electrical insulating gloves and sleeves are presently worn by linemen for protection from electrical shock. In addition, insulating line hose, covers, and blankets are employed to cover high voltage sources when linemen are working in those areas. Leather gloves--protectors-- are worn over the rubber electrical insulating gloves to prevent cuts, punctures, or other physical injuries to the rubber glove. Deficiencies were perceived, however, with respect to protective equipment now available. Specific problems being experienced with insulating protective equipment were reported to be related to material characteristics such as flexibility, weight, ozone/corona resistance, hydraulic fluid resistance and stiffness, particularly at cold temperatures. Discussions between the Electric Power Research Institute (EPRI) and Battelle's Columbus Division (BCD) resulted a program to investigate the need for and the development of improved electrical insulating equipment for linemen. This article describes the program

  16. Materials testing by computerized tomography with neutrons and gamma-rays

    Energy Technology Data Exchange (ETDEWEB)

    El-Ghobary, A M; Bakkoush, F A; Megahid, R M [Reactor and Neutron Physics Department, Nuclear Research Center, A.E.A., Cairo (Egypt)

    1997-12-31

    The method of computerized tomography by fast neutrons and gamma-rays are used for inspecting and testing of materials by non-destructive technique. The transmission technique was applied using narrow collimated beams of reactor neutrons and gamma-ray. The neutron and gamma-rays transmitted through the object inspection were measured by means of a neutron gamma detector with Ne - 213 liquid organic scintillator. The undesired pulses of neutrons or gamma-rays are rejected from the transmitted beam by a discrimination technique based on the difference in the decay part of light pulse produced by recoil electrons or recoil protons. The transmitted neutrons or gamma-rays for different projections used to get the image of the section through the object investigated using the method of filtered back projection (FBP) algorithm. 8 figs.

  17. Computerization of operation and maintenance for nuclear power plants. Working material

    International Nuclear Information System (INIS)

    1994-01-01

    This report provides a resource for computerization of activities in plant operation and maintenance. Experience gained from design and implementation of various computer systems around the world is described. The material may be useful as a guide to modification and upgrading of existing plants as well as design and engineering of new plants. It should be particularly of interest to managers and engineers who are engaged in planning, bidding, specifying or designing computer systems for operation and maintenance applications. The technical document is the result of a series of advisory and consultant meetings held by the IAEA in Vienna in 1991 - 1994. The document was prepared with the participation of experts from Canada, France, Germany, Hungary, Japan, Russia, Sweden, United Kingdom, and the United States. Refs, figs and tabs

  18. RADTRAN II: a computerized model for risk analysis of transportation of radioactive material

    International Nuclear Information System (INIS)

    Taylor, J.M.; Daniel, S.L.; Biringer, B.E.

    1980-01-01

    The RADTRAN computer code, which formed the basis for the 1977 US generic transportation risk assessment, has been extensively updated. The updated version of the code, denoted RADTRAN II, includes changes based on findings from other transportation risk studies as well as changes based on reevaluation of earlier assumptions, analyses, and computerization techniques. The environmental impact of the transportation of radioactive material can be envisioned as consisting of five components, incident free transport, non-radiological impacts, vehicular accidents, breaches of security/safeguards, and failures of quality assurance. RADTRAN II is designed to evaluate both the incident-free and the accident contribution directly and can be used to evaluate the contributions of breaches of security and quality assurances deviation if some alterations in coding are made. Non-radiological impacts are not addressed

  19. Detecting errors and anomalies in computerized materials control and accountability databases

    International Nuclear Information System (INIS)

    Whiteson, R.; Hench, K.; Yarbro, T.; Baumgart, C.

    1998-01-01

    The Automated MC and A Database Assessment project is aimed at improving anomaly and error detection in materials control and accountability (MC and A) databases and increasing confidence in the data that they contain. Anomalous data resulting in poor categorization of nuclear material inventories greatly reduces the value of the database information to users. Therefore it is essential that MC and A data be assessed periodically for anomalies or errors. Anomaly detection can identify errors in databases and thus provide assurance of the integrity of data. An expert system has been developed at Los Alamos National Laboratory that examines these large databases for anomalous or erroneous data. For several years, MC and A subject matter experts at Los Alamos have been using this automated system to examine the large amounts of accountability data that the Los Alamos Plutonium Facility generates. These data are collected and managed by the Material Accountability and Safeguards System, a near-real-time computerized nuclear material accountability and safeguards system. This year they have expanded the user base, customizing the anomaly detector for the varying requirements of different groups of users. This paper describes the progress in customizing the expert systems to the needs of the users of the data and reports on their results

  20. 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.)

  1. Advantages obtained in radiation protection when using computerized radiography tests - CR (digital) in processing plants

    International Nuclear Information System (INIS)

    Jose, Joao Carlos Videira; Milani, Hilton Sergio B.; Paes, Eliseu Almir de Oliveira; Boita, Mario de; Souza, Laercio de; Serra, Flavio Augusto dos Santos

    2002-01-01

    During the year 2000, the ARCtest initiated the development of the research for adapting the Computerized Radiography - CR, originally conceived for medical applications, for the Industry, trying initially to attend the requirements of the processing plants, concerning to the detection of deterioration mechanisms (evaluation of the piping integrity). Due to the obtained excellent results, the possibility of utilization the Computerized Radiography - CR in the radiographic inspection were studied during the shutdown of the Catalytic Cracking Unit of the PETROBRAS-REPLAN, specifically in the replacement of the CO boiler superheater, where a large number of the small diameter welded joints have been predicted

  2. X-ray exposure dose for the gonadal gland by the examination of computerized tomography and its protection

    International Nuclear Information System (INIS)

    Moriuchi, Iwao; Kaiya, Hisanori; Hirata, Toshifumi; Asada, Shuichi

    1978-01-01

    Computerized tomography (CT) is very useful for neuroradiological examination, and so it may possibly be used for screening tests. But x-ray exposure dose by a examination of CT is considerable, especially for the male gonadal gland. This study showed that the dose from a complete CT examination of 10 - 15 scans for a male gonadal gland was about 1,800 times more than a single plain neuroradiography. But by only a 0.07 mm lead equivalent protecter, the exposure dose resulting from CT for a gonadal gland could be reduced to 0.0 mrad. (auth.)

  3. Alkali metal protective garment and composite material

    Science.gov (United States)

    Ballif, III, John L.; Yuan, Wei W.

    1980-01-01

    A protective garment and composite material providing satisfactory heat resistance and physical protection for articles and personnel exposed to hot molten alkali metals, such as sodium. Physical protection is provided by a continuous layer of nickel foil. Heat resistance is provided by an underlying backing layer of thermal insulation. Overlying outer layers of fireproof woven ceramic fibers are used to protect the foil during storage and handling.

  4. The physical protection of nuclear material

    International Nuclear Information System (INIS)

    1989-12-01

    A Technical Committee on Physical Protection of Nuclear Material met in April-May 1989 to advise on the need to update the recommendations contained in document INFCIRC/225/Rev.1 and on any changes considered to be necessary. The Technical Committee indicated a number of such changes, reflecting mainly: the international consensus established in respect of the Convention on the Physical Protection of Nuclear Material; the experience gained since 1977; and a wish to give equal treatment to protection against the theft of nuclear material and protection against the sabotage of nuclear facilities. The recommendations presented in this IAEA document reflect a broad consensus among Member States on the requirements which should be met by systems for the physical protection of nuclear materials and facilities. 1 tab

  5. Studies and research concerning BNFP: computerized nuclear materials control and accounting system development evaluation report, FY 1978

    Energy Technology Data Exchange (ETDEWEB)

    Crawford, J M; Ehinger, M H; Joseph, C; Madeen, M L

    1978-10-01

    Development work on a computerized system for nuclear materials control and accounting in a nuclear fuel reprocessing plant is described and evaluated. Hardware and software were installed and tested to demonstrate key measurement, measurement control, and accounting requirements at accountability input/output points using natural uranium. The demonstration included a remote data acquisition system which interfaces process and special instrumentation to a cenral processing unit.

  6. The Physical Protection of Nuclear Material

    International Nuclear Information System (INIS)

    1993-01-01

    Physical protection against the theft or unauthorized diversion of nuclear materials and against the sabotage of nuclear facilities by individuals or groups has long been a matter of national and international concern. Although responsibility for establishing and operating a comprehensive physical protection system for nuclear materials and facilities within a State rests entirely with the Government of that State, it is not a matter of indifference to other States whether and to what extent that responsibility is fulfilled. Physical protection has therefore become a matter of international concern and co-operation. The need for international cooperation becomes evident in situations where the effectiveness of physical protection in one State depends on the taking by other States also of adequate measures to deter or defeat hostile actions against nuclear facilities and materials, particularly when such materials are transported across national frontiers

  7. The Physical Protection of Nuclear Material

    International Nuclear Information System (INIS)

    1993-09-01

    Physical protection against the theft or unauthorized diversion of nuclear materials and against the sabotage of nuclear facilities by individuals or groups has long been a matter of national and international concern. Although responsibility for establishing and operating a comprehensive physical protection system for nuclear materials and facilities within a State rests entirely with the Government of that State, it is not a matter of indifference to other States whether and to what extent that responsibility is fulfilled. Physical protection has therefore become a matter of international concern and co-operation. The need for international cooperation becomes evident in situations where the effectiveness of physical protection in one State depends on the taking by other States also of adequate measures to deter or defeat hostile actions against nuclear facilities and materials, particularly when such materials are transported across national frontiers [es

  8. The Physical Protection of Nuclear Material

    International Nuclear Information System (INIS)

    1993-09-01

    Physical protection against the theft or unauthorized diversion of nuclear materials and against the sabotage of nuclear facilities by individuals or groups has long been a matter of national and international concern. Although responsibility for establishing and operating a comprehensive physical protection system for nuclear materials and facilities within a State rests entirely with the Government of that State, it is not a matter of indifference to other States whether and to what extent that responsibility is fulfilled. Physical protection has therefore become a matter of international concern and co-operation. The need for international cooperation becomes evident in situations where the effectiveness of physical protection in one State depends on the taking by other States also of adequate measures to deter or defeat hostile actions against nuclear facilities and materials, particularly when such materials are transported across national frontiers [fr

  9. The Physical Protection of Nuclear Material

    International Nuclear Information System (INIS)

    1993-09-01

    Physical protection against the theft or unauthorized diversion of nuclear materials and against the sabotage of nuclear facilities by individuals or groups has long been a matter of national and international concern. Although responsibility for establishing and operating a comprehensive physical protection system for nuclear materials and facilities within a State rests entirely with the Government of that State, it is not a matter of indifference to other States whether and to what extent that responsibility is fulfilled. Physical protection has therefore become a matter of international concern and co-operation. The need for international cooperation becomes evident in situations where the effectiveness of physical protection in one State depends on the taking by other States also of adequate measures to deter or defeat hostile actions against nuclear facilities and materials, particularly when such materials are transported across national frontiers

  10. Physical protection of radioactive material in transport

    International Nuclear Information System (INIS)

    1975-01-01

    Safety in the transport of radioactive material is ensured by enclosing the material, when necessary, in packaging which prevents its dispersal and which absorbs to any adequate extent any radiation emitted by the material. Transport workers, the general public and the environment are thus protected against the harmful effects of the radioactive material. The packaging also serves the purpose of protecting its contents against the effects of rough handling and mishaps under normal transport conditions, and against the severe stresses and high temperatures that could be encountered in accidents accompanied by fires. If the radioactive material is also fissile, special design features are incorporated to prevent any possibility of criticality under normal transport conditions and in accidents. The safe transport requirements are designed to afford protection against unintentional opening of packages in normal handling and transport conditions and against damage in severe accident conditions; whereas the physical protection requirements are designed to prevent intentional opening of packages and deliberate damage. This clearly illustrates the difference in philosophical approach underlying the requirements for safe transport and for physical protection during transport. This difference in approach is, perhaps, most easily seen in the differing requirements for marking of consignments. While safety considerations dictate that packages be clearly labelled, physical protection considerations urge restraint in the use of special labels. Careful consideration must be given to such differences in approach in any attempt to harmonize the safety and physical protection aspects of transport. (author)

  11. Computerized tomography

    International Nuclear Information System (INIS)

    Rubashov, I.B.

    1985-01-01

    Operating principle is described for the devices of computerized tomography used in medicine for diagnosis of brain diseases. Computerized tomography is considered as a part of computerized diagnosis, as a part of information science. It is shown that computerized tomography is a real existed field of investigations in medicine and industrial production

  12. Method of manufacturing neutron protection materials

    Energy Technology Data Exchange (ETDEWEB)

    Kakibana, Hidetake; Okamoto, Masazane; Fujii, Yasuhiko; Koguchi, Noboru; Takesute, Morito; Miyamatsu, Tokuhisa

    1985-06-22

    To obtain protection materials easily moldable, flexible and capable of minimizing the workers' neutron exposure dose, a fine fiberous assembly is prepared by dispersing compounds of atoms having neutron absorbing performance such as Li or B, for example, finely powderous compounds of LiF or /sup 6/LiF into a solution of spinnable polymer, particularly, polyolefin polymer such as polyethylene in CH/sub 2/Cl and then flash spinning them. The fine fibers are fabricated into mat-like material, blankets, cloths and the likes for use in neutron exposure protection. In the case of neutron irradiation therapy, protection materials of reduced weight, flexible and giving preferred contact with human body can be obtained with ease for protecting the regions other than the lesion area.

  13. Neutron protection material and neutron protection devices made of such material

    International Nuclear Information System (INIS)

    Ries, W.

    1984-01-01

    This is concerned with a neutron protection material made of thermoplastic or thermosetting plastic from high molecule hydrocarbon compounds with particularly high hydrogen and carbon contents as braking or shielding material (moderator) for fast neutrons. The plastic can contain boron for absorbing low energy neutrons. The material is used to manufacture foil, plates, pipes, shielding walls, components, bodies for radiation protection equipment, devices and plant and for neutron protection clothes. (orig./HP) [de

  14. Advanced physical protection systems for nuclear materials

    International Nuclear Information System (INIS)

    Jones, O.E.

    1975-10-01

    Because of the increasing incidence of terrorism, there is growing concern that nuclear materials and facilities need improved physical protection against theft, diversion, or sabotage. Physical protection systems for facilities or transportation which have balanced effectiveness include information systems, access denial systems, adequate and timely response, recovery capability, and use denial methods for despoiling special nuclear materials (SNM). The role of these elements in reducing societal risk is described; however, it is noted that, similar to nuclear war, the absolute risks of nuclear theft and sabotage are basically unquantifiable. Sandia Laboratories has a major Energy Research and Development Administration (ERDA) role in developing advanced physical protection systems for improving the security of both SNM and facilities. These activities are surveyed. A computer simulation model is being developed to assess the cost-effectiveness of alternative physical protection systems under various levels of threat. Improved physical protection equipment such as perimeter and interior alarms, secure portals, and fixed and remotely-activated barriers is being developed and tested. In addition, complete prototype protection systems are being developed for representative nuclear facilities. An example is shown for a plutonium storage vault. The ERDA safe-secure transportation system for highway shipments of all significant quantities of government-owned SNM is described. Adversary simulation as a tool for testing and evaluating physical protection systems is discussed. A list of measures is given for assessing overall physical protection system performance. (auth)

  15. Advanced physical protection systems for nuclear materials

    International Nuclear Information System (INIS)

    Jones, O.E.

    1976-01-01

    Because of the increasing incidence of terrorism, there is growing concern that nuclear materials and facilities need improved physical protection against theft, diversion, or sabotage. Physical protection systems for facilities or transportation which have balanced effectiveness include information systems, access denial systems, adequate and timely response, recovery capability, and use denial methods for despoiling special nuclear materials (SNM). The role of these elements in reducing societal risk is described; however, it is noted that, similar to nuclear war, the absolute risks of nuclear theft and sabotage are basically unquantifiable. Sandia Laboratories has a major US Energy Research and Development Administration (ERDA) role in developing advanced physical protection systems for improving the security of both SNM and facilities. These activities are surveyed in this paper. A computer simulation model is being developed to assess the cost-effectiveness of alternative physical protection systems under various levels of threat. Improved physical protection equipment such as perimeter and interior alarms, secure portals, and fixed and remotely activated barriers is being developed and tested. In addition, complete prototype protection systems are being developed for representative nuclear facilities. An example is shown for a plutonium storage vault. The ERDA safe-secure transportation system for highway shipments of all significant quantities of government-owned SNM is described. Adversary simulation as a tool for testing and evaluating physical protection systems is discussed. Finally, a list of measures is given for assessing overall physical protection system performance. (author)

  16. Protecting cognition from aging and Alzheimer's disease: a computerized cognitive training combined with reminiscence therapy.

    Science.gov (United States)

    Barban, Francesco; Annicchiarico, Roberta; Pantelopoulos, Stelios; Federici, Alessia; Perri, Roberta; Fadda, Lucia; Carlesimo, Giovanni Augusto; Ricci, Claudia; Giuli, Simone; Scalici, Francesco; Turchetta, Chiara Stella; Adriano, Fulvia; Lombardi, Maria Giovanna; Zaccarelli, Chiara; Cirillo, Giulio; Passuti, Simone; Mattarelli, Paolo; Lymperopoulou, Olga; Sakka, Paraskevi; Ntanasi, Eva; Moliner, Reyes; Garcia-Palacios, Azucena; Caltagirone, Carlo

    2016-04-01

    The aim of this paper was to assess the efficacy of process-based cognitive training (pb-CT) combined with reminiscence therapy (RT) in patients with mild Alzheimer's disease (mAD) and mild cognitive impairment (MCI) and in healthy elderly (HE) subjects. This multicenter, randomized, controlled trial involved 348 participants with mAD, MCI, and HE from four European countries. Participants were randomly assigned to two arms of a crossover design: those in arm A underwent 3 months of computerized pb-CT for memory and executive functions combined with RT and 3 months of rest; those in arm B underwent the reverse. The primary outcome was the effect of the training on memory and executive functions performance. The secondary outcome was the effect of the training on functional abilities in mAD assessed with the instrumental activities of daily living. We found a significant effect of the training for memory in all three groups on delayed recall of the Rey Auditory Verbal Learning Test and for executive functions in HE on the phonological fluency test. MCI and HE participants maintained these effects at follow-up. MCI and mAD participants also showed a significant effect of the training on the Mini-mental state examination scale. Participants with mAD showed more stable instrumental activities of daily living during the training versus the rest period. Our results corroborate the positive effect of pb-CT and its maintenance primarily on memory in HE and MCI participants that did not seem to be potentiated by RT. Moreover, our results are very promising for the mAD participants. Copyright © 2015 John Wiley & Sons, Ltd.

  17. CFES--California Fire Economics Simulator: A Computerized System for Wildland Fire Protection Planning

    Science.gov (United States)

    Jeremy S. Fried; J. Keith Gilless; Robert E. Martin

    1987-01-01

    The University of California's Department of Forestry and Resource Management, under contract with the California Department of Forestry and Fire Protection, has developed and released the first version of the California Fire Economics Simulator (CFES). The current release is adapted from the Initial Action Assessment component of the USFS's National Fire...

  18. Safety assessment of computerized control and protection systems. Report of a technical committee meeting held in Vienna, 12-16 October 1992

    International Nuclear Information System (INIS)

    1994-12-01

    In developing the views expressed in this document, papers were presented by delegates from Member States. A total of 6 papers were presented in all on topics ranging from applications of computerized control and protection systems in older plants and in new advanced reactors to methods for improving software reliability. In addition two informal presentations were provided by a vendor and a licensing authority. These presentations provided valuable insights into the application of computerized control and protection systems and into the concern of software reliability with proposals for diverse 'backup' systems of different types. This was supplemented by utility and vendor presentations on system designs. Following the presentations, three working groups were formed to produce their views on the licensing of software based safety systems on reliability models and techniques for assessment of computerized safety systems, and on systems considered for computerized upgrading (need, criteria, approach, pitfalls and benefits). This document represents these collected views with the papers presented attached as an annex. Refs, figs and tabs

  19. The physical protection of nuclear material

    Energy Technology Data Exchange (ETDEWEB)

    1993-09-01

    Technical Committee met 21-25 June 1993 to consider changes to INFCIRC/225/Rev.2. The revised document, INFCIRC/225/Rev.3, reflects the Technical Committee recommendations for changes to the text as well as other modifications determined necessary to advance the consistency of the Categorization Table in INFCIRC/225/Rev.2 with the categorization table contained in The Convention of the Physical Protection of Nuclear Material and to reflect additional improvements presented by the experts. The recommendations presented in this IAEA document reflect a broad consensus among Member States on the requirements which should be met by systems for the physical protection of nuclear materials and facilities. It is hoped that they will provide helpful guidance for Member States.

  20. The physical protection of nuclear material

    International Nuclear Information System (INIS)

    1993-09-01

    Technical Committee met 21-25 June 1993 to consider changes to INFCIRC/225/Rev.2. The revised document, INFCIRC/225/Rev.3, reflects the Technical Committee recommendations for changes to the text as well as other modifications determined necessary to advance the consistency of the Categorization Table in INFCIRC/225/Rev.2 with the categorization table contained in The Convention of the Physical Protection of Nuclear Material and to reflect additional improvements presented by the experts. The recommendations presented in this IAEA document reflect a broad consensus among Member States on the requirements which should be met by systems for the physical protection of nuclear materials and facilities. It is hoped that they will provide helpful guidance for Member States

  1. Structural adhesives for missile external protection material

    Science.gov (United States)

    Banta, F. L.; Garzolini, J. A.

    1981-07-01

    Two basic rubber materials are examined as possible external substrate protection materials (EPM) for missiles. The analysis provided a data base for selection of the optimum adhesives which are compatible with the substrate, loads applied and predicted bondline temperatures. Under the test conditions, EA934/NA was found to be the optimum adhesive to bond VAMAC 2273 and/or NBR/EPDM 9969A to aluminum substrate. The optimum adhesive for composite structures was EA956. Both of these adhesives are two-part epoxy systems with a pot life of approximately two hours. Further research is suggested on field repair criteria, nuclear hardness and survivability effects on bondline, and ageing effects.

  2. Ultrasonic tests on materials with protective coatings

    International Nuclear Information System (INIS)

    Whaley, H.L.

    1977-01-01

    Protective coatings are applied to some nuclear components such as reactor vessels to inhibit surface corrosion. Since in-service ultrasonic inspection is required for such components, a study was performed to determine whether the use of protective coatings can affect ultrasonic tests. Two 2 in. thick steel plates were uniformly machined, sandblasted, and used as bases for two types of protective coatings. The type and thickness of the coating and the presence of contamination, such as fingerprints or mild oxidation under the paint, were the independent variables associated with the coating. Tests were run to determine the effects of the protective coatings on ultrasonic tests conducted on the steel plates. Significant variations in ultrasonic test sensitivity occurred as a function of the type and thickness of protective coating, couplant (material that conducts the ultrasound from the transducer into the test part, normally water or some type of oil), transducer wear plate, and ultrasonic test frequency. Ultrasonic tests can be strongly affected by a protective coating on the component to be inspected. As compared to the test sensitivity for an uncoated reference sample, the sensitivity may be dramatically shifted up or down on the coated surface. In certain coating thickness ranges, the sensitivity can fluctuate widely with small changes in coating thickness. If a coating is chosen properly, however, components with protective coatings can be tested ultrasonically with valid results. These results are for the case of ultrasonic input on the coated surface. It is not expected that an ultrasonic test conducted from the front surface would be appreciably affected by a coating on the rear surface

  3. Materials corrosion and protection at high temperatures

    International Nuclear Information System (INIS)

    Balbaud, F.; Desgranges, Clara; Martinelli, Laure; Rouillard, Fabien; Duhamel, Cecile; Marchetti, Loic; Perrin, Stephane; Molins, Regine; Chevalier, S.; Heintz, O.; David, N.; Fiorani, J.M.; Vilasi, M.; Wouters, Y.; Galerie, A.; Mangelinck, D.; Viguier, B.; Monceau, D.; Soustelle, M.; Pijolat, M.; Favergeon, J.; Brancherie, D.; Moulin, G.; Dawi, K.; Wolski, K.; Barnier, V.; Rebillat, F.; Lavigne, O.; Brossard, J.M.; Ropital, F.; Mougin, J.

    2011-01-01

    This book was made from the lectures given in 2010 at the thematic school on 'materials corrosion and protection at high temperatures'. It gathers the contributions from scientists and engineers coming from various communities and presents a state-of-the-art of the scientific and technological developments concerning the behaviour of materials at high temperature, in aggressive environments and in various domains (aerospace, nuclear, energy valorization, and chemical industries). It supplies pedagogical tools to grasp high temperature corrosion thanks to the understanding of oxidation mechanisms. It proposes some protection solutions for materials and structures. Content: 1 - corrosion costs; macro-economical and metallurgical approach; 2 - basic concepts of thermo-chemistry; 3 - introduction to the Calphad (calculation of phase diagrams) method; 4 - use of the thermodynamic tool: application to pack-cementation; 5 - elements of crystallography and of real solids description; 6 - diffusion in solids; 7 - notions of mechanics inside crystals; 8 - high temperature corrosion: phenomena, models, simulations; 9 - pseudo-stationary regime in heterogeneous kinetics; 10 - nucleation, growth and kinetic models; 11 - test experiments in heterogeneous kinetics; 12 - mechanical aspects of metal/oxide systems; 13 - coupling phenomena in high temperature oxidation; 14 - other corrosion types; 15 - methods of oxidized surfaces analysis at micro- and nano-scales; 16 - use of SIMS in the study of high temperature corrosion of metals and alloys; 17 - oxidation of ceramics and of ceramic matrix composite materials; 18 - protective coatings against corrosion and oxidation; 19 - high temperature corrosion in the 4. generation of nuclear reactor systems; 20 - heat exchangers corrosion in municipal waste energy valorization facilities; 21 - high temperature corrosion in oil refining and petrochemistry; 22 - high temperature corrosion in new energies industry. (J.S.)

  4. Computerization of the nuclear material accounting system for safeguards purposes at nuclear power plants with WWER-440 reactors

    International Nuclear Information System (INIS)

    Antonov, V.P.; Konnov, Yu.I.; Semenets, A.N.

    1983-01-01

    The paper sets forth the basic principles underlying nuclear material accounting at nuclear power plants with WWER-440 reactors. It briefly describes the general structure and individual units in a program for computerized accounting. The use of this program is illustrated by the actual accounting data from the fifth unit of the Novovoronezh nuclear power station. The NUMIS program seems to be of interest both for the purposes of IAEA safeguards and for nuclear power plant operators in countries where power plants with WWER-440 reactors subject to IAEA safeguards are either in operation or under construction. The research in question was conducted initially under an IAEA research contract; the system is now being developed further and tested under the IAEA-USSR technical and scientific co-operation programme on safeguards. (author)

  5. Femtosecond laser interaction with protection materials

    Energy Technology Data Exchange (ETDEWEB)

    Martin, S.; Krueger, J.; Hertwig, A.; Fiedler, A.; Kautek, W

    2003-03-15

    Textile, aluminium and polyethylene used as components in laser protection curtains were investigated with respect to their ablation behaviour. Employing 33-fs pulses (800 nm wavelength, 1 kHz repetition rate), ex situ geometrical measurements of the ablation cavities and in situ acoustic investigations with a microphone were performed to determine the ablation thresholds in the single- and multi-pulse cases. The acoustical method proved advantageous for complex surface morphologies and/or single laser pulse interactions. Incubation phenomena can be observed for all the materials studied. Technically relevant multi-pulse ablation thresholds are presented and are compared with the single-pulse (1-on-1) irradiation.

  6. KrasMAS: Implementation of a nuclear material computerized accounting system at the Mining and Chemical Combine through the Russian/US cooperative MPC and A program

    International Nuclear Information System (INIS)

    Dorofeev, K.V.; Zhidkov, V.V.; Martinez, B.J.; Perry, R.T.; Scott, S.C.

    1998-01-01

    The Russian/US Mining and Chemical Combine (Gorno-Kimichesky Kombinat, GKhK, also referred to as Krasnoyarsk-26) Material Protection, Control and Accounting (MPC and A) project was initiated in June 1996. A critical component of the ongoing cooperative MPC and A enhancements at the GKhK is the implementation of a computerized nuclear material control and accountability (MC and A) system. This system must meet the MC and A requirements of the GKhK by integrating the information generated by numerous existing and new MC and A components in place at the GKhK (e.g., scales, bar-code equipment, NDA measurement systems). During the first phase of this effort, the GKhK adapted CoreMAS (developed at Los Alamos National Laboratory) for use in the PuO 2 storage facility. This included formulation of Web-based user interfaces for plant personnel, Russification of the existing user interface, and at the functional level, modification of the CoreMAS stored procedures. The modified system is referred to as KrasMAS and builds upon completed work on CoreMAS. Ongoing efforts include adding GKhK specific report forms and expanding the functionality of the system for implementation at the radiochemical processing and reactor plants of the GKhK. Collaborations with other Russian facilities for appropriate parts of these efforts will be pursued

  7. Sprayable Phase Change Coating Thermal Protection Material

    Science.gov (United States)

    Richardson, Rod W.; Hayes, Paul W.; Kaul, Raj

    2005-01-01

    NASA has expressed a need for reusable, environmentally friendly, phase change coating that is capable of withstanding the heat loads that have historically required an ablative thermal insulation. The Space Shuttle Program currently relies on ablative materials for thermal protection. The problem with an ablative insulation is that, by design, the material ablates away, in fulfilling its function of cooling the underlying substrate, thus preventing the insulation from being reused from flight to flight. The present generation of environmentally friendly, sprayable, ablative thermal insulation (MCC-l); currently use on the Space Shuttle SRBs, is very close to being a reusable insulation system. In actual flight conditions, as confirmed by the post-flight inspections of the SRBs, very little of the material ablates. Multi-flight thermal insulation use has not been qualified for the Space Shuttle. The gap that would have to be overcome in order to implement a reusable Phase Change Coating (PCC) is not unmanageable. PCC could be applied robotically with a spray process utilizing phase change material as filler to yield material of even higher strength and reliability as compared to MCC-1. The PCC filled coatings have also demonstrated potential as cryogenic thermal coatings. In experimental thermal tests, a thin application of PCC has provided the same thermal protection as a much thicker and heavier application of a traditional ablative thermal insulation. In addition, tests have shown that the structural integrity of the coating has been maintained and phase change performance after several aero-thermal cycles was not affected. Experimental tests have also shown that, unlike traditional ablative thermal insulations, PCC would not require an environmental seal coat, which has historically been required to prevent moisture absorption by the thermal insulation, prevent environmental degradation, and to improve the optical and aerodynamic properties. In order to reduce

  8. Emergency respiratory protection with common materials

    International Nuclear Information System (INIS)

    Cooper, D.W.; Hinds, W.C.; Price, J.M.

    1983-01-01

    Certain unexpected accidents, such as fires, explosions, chemical spills, or nuclear reactor malfunctions, can lead to the exposure of workers and the public to toxic gases, vapors, and aerosols. The efficacy of readily available materials, such as cotton fabric, toweling, and a single-use respirator, for providing emergency respiratory protection was evaluated by determining the filtration efficiency as a function of particle size over the range of 0.4 to 5 μm diameter and performance against a reactive water soluble (I 2 ) and unreactive vapor (CH 3 I). At a reasonable design face velocity (1.5 cm/s), the respirator mask used at double thickness could reduce particle concentrations a factor of 30 or more throughout the particle range tested, and a wetted towel four layers thick could provide a factor of five. Dry fabrics were ineffective in removing iodine vapor, but wetted sheeting or toweling reduced concentration by a factor of ten or more under design conditions, 1.5 cm/s face velocity and 50 Pa pressure drop (0.2 inches of water). The fabrics provided a statistically insignificant reduction in methyliodide. In practice, any leaks around the seal to the face would lessen the protection offered by such materials. The effectiveness factor approach proved useful in comparing filter performance under different conditions

  9. X-ray computerized tomography used in non-destructive testing of aerospace materials

    International Nuclear Information System (INIS)

    Maschio, Celio; Alencar Lotufo, Roberto de

    1996-01-01

    This work reports the development of nondestructive testing procedures for aerospace materials, using a medical tomograph (80 to 150 KeV), associated to the image digital processing techniques through the KHOROS system

  10. Advanced materials for thermal protection system

    Science.gov (United States)

    Heng, Sangvavann; Sherman, Andrew J.

    1996-03-01

    Reticulated open-cell ceramic foams (both vitreous carbon and silicon carbide) and ceramic composites (SiC-based, both monolithic and fiber-reinforced) were evaluated as candidate materials for use in a heat shield sandwich panel design as an advanced thermal protection system (TPS) for unmanned single-use hypersonic reentry vehicles. These materials were fabricated by chemical vapor deposition/infiltration (CVD/CVI) and evaluated extensively for their mechanical, thermal, and erosion/ablation performance. In the TPS, the ceramic foams were used as a structural core providing thermal insulation and mechanical load distribution, while the ceramic composites were used as facesheets providing resistance to aerodynamic, shear, and erosive forces. Tensile, compressive, and shear strength, elastic and shear modulus, fracture toughness, Poisson's ratio, and thermal conductivity were measured for the ceramic foams, while arcjet testing was conducted on the ceramic composites at heat flux levels up to 5.90 MW/m2 (520 Btu/ft2ṡsec). Two prototype test articles were fabricated and subjected to arcjet testing at heat flux levels of 1.70-3.40 MW/m2 (150-300 Btu/ft2ṡsec) under simulated reentry trajectories.

  11. Method of manufacturing neutron protecting materials

    Energy Technology Data Exchange (ETDEWEB)

    Kakibana, Hidetake; Okamoto, Masazane; Fujii, Yasuhiko; Koguchi, Noboru; Takesute, Morihito; Miyamatsu, Tokuhisa

    1985-06-03

    Purpose: To manufacture neutron protecting materials which are highly flexible and can be shaped with ease at a good workability. Method: In this invention, natural lithium, natural boron such as Li-6 or B-10 or enriched isotope thereof with a great neutron absorption cross section is fixed to fibers. As a specific example, lumps of copolymer fibers are fabricated into weave sheets in a carding machine and applied with needle punching to prepare felt-like products. They are conditioned to OH or H type, which are respectively immersed in saturated aqueous boric acid or 1M-aqueous solution of lithium hydroxide and then dewatered and dried. As a result, boric acid type anion exchange fibers and lithium type cation exchange fibers can be obtained from the former and the latter respectively. In this way, blankets or cloths which are light in weight, flexible and have high neutron absorbing performance can be shaped. They are also in good fitting contact to a human body. (Kamimura, M.).

  12. The convention on the physical protection of nuclear material

    International Nuclear Information System (INIS)

    1980-05-01

    This document contains the full text of a convention to facilitate the safe transfer of nuclear material, and to insure the physical protection of nuclear material in domestic use, storage, and transport. Two annexes are included, which establish categories of nuclear materials and levels of physical protection to be applied in international transport

  13. US/Russian program in materials protection, control and accounting at the RRC Kurchatov Institute: 1997--1998

    International Nuclear Information System (INIS)

    Sukhoruchkin, V.; Rumyantsev, A.; Shmelev, V.

    1998-01-01

    Six US Department of Energy Laboratories are carrying out a program of cooperation with the Russian Research Center Kurchatov Institute to improve nuclear material protection, control and accounting (MPC and A) at Kurchatov. In 1997--1998 the primary thrust of this program has been directed to Building 106, which houses a number of test reactors and critical facilities. Substantial improvements in physical protection, upgrades in the physical inventory taking procedures, installation of equipment for the computerized materials accounting system, and installation of nuclear material portal monitors and neutron-based measurement equipment are being carried out at this facility. Software for the computerized accounting system, named KI-MACS, has been developed at Kurchatov and the system has been fully integrated with the bar code printing and reading equipment, electronic scales, and nondestructive assay equipment provided under this program. Additional 1997--1998 activities at Kurchatov include continuation of a tamper indicating device program, vulnerability assessments of several facilities, hosting of a Russian-American Workshop on Fissile Material Control and Accountability at Critical Facilities, and the development of accounting procedures for transfers of nuclear materials between material balance areas

  14. Investigating the Use of a Protective Coating Material as an ...

    African Journals Online (AJOL)

    Petroleum wax is known to provide ozone protection to natural rubber under static deformation while a combination of chemical antiozonant and wax is normally used for ozone protection under dynamic conditions. The work described in this paper, aims at investigating the effectiveness of a coating material in protecting a ...

  15. US/Russian laboratory-to-laboratory program in materials protection, control and accounting at the RRC Kurchatov Institute

    International Nuclear Information System (INIS)

    Sukhoruchkin, V.; Roumiansev, A.; Shmelev, V.

    1996-01-01

    Six US DOE Laboratories are carrying out a program of cooperation with the Russian Research Center Kurchatov Institute (RRC KI) to improve the capabilities and facilities in nuclear material protection, control, and accounting (MPC ampersand A). In 1995, the primary emphasis of this program was the implementation of improved physical protection at a demonstration building at RRC KI, and the upgrading of the computerized MC ampersand A system, diagnostic instrumentation, and physical inventory procedures at a critical assembly within this building. Work continues in 1996 at the demonstration building but now also has begun at the two Kurchatov buildings which constitute the Central Storage Facility (CSF). At this facility, there will be upgrades in the physical inventory taking procedures, a test and evaluation of gamma-ray isotopic measurements, evaluations of nuclear material portal monitors and neutron-based measurement equipment as well as development of an improved computerized materials accounting system, implementation of bar code printing and reading equipment, development of tamper indicating device program, and substantial improvements in physical protection. Also, vulnerability assessments begun in 1995 are being extended to additional high priority facilities at Kurchatov

  16. Computerized versus hand-scored health literacy tools: a comparison of Simple Measure of Gobbledygook (SMOG) and Flesch-Kincaid in printed patient education materials.

    Science.gov (United States)

    Grabeel, Kelsey Leonard; Russomanno, Jennifer; Oelschlegel, Sandy; Tester, Emily; Heidel, Robert Eric

    2018-01-01

    The research compared and contrasted hand-scoring and computerized methods of evaluating the grade level of patient education materials that are distributed at an academic medical center in east Tennessee and sought to determine if these materials adhered to the American Medical Association's (AMA's) recommended reading level of sixth grade. Librarians at an academic medical center located in the heart of Appalachian Tennessee initiated the assessment of 150 of the most used printed patient education materials. Based on the Flesch-Kincaid (F-K) scoring rubric, 2 of the 150 documents were excluded from statistical comparisons due to the absence of text (images only). Researchers assessed the remaining 148 documents using the hand-scored Simple Measure of Gobbledygook (SMOG) method and the computerized F-K grade level method. For SMOG, 3 independent reviewers hand-scored each of the 150 documents. For F-K, documents were analyzed using Microsoft Word. Reading grade levels scores were entered into a database for statistical analysis. Inter-rater reliability was calculated using intra-class correlation coefficients (ICC). Paired t -tests were used to compare readability means. Acceptable inter-rater reliability was found for SMOG (ICC=0.95). For the 148 documents assessed, SMOG produced a significantly higher mean reading grade level (M=9.6, SD=1.3) than F-K (M=6.5, SD=1.3; p SMOG method of assessment, 147 of the 148 documents (99.3%) scored above the AMA's recommended reading level of sixth grade. Computerized health literacy assessment tools, used by many national patient education material providers, might not be representative of the actual reading grade levels of patient education materials. This is problematic in regions like Appalachia because materials may not be comprehensible to the area's low-literacy patients. Medical librarians have the potential to advance their role in patient education to better serve their patient populations.

  17. Manual of respiratory protection against airborne radioactive materials

    Energy Technology Data Exchange (ETDEWEB)

    Caplin, J.L.; Held, B.J.; Catlin, R.J.

    1976-10-01

    The manual supplements Regulatory Guide 8.15, ''Acceptable Programs for Respiratory Protection''. It provides broad guidance for the planned use of respirators to protect individuals from airborne radioactive materials that might be encountered during certain operations. The guidance is intended for use by management in establishing and supervising programs and by operating personnel in implementing programs. Guidance is primarily directed to the use of respirators to prevent the inhalation of airborne radioactive materials. Protection against other modes of intake (e.g., absorption, swallowing, wound injection) is, in general, not covered nor is the use of protective equipment for head, eye, or skin protection.

  18. Manual of respiratory protection against airborne radioactive materials

    International Nuclear Information System (INIS)

    Caplin, J.L.; Held, B.J.; Catlin, R.J.

    1976-10-01

    The manual supplements Regulatory Guide 8.15, ''Acceptable Programs for Respiratory Protection''. It provides broad guidance for the planned use of respirators to protect individuals from airborne radioactive materials that might be encountered during certain operations. The guidance is intended for use by management in establishing and supervising programs and by operating personnel in implementing programs. Guidance is primarily directed to the use of respirators to prevent the inhalation of airborne radioactive materials. Protection against other modes of intake (e.g., absorption, swallowing, wound injection) is, in general, not covered nor is the use of protective equipment for head, eye, or skin protection

  19. The system of physical protection of nuclear materials in the Republic of Belarus: problems and solutions

    International Nuclear Information System (INIS)

    Piotukh, V.

    2002-01-01

    Full text: It is a matter of common knowledge, that the responsibility for establishing and operating a comprehensive physical protection system for nuclear material and facilities within a state shall rest entirely with the Government of that state. In Belarus all nuclear materials, including HEU, are located at the Center of Nuclear Technologies of the Belarus National Academy of Sciences 'Sosny'. Through regulatory resolution on measures for physical protection of nuclear materials issued by the Council of Ministers of the Republic of Belarus in 1993, the committee for Supervision of Industrial and Nuclear Safety (Promatomnadzor) was appointed as the authority responsible for ensuring physical protection of nuclear materials and facilities and was tasked to develop and approve relevant normative documents. In 1994 Promatomnadzor issued the order on ensuring physical protection of nuclear materials during use, storage and transportation that was in line with then relevant IAEA recommendations. Since September 2001 Promatomnadzor has been a department of the Ministry for Emergencies of the Republic of Belarus. The system of physical protection at 'Sosny' includes elements of the 'old' system set up in 1984, and the 'new' one installed in 1996 as a result of a multilateral co-operative effort between Belarus, Sweden, Japan and USA. The main technical components of the system are: detection system including magnetic, microwave and infrared sensors; video-surveillance system; system of access delay including electronic blocking devices; system of authorized access including magnetic cards; system of computerized control over all components and communication system. Discussions between potential donor states are taking place regarding various security upgrades, particularly to the protected area where main security sensitive buildings are located. In 2000 Promatomnadzor requested an international physical protection advisory service (IPPAS) mission from the IAEA. The

  20. National practices in physical protection of nuclear materials. Regulatory basis

    International Nuclear Information System (INIS)

    Goltsov, V.Y.

    2002-01-01

    Full text: The Federal law 'On The Use Of Atomic Energy' containing the section on physical protection of nuclear materials and nuclear facilities was issued in 1995 in Russian Federation. This document became the first federal level document regulating the general requirements to physical protection (PP). The federal PP rules developed on the base of this law by Minatom of Russia and other federal bodies of the Russian Federation were put in force by the government of Russia in 1997. The requirements of the convention on physical protection of nuclear materials (INFCIRC 274) and the modern IAEA recommendations (INFCIRC/225/Rev.4) are taken into account in the PP rules. Besides, while developing the PP rules the other countries' experience in this sphere has been studied and taken into account. The PP rules are action-obligatory for all juridical persons dealing with nuclear activity and also for those who are coordinating and monitoring this activity. Nuclear activity without physical protection ensured in accordance with PP rules requirements is prohibited. The requirements of PP Rules are stronger than the IAEA recommendations. The PP rules are establishing: physical protection objectives; federal executive bodies and organizations functions an implementation of physical protection; categorization of nuclear materials; requirements for nuclear materials physical protection as during use and storage as during transportation; main goals of state supervision and ministry level control for physical protection; notification order about the facts of unauthorized actions regarding nuclear materials and facilities. Besides the above mentioned documents, there were put in force president decrees, federal laws and regulations in the field of: counteraction to nuclear terrorism; interactions in physical protection systems; military and ministerial on-site guard activities; information protection. By the initiative of Minatom of Russia the corrections were put into the

  1. Upgrading nuclear material protection, control and accounting in Russia

    International Nuclear Information System (INIS)

    Caravelli, Jack; Behan, Chris; Fishbone, Les

    2001-01-01

    focus on implementation of the upgrades at the Russian nuclear sites, and on certain national or infrastructure areas: Regulatory Development; Training; Physical Inventory Taking and Material Balance; Computerized Material Accounting and Control; Bar Coding; Nondestructive Assay Measurements; Bulk (Weight and Volume) Measurements; Tamper-Indicating Devices; Nuclear Material Pedestrian Portal Monitors; Access Control; Building Hardening; Federal Information System. III. Results - To date, after more than six years of work, significant progress has been achieved in a variety of ways. For example: Security improvements are underway on some 750 metric tons of highly enriched uranium and plutonium at many sites under the supervision of Minatom, Gosatomnadzor, the Russian Navy, and other Russian entities. Among these are an ingenious concrete-block delay system for plutonium storage at the Mayak Production Association and an inventory strategy at the Institute of Physics and Power Engineering that, by fostering the consolidation of items, reduces the time required to inventory them. About 850 kg of HEU have been converted to low-enriched uranium in a project that is now active at two processing sites; More than 1000 Russian MPC and A staff have undergone training at the Russian Methodological and Training Center; and Hardening of more than 90 transport vehicles has enhanced transport security. We will illustrate this progress in the paper by describing the MPC and A upgrade work at specific Russian sites. IV. Discussion - During its existence, the MPC and A Program has confronted several problems. They include issues surrounding taxation, exports, travel, assurances, and business practice. Most have been overcome, but sometimes only after long and sustained effort. Positive results have been achieved because of the mutual desire of the United States and Russia to address the need for enhanced nuclear material protection, control and accounting at Russian nuclear sites. Yet

  2. Computerized industrial tomography

    International Nuclear Information System (INIS)

    Ashraf, M.M.

    1999-01-01

    Computerized Tomographic (CT) has been used for a number of applications in the field of medicine and industry. For the last couple of years, the technique has been applied for the material characterization and detection of defects and flaws inside the industrial components of nuclear, aerospace and missile industries. A CT scanner of first generation was developed at the institute. The scanner has been used to demonstrate couple of applications of CT in the field of non destructive testing of materials. The data acquired by placing the test objects at various angles and scanning the object through a source detector assembly has been processed on a Pentium computer for image reconstruction using a filtered back projection method. The technique has been developed which can be modified and improved to study various other applications in materials science and a modern computerized tomographic facility can be established. (author)

  3. Summary of physical protection and material accounting

    International Nuclear Information System (INIS)

    Koppel, P.J.

    1977-01-01

    The tremendous growth in safeguards and security requirements for activities involving strategic quantities of high enriched uranium and plutonium has resulted in a wealth of proposed regulations, counter proposals, interim plans, license conditions, and final regulations. This paper reviews the actions taken and indicates their impact on facilities handling special nuclear material

  4. The Physical Protection of Nuclear Material and Nuclear Facilities

    International Nuclear Information System (INIS)

    1999-08-01

    Physical protection against the theft or unauthorized diversion of nuclear materials and against the sabotage of nuclear facilities by individuals or groups has long been a matter of national and international concern. Although responsibility for establishing and operating a comprehensive physical protection system for nuclear materials and facilities within a State rests entirely with the Government of that State, it is not a matter of indifference to other States whether and to what extent that responsibility is fulfilled. Physical protection has therefore become a matter of international concern and co-operation. The need for international co-operation becomes evident in situations where the effectiveness of physical protection in one State depends on the taking by other States also of adequate measures to deter or defeat hostile actions against nuclear facilities and nuclear materials, particularly when such materials are transported across national frontiers

  5. 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

  6. The Physical Protection of Nuclear Material and Nuclear Facilities

    International Nuclear Information System (INIS)

    1999-06-01

    Physical protection against the theft or unauthorized diversion of nuclear materials and against the sabotage of nuclear facilities by individuals or groups has long been a matter of national and international concern. Although responsibility for establishing and operating a comprehensive physical protection system for nuclear materials and facilities within a State rests entirely with the Government of that State, it is not a matter of indifference to other States whether and to what extent that responsibility is fulfilled. Physical protection has therefore become a matter of international concern and co-operation. The need for international co-operation becomes evident in situations where the effectiveness of physical protection in one State depends on the taking by other States also of adequate measures to deter or defeat hostile actions against nuclear facilities and nuclear materials, particularly when such materials are transported across national frontiers [es

  7. Maintenance standards, care and control of the radiation protection material

    International Nuclear Information System (INIS)

    Brasesco, L.

    2004-01-01

    The present protocol in Radiology, Tomography, surgical block and intensive care unit in the Britanic Hospital from Uruguay.Between their topics find care procedures in protective clothes, periodic and control methods, material record,and staff assigned

  8. The Physical Protection of Nuclear Material and Nuclear Facilities

    International Nuclear Information System (INIS)

    1999-06-01

    Physical protection against the theft or unauthorized diversion of nuclear materials and against the sabotage of nuclear facilities by individuals or groups has long been a matter of national and international concern. Although responsibility for establishing and operating a comprehensive physical protection system for nuclear materials and facilities within a State rests entirely with the Government of that State, it is not a matter of indifference to other States whether and to what extent that responsibility is fulfilled. Physical protection has therefore become a matter of international concern and co-operation. The need for international co-operation becomes evident in situations where the effectiveness of physical protection in one State depends on the taking by other States also of adequate measures to deter or defeat hostile actions against nuclear facilities and nuclear materials, particularly when such materials are transported across national frontiers

  9. Computerized tomography

    International Nuclear Information System (INIS)

    1980-01-01

    Improvements in the design of computerized tomographic X-ray equipment are described which lead to improvements in the mechanical properties, speed and size of scanning areas. The method envisages the body being scanned as a two-dimensional matrix of elements arising from a plurality of concentric rings. The concentric centre need not coincide with the axis of rotation. The procedures for rotation of the X-ray beam and detectors around the patient and for translating the measured information into attenuation coefficients for each matrix element of the body are described in detail. Explicit derivations are given for the mathematical formulae used. (U.K.)

  10. Measurement of HTO permeability of materials for protective appliances

    International Nuclear Information System (INIS)

    Yamamoto, H.; Tomooka, M.; Kato, S.; Murata, M.; Kinouchi, N.; Yamamoto, H.

    1992-01-01

    Tritiated water (HTO) vapor permeabilities were measured for plastic and rubber films used for protective appliances (suits, gloves, wrappings, etc.). The measurement data prove that polyehylene and butyl rubbers are materials suitable for HTO protective appliances with their lower permeability. The data also indicate that desiccating protective appliances before reuse is effective for restoring their original resistances to penetrating HTO vapor when they are repeatedly used. (author)

  11. Material surface modification for first wall protection

    International Nuclear Information System (INIS)

    Davis, M.J.

    1979-01-01

    The elements and strategy of a program to develop low Z surfaces for tokamak reactors is described. The development of low Z coated limiters is selected as an interim goal. Candidate materials were selected from the elements: Be, B, Al, Ti, V, C, O, N and their compounds. The effect of low energy erosion on surface morphology is shown for Be, TiC and VBe 12 . The tradeoffs in coating design are described. Stress analysis results for TiB 2 coated POCO graphite limiters for ORNL's ISX-B tokamak are given

  12. Plasma processing of fibre materials for enhanced impact protection

    NARCIS (Netherlands)

    Creyghton, Y.L.M.; Simor, M.

    2009-01-01

    The performance of lightweight impact protective clothing depends on the constituting materials, their assembly in a system and interaction under various dynamic impact conditions. In this paper an overview of options for improved impact protective clothing systems based on a new plasma technology

  13. Utilization of colemanite as a radiation protection material

    International Nuclear Information System (INIS)

    Bayulken, Ahmet; Aksut, Cem

    1986-01-01

    In experiments utilizing neutrons, a good shielding is very important. For developing countries, economics of the protection system is also a very important factor. In this work, a new material for protection blocks is investigated. These blocks are fabricated with colemanite powder in a paraffin wax matrix, and their behaviour as a neutron shield are investigated with a Pu-Be neutron source. (author)

  14. U.S./Russian lab-to-lab materials protection, control and accounting program efforts at the Institute of Inorganic Materials. Revision 1

    International Nuclear Information System (INIS)

    Ruhter, W.D.; Kositsyn, V.; Rudenko, V.; Siskind, B.; Bieber, A.; Hoida, Hiroshi; Augustson, R.; Ehinger, M.; Smith, B.W.

    1996-01-01

    The All-Russian Scientific Research Institute of Inorganic Materials (VNIINM) performs research in nuclear power reactor fuel, spent fuel reprocessing and waste management, materials science of fissionable and reactor structural materials, metallurgy, superconducting materials, and analytical sciences. VNIINM supports the Ministry of Atomic Energy of the Russian Federation (MINATOM) in technologies for fabrication and processing of nuclear fuel. As a participant in the US/Russian Lab-to-Lab nuclear materials protection, control and accounting (MPC and A) program, VNIINM is providing support for measurements of nuclear materials in bulk forms by developing specifications, test and evaluation, certification, and implementation of measurement methods for such materials. In 1996, VNIINM will be working with Brookhaven staff in developing and documenting material control and accounting requirements for nuclear materials in bulk form, Livermore and Los Alamos staff in testing and evaluating gamma-ray spectrometry methods for bulk materials, Los Alamos staff in test and evaluation of neutron-coincidence counting techniques, Oak Ridge staff in accounting of bulk materials with process instrumentation, and Pacific Northwest staff on automating VNIINM's coulometric titration system. In addition, VNIINM will develop a computerized accounting system for nuclear material within VNIINM and their storage facility. The paper will describe the status of this work and anticipated progress in 1996

  15. An integrated approach towards future ballistic neck protection materials selection.

    Science.gov (United States)

    Breeze, John; Helliker, Mark; Carr, Debra J

    2013-05-01

    Ballistic protection for the neck has historically taken the form of collars attached to the ballistic vest (removable or fixed), but other approaches, including the development of prototypes incorporating ballistic material into the collar of an under body armour shirt, are now being investigated. Current neck collars incorporate the same ballistic protective fabrics as the soft armour of the remaining vest, reflecting how ballistic protective performance alone has historically been perceived as the most important property for neck protection. However, the neck has fundamental differences from the thorax in terms of anatomical vulnerability, flexibility and equipment integration, necessitating a separate solution from the thorax in terms of optimal materials selection. An integrated approach towards the selection of the most appropriate combination of materials to be used for each of the two potential designs of future neck protection has been developed. This approach requires evaluation of the properties of each potential material in addition to ballistic performance alone, including flexibility, mass, wear resistance and thermal burden. The aim of this article is to provide readers with an overview of this integrated approach towards ballistic materials selection and an update of its current progress in the development of future ballistic neck protection.

  16. U.S./Russian lab-to-lab materials protection, control and accounting program efforts at the Institute of Inorganic Materials

    International Nuclear Information System (INIS)

    Ruhter, W.D.; Kositsyn, V.; Rudenko, V.; Siskind, B.; Bieber, A.; Hoida, H.; Augustson; Ehinger, M.; Smith, B.W.

    1996-01-01

    The All-Russian Scientific Research Institute of Inorganic Materials (VNIINM) performs research in nuclear power reactor fuel,m spent fuel reprocessing and waste management, materials science of fissionable and reactor structural materials, metallurgy, superconducting materials, and analytical sciences. VNIINM supports the Ministry of Atomic Energy of the Russian Federation (MINATOM) in technologies for fabrication and processing of nuclear fuel. As a participant in the U. S./Russian Lab-to-Lab nuclear materials protection, control and accounting (MPC ampersand A) program, VNIINM is providing evaluation, certification, and implementation of measurement methods for such materials. In 1966, VNIINM will be working with Brookhaven staff in developing and documenting material control and accounting requirements for nuclear materials in bulk form, Livermore and Los Alamos staff in testing and evaluating gamma-ray spectrometry methods for bulk materials, Los Alamos staff in test and evaluation of neutron-coincidence counting techniques, Oak Ridge staff in accounting of bulk materials with process instrumentation, and Pacific Northwest staff on automating VNIINM's coulometric titration system. In addition, VNIINM will develop a computerized accounting system for nuclear material within VNIINM and heir storage facility. This paper describes the status of this work and anticipated progress in 1996

  17. The influence of protective properties of packaging materials and ...

    African Journals Online (AJOL)

    The influence of protective properties of packaging materials and modified atmosphere on quality changes of dried apricot is shown in this paper. In our investigation, we used four different characteristic combinations of packaging materials with different barrier properties for packaging of dried apricot: ...

  18. The Application of Auxetic Material for Protective Sports Apparel

    Directory of Open Access Journals (Sweden)

    Charlotte Moroney

    2018-02-01

    Full Text Available Current research of auxetic materials highlights its potential as personal protective equipment for sports apparel with enhanced properties such as conformability, superior energy absorption and reduced thickness. In contrast, commercially available protective materials have proven to be problematic in that they inhibit movement, breathability, wicking and that molded pads are prone to saddling. Foam components are embedded within personal protective equipment for sports apparel, where protective material is positioned at regions of the body frequently exposed to injury of the soft tissue through collision, falls or hard impact. At present, the impact resistance of auxetic open cell polyurethane foam and some additively manufactured auxetic structures have been established, and processes for manufacturing curved auxetic materials as well as molding methods have been developed. Despite this, auxetic materials have not yet been applied as personal protective equipment for sports apparel in current research. This paper argues that there is scope to investigate auxetic materials potential for enhanced wearer functionality through properties of synclastic curvature and biaxial expansion.

  19. The usage of phase change materials in fire fighter protective clothing: its effect on thermal protection

    Science.gov (United States)

    Zhao, Mengmeng

    2017-12-01

    The thermal protective performance of the fire fighter protective clothing is of vital importance for fire fighters. In the study fabrics treated by phase change materials (PCMs) were applied in the multi-layered fabrics of the fire fighter protective clothing ensemble. The PCM fabrics were placed at the different layers of the clothing and their thermal protective performance were measured by a TPP tester. Results show that with the application of the PCM fabrics the thermal protection of the multi-layered fabrics was greatly increased. The time to reach a second degree burn was largely reduced. The location of the PCM fabrics at the different layers did not affect much on the thermal protective performance. The higher amount of the PCM adds on, the higher thermal protection was brought. The fabrics with PCMs of a higher melting temperature could contribute to higher thermal protection.

  20. Convention on the Physical Protection of Nuclear Material

    International Nuclear Information System (INIS)

    1980-01-01

    The convention on the Physical Protection of Nuclear Material is composed of the text of 23 articles, annex 1 showing the levels of physical protection and annex 2 which is the categorization list of nuclear material. The text consists of definitions (article 1), the scope of applications (2), liability of protecting nuclear material during international transport (3 and 4), duty of mutual cooperation (5 and 6), responsibility for criminal punishment (7 to 13), and final provisions (14 to 23). It is to be noted that the nuclear material for military purposes and domestic nuclear facilities are excluded in the connection. After the brief description of the course leading to the establishment of the convention, individual articles and annexes and the respective Japanese version, and the explanation based on the intergovernmental meeting discussion on the draft convention are described. (J.P.N.)

  1. Physical protection of nuclear materials and facilities in CEA

    International Nuclear Information System (INIS)

    Garnier-Gratia, M.-H.; Jorda, A.

    2001-01-01

    Full text: CEA (Commissariat a l'Energie Atomique), as nuclear operator, is responsible for the control and protection of their nuclear materials. Inside CEA, DCS (Central Security Division) is in charge of the security matters, DCS defines the CEA strategy in this field, especially in physical protection. The paper will present the physical protection strategy of CEA. DCS defines the rules and methods; the operators have to apply in order to fulfill the security objectives of CEA. CEA has to provide the regulatory authority with documents proving that it is in accordance with the requirements of the 25th July 1980 law and 12th May 1981 decree. It has to implement all the necessary means in order to achieve the results requested by the regulatory authority. All these arrangements are described in the 'license and control file'. This file should specify the facility safeguards and physical protection system. Accounting measures are also described. In this file, the petitioner has to justify its capacity for holding nuclear materials and for exercising authorized activities on them. So the organization and the installed means have to be described in this authorization file. For physical protection, containment, surveillance and physical protection measures are presented: Containment measures must prevent the unauthorized or unjustified movements of nuclear material in the framework of the authorized activities; Surveillance measures must guarantee the integrity of the containment, check that no material is exiting by an abnormal channel; Physical protection measures for the materials, the premises and the facilities are intended to protect them against malevolent actions by means of security systems. The Central Security Division has established guidelines to provide guidance to the nuclear materials holders in writing such files. Each holding unit has to establish a 'license and control file' and each CEA site establishes a 'site license and control file

  2. [Safeguards for the physical protection of nuclear materials and facilities

    International Nuclear Information System (INIS)

    Jones, O.E.

    1975-01-01

    Testimony is given on the subject of safeguards for the physical protection of nuclear materials and facilities, particularly during transportation. The ERDA nation-wide safe-secure transportation system and the Safe-Secure Trailer are described. The nationwide ERDA voice communication system is also described. Development of hardware and systems is discussed. The use of adversary simulation for evaluating protection systems is mentioned

  3. Physical protection of facilities and special nuclear materials in france

    International Nuclear Information System (INIS)

    Jeanpierre, G.

    1980-01-01

    Physical protection of nuclear facilities and special nuclear materials is subject in France to a national governmental regulation which provides for the basic principles to be taken into account and the minimal level of protection deemed necessary. But the responsibility of implementation is left to the facility management and the resulting decentralization allows for maximum efficiency. All safeguards measures comply with the commitments taken at the international level by the French government

  4. Protective material for solar cell; Taiyo denchiyo hyomen hogozai

    Energy Technology Data Exchange (ETDEWEB)

    Iimura, M.; Domoto, T. [Nitto Denko Corp., Osaka (Japan)

    1998-02-03

    The protective material for the solar cell of this invention consists of fluororesin containing from 1 to 20wt% titanium oxide particles with the particle size range from 1 to 1,000nm. Surface contamination of the protective material for the solar cell and deterioration of the adhesive are prevented when titanium oxide with particular particle size is contained in the fluororesin in a particular range as mentioned above. Titanium oxide has photocatalytic performance to decompose organic substances, and the surface protective material for the solar cell containing titanium oxide can decompose and remove dirt such as dust adhering the surface for preventing surface contamination. In addition, total light permeability can be maintained at high rate and the permeability of less than 350nm ultraviolet rays causing deterioration of the adhesive can be decreased if the particle size and content of titanium oxide are specified. Titanium dioxide of anatase type crystal structure is ideal as the titanium oxide. 1 tab.

  5. On-line course as tools for radiation protection training in patients. A practical case in computerized tomography

    International Nuclear Information System (INIS)

    Medina Campos, J.; Fernandez Tallon, J.; Busca Suau, J.; Baro Casanovas, J.

    2006-01-01

    The rise in ionizing radiation applications within the field of diagnostics, with the corresponding increase in both number and doses received by patients, requires adequate resources for education and training in radiological protection. In is quite difficult to assemble professionals at a specific place to carry out training. However, the use of Information and Communication Technologies (IT) makes it possible to carry out training. However, the use of Information and Communication Technologies (IT) makes it possible to carry out training through Internet in an effective, easy and amusing way (e-learning). An on-line course of patient radiological protection and quality control in computer tomography has been developed aimed at professionals that use these diagnostic techniques. The course has been run twice in the period 2005-2006. The course is found on an Internet-accessible Virtual Campus, which allows access to multimedia contents, communication between students and instructors and follow-up of students performance. Final evaluation is done on-line and successfully passing the course counts for 8.9 credits in the Continuous Education Programme of Spanish Health Systems. (Author)

  6. Computerized procedure for protection coordination in distribution primary circuits; Procedimiento computarizado para coordinacion de protecciones en circuitos primarios de distribucion

    Energy Technology Data Exchange (ETDEWEB)

    Carrillo, Victor M; Velazquez Sanchez, Raul [Instituto de Investigaciones Electricas, Cuernavaca (Mexico)

    1987-12-31

    Nowadays, the method employed to study the protection coordination are based in the hand outlining of curves time- current and in the visual comparison in log sheets. Due to the large amount of distribution circuits, the engineer makes a considerable effort to perform this type of studies, which besides are routinist and time consuming. In this article a program for the computer aided design for the protection coordination in primary distribution circuits is presented. Such a program -carried out in the Transmission and Distribution Department of the Power Systems Division of the Instituto de Investigaciones Electricas (IIE)- substitutes in an efficient manner, the manual procedures that are performed in the protection coordination studies. The coordination principles, suggested by the equipment manufacturers, were respected, trying, at the same time, to keep the procedures of the Comision Federal de Electricidad personnel (CFE) emerged from the field experience. The algorithm basically consists of an iterative process in the selection of the adjustments taking as a reference the of three-phase short- circuit and of phase to ground, values, as well as the operating times. [Espanol] Actualmente, los metodos que se emplean para estudiar la coordinacion de protecciones se basan en el trazado manual de curvas de tiempo-corriente y en la comparacion visual sobre hojas logaritmicas. Debido a la gran cantidad de circuitos de distribucion, el ingeniero hace un esfuerzo considerable para realizar este tipo de estudios, los que ademas, son rutinarios y tardados. En este articulo, se presenta un programa para el diseno asistido por computadora del proceso de coordinacion de protecciones en circuitos primarios de distribucion. Dicho programa -realizado en el Departamento de Transmision y Distribucion, de la Division de Sistemas de Potencia, del Instituto de Investigaciones Electricas (IIE)- sustituye de manera eficaz los procedimientos manuales que se efectuan en los estudios

  7. Computerized procedure for protection coordination in distribution primary circuits; Procedimiento computarizado para coordinacion de protecciones en circuitos primarios de distribucion

    Energy Technology Data Exchange (ETDEWEB)

    Carrillo, Victor M.; Velazquez Sanchez, Raul [Instituto de Investigaciones Electricas, Cuernavaca (Mexico)

    1986-12-31

    Nowadays, the method employed to study the protection coordination are based in the hand outlining of curves time- current and in the visual comparison in log sheets. Due to the large amount of distribution circuits, the engineer makes a considerable effort to perform this type of studies, which besides are routinist and time consuming. In this article a program for the computer aided design for the protection coordination in primary distribution circuits is presented. Such a program -carried out in the Transmission and Distribution Department of the Power Systems Division of the Instituto de Investigaciones Electricas (IIE)- substitutes in an efficient manner, the manual procedures that are performed in the protection coordination studies. The coordination principles, suggested by the equipment manufacturers, were respected, trying, at the same time, to keep the procedures of the Comision Federal de Electricidad personnel (CFE) emerged from the field experience. The algorithm basically consists of an iterative process in the selection of the adjustments taking as a reference the of three-phase short- circuit and of phase to ground, values, as well as the operating times. [Espanol] Actualmente, los metodos que se emplean para estudiar la coordinacion de protecciones se basan en el trazado manual de curvas de tiempo-corriente y en la comparacion visual sobre hojas logaritmicas. Debido a la gran cantidad de circuitos de distribucion, el ingeniero hace un esfuerzo considerable para realizar este tipo de estudios, los que ademas, son rutinarios y tardados. En este articulo, se presenta un programa para el diseno asistido por computadora del proceso de coordinacion de protecciones en circuitos primarios de distribucion. Dicho programa -realizado en el Departamento de Transmision y Distribucion, de la Division de Sistemas de Potencia, del Instituto de Investigaciones Electricas (IIE)- sustituye de manera eficaz los procedimientos manuales que se efectuan en los estudios

  8. U.S. government-to-government cooperation on nuclear materials protection, control, and accounting

    International Nuclear Information System (INIS)

    Mladineo, S.; Bricker, K.; Alberque, W.

    1996-01-01

    The US Department of Energy (DOE) is cooperating with Russia, the Newly Independent States (NIS), and the Baltics to help prevent the proliferation of nuclear weapons through the improvement of national systems of nuclear material protection, control, and accounting (MPC and A). US cooperation with Russia is carried out under the DOE MPC and A Program and the Nunn-Lugar funded Cooperative Threat Reduction program for Russia. Presidential Decision Directive (PDD)-41 designated DOE as the government agency with primary responsibility for MPC and A efforts in Russia, the NIS, and Baltics. Cooperation is conducted in coordination with the Nuclear Regulatory Commission (NRC) for the development of a strong, independent national regulatory agency in Russia. DOE also coordinates these efforts with the European Community and other countries. DOE''s cooperation under the MPC and A program with Russia includes aggressive near-term activities to better secure nuclear materials through MPC and A system upgrades at facilities. Simultaneously, DOE is supporting Russia in its long-term goal of implementing upgraded MPC and A systems that can be maintained and supported from indigenous resources. Projects include the development of national regulations and laws, training of trainers, the development of a computerized federal information system, and other related tasks. NRC''s role in these efforts includes regulatory development activities, such as licensing and inspection program development, and related training. This paper provides an overview of the activities undertaken through DOE-Russian cooperation on MPC and A and how they complement each other

  9. Lightning protection technology for small general aviation composite material aircraft

    Science.gov (United States)

    Plumer, J. A.; Setzer, T. E.; Siddiqi, S.

    1993-01-01

    An on going NASA (Small Business Innovative Research) SBIR Phase II design and development program will produce the first lightning protected, fiberglass, General Aviation aircraft that is available as a kit. The results obtained so far in development testing of typical components of the aircraft kit, such as the wing and fuselage panels indicate that the lightning protection design methodology and materials chosen are capable of protecting such small composite airframes from lightning puncture and structural damage associated with severe threat lightning strikes. The primary objective of the program has been to develop a lightening protection design for full scale test airframe and verify its adequacy with full scale laboratory testing, thus enabling production and sale of owner-built, lightning-protected, Stoddard-Hamilton Aircraft, Inc. Glasair II airplanes. A second objective has been to provide lightning protection design guidelines for the General Aviation industry, and to enable these airplanes to meet lightening protection requirements for certification of small airplanes. This paper describes the protection design approaches and development testing results obtained thus far in the program, together with design methodology which can achieve the design goals listed above. The presentation of this paper will also include results of some of the full scale verification tests, which will have been completed by the time of this conference.

  10. Application of crime countermeasures for the protection of nuclear materials

    International Nuclear Information System (INIS)

    Bean, C.H.

    1975-01-01

    Federal regulations prepared by the Nuclear Regulatory Commission and published in the Federal Register require licensees to take appropriate action to protect the health and safety of the public from unauthorized use of special nuclear material (SNM), which includes plutonium, uranium-233, and highly enriched uranium. Crime countermeasures for compliance with these regulations are an important part of the guidance that is provided by the NRC's Office of Standards Development. The use of crime countermeasures and protective devices is intended to prevent the unauthorized diversion of material and to aid in the detection of diversion should it be attempted. Plant and equipment designs should incorporate both electronic and physical security measures for protection of SNM. This applies to facilities and equipment for reprocessing, fabrication, and transportation of SNM. The protection systems include physical barriers, access controls, intrusion detection devices, surveillance devices, central alarm stations, communications, and response capability. Acceptable security measures and devices applicable to protected areas, material access areas, vital areas, vital equipment, and transportation vehicles have been presented in Regulatory Guides. (U.S.)

  11. Convention on the physical protection of nuclear material

    International Nuclear Information System (INIS)

    1991-09-01

    The document refers to the Convention on the Physical Protection of Nuclear Material (IAEA-INFCIRC-274). Part I contains the status list as of September 6, 1991; Part II contains the texts of reservations/declarations made upon expressing consent to be bound; Part III contains the texts of reservations/declarations made upon signature

  12. Physical protection of radioactive materials in a University Research Institute

    International Nuclear Information System (INIS)

    Boeck, H.

    1998-01-01

    Although nuclear research centers attached to universities usually do not keep large inventories of radioactive or special nuclear material, the mentioned material has still to be under strict surveillance and safeguards if applicable. One problem in such research centers is the large and frequent fluctuation of persons - mainly students, scientists or visiting guest scientists - using such materials for basic or applied research. In the present paper an overview of protective actions in such a research institute will be given and experience of more than 36 years will be presented. (author)

  13. Protecting nuclear material and facilities: Is a new approach needed?

    International Nuclear Information System (INIS)

    Steinhausler, F.; Bunn, G.

    2002-01-01

    Full text: The main reason why national physical protection (PP) systems for nuclear and other radioactive material need to be strengthened further is that, after the attacks on the US on 11 September 2001, the threat of dangerous, suicidal radiological and nuclear terrorism can no longer be excluded as a possibility. Existing PP systems were not designed to deal with the threat of suicidal terrorists having the numbers, skills, training, and resources available to the commandos attacking on 11 September. Moreover, there are no mandatory international standards for domestic PP systems for nuclear or radioactive material, and this has produced great variation in protection provided from country to country. IAEA recommended standards, while useful, were not designed with the new terrorist threat in mind. Moreover, they are often not followed in practice. The result is inadequate protection against the new form of terrorism in most countries. The Director General of the IAEA expressed a similar view after 11 September, but achieving a consensus to amend the Convention on the Physical Protection of Nuclear Material (CPPNM) to require specific standards of protection for different amounts and kinds of nuclear material used or stored domestically (not in international transport) has been impossible in the year since 11 September. In the case of radiological materials, a new effort to provide required international standards for protection against the new form of terrorism has not begun. In the summer of 2001, leaders of the G-8 countries agreed to a Global Partnership to prevent the new terrorists from acquiring nuclear and radiological as well as other materials related to weapons of mass destruction. Perhaps in part because of the failure to date to achieve agreement on an effective amendment to the CPPNM, the first principle of this partnership is to strengthen 'multilateral treaties and other instruments whose aim is to prevent the proliferation or illicit

  14. The physical protection of nuclear material and nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-06-01

    The latest review (1993) of this document was of limited scope and resulted in changes to the text of INFCIRC/225/Rev.2 designed to make the categorization table in that document consistent with the categorization table contained in the Convention on Physical Protection of Nuclear Materials. Consequently, a comprehensive review of INFCIRC/225 has not been conducted since 1989. Consequently, a meeting of national experts was convened from 2-5 June 1998 and from 27-29 October 1998 for a thorough review of INFCIRC/225/Rev.3. The revised document reflects the recommendations of the national experts to improve the structure and clarity of the document and to take account of improved technology and current international and national practices. In particular, a chapter has been added which provides specific recommendations related to sabotage of nuclear facilities and nuclear material. As a result of this addition, the title has been changed to 'The Physical Protection of Nuclear Material and Nuclear Facilities'. The recommendations presented in this IAEA document reflect a broad consensus among Member States on the requirements which should be met by systems for the physical protection of nuclear materials and facilities. It is hoped that they will provide helpful guidance for Member States.

  15. The physical protection of nuclear material and nuclear facilities

    International Nuclear Information System (INIS)

    1999-06-01

    The latest review (1993) of this document was of limited scope and resulted in changes to the text of INFCIRC/225/Rev.2 designed to make the categorization table in that document consistent with the categorization table contained in the Convention on Physical Protection of Nuclear Materials. Consequently, a comprehensive review of INFCIRC/225 has not been conducted since 1989. Consequently, a meeting of national experts was convened from 2-5 June 1998 and from 27-29 October 1998 for a thorough review of INFCIRC/225/Rev.3. The revised document reflects the recommendations of the national experts to improve the structure and clarity of the document and to take account of improved technology and current international and national practices. In particular, a chapter has been added which provides specific recommendations related to sabotage of nuclear facilities and nuclear material. As a result of this addition, the title has been changed to 'The Physical Protection of Nuclear Material and Nuclear Facilities'. The recommendations presented in this IAEA document reflect a broad consensus among Member States on the requirements which should be met by systems for the physical protection of nuclear materials and facilities. It is hoped that they will provide helpful guidance for Member States

  16. A computerized system based on an alternative pulse echo immersion technique for acoustic characterization of non-porous solid tissue mimicking materials

    Science.gov (United States)

    Nazihah Mat Daud, Anis; Jaafar, Rosly; Kadri Ayop, Shahrul; Supar Rohani, Md

    2018-04-01

    This paper discusses the development of a computerized acoustic characterization system of non-porous solid tissue mimicking materials. This system employs an alternative pulse echo immersion technique and consists of a pulser/receiver generator, a transducer used as both a transmitter and a receiver, a digital oscilloscope, and a personal computer with a custom-developed program installed. The program was developed on the LabVIEW 2012 platform and comprises two main components, a user interface and a block diagram. The user interface consists of three panels: a signal acquisition and selection panel, a display panel, and a calculation panel. The block diagram comprises four blocks: a signal acquisition block, a peak signal analysis block, an acoustic properties calculation and display block, and an additional block. Interestingly, the system can be operated in both online and offline modes. For the online mode, the measurements are performed by connecting the system with a Rigol DS2000 Series digital oscilloscope. In contrast, the measurements are carried out by processing the saved data on the computer for the offline mode. The accuracy and consistency of the developed system was validated by a KB-Aerotech Alpha Series transducer with 5 MHz center frequency and a Rigol DS2202 two-channel 200 MHz 2 GSa s-1 digital oscilloscope, based on the measurement of the acoustic properties of three poly(methyl methacrylate) samples immersed in a medium at a temperature of (24.0  ±  0.1) °C. The findings indicated that the accuracy and consistency of the developed system was exceptionally high, within a 1.04% margin of error compared to the reference values. As such, this computerized system can be efficiently used for the acoustic characterization of non-porous solid tissues, given its spontaneous display of results, user-friendly interface, and convenient hardware connection.

  17. Impact Testing of Orbiter Thermal Protection System Materials

    Science.gov (United States)

    Kerr, Justin

    2006-01-01

    This viewgraph presentation reviews the impact testing of the materials used in designing the shuttle orbiter thermal protection system (TPS). Pursuant to the Columbia Accident Investigation Board recommendations a testing program of the TPS system was instituted. This involved using various types of impactors in different sizes shot from various sizes and strengths guns to impact the TPS tiles and the Leading Edge Structural Subsystem (LESS). The observed damage is shown, and the resultant lessons learned are reviewed.

  18. A review of the materials and allergens in protective gloves.

    Science.gov (United States)

    Rose, Rebecca F; Lyons, Paul; Horne, Helen; Mark Wilkinson, S

    2009-09-01

    The ingredients previously reported to cause protective glove allergy are presented and evaluated for strength of evidence. Allergens that have caused both delayed hypersensitivity and contact urticaria are considered for rubber, plastic, leather, and textile gloves. The current guidelines regarding glove manufacture are described. A list of materials confirmed by the industry to be used in glove production is presented together with a suggested series for investigating patients with delayed type hypersensitivity and contact urticaria secondary to glove use.

  19. Convention on the physical protection of nuclear materials

    International Nuclear Information System (INIS)

    1997-01-01

    The document refers to the Convention on the Physical Protection of Nuclear Material (IAEA-INFCIRC-274), including in Part I the status list of signature, ratification, acceptance, approval, accession or succession by States or organizations as of 31 December 1996, in Part II the texts of reservations/declarations made upon or following expressing consent to be bound, and in Part III the texts of reservations/declarations made upon signature

  20. Convention on the physical protection of nuclear material

    International Nuclear Information System (INIS)

    1990-08-01

    The document refers to the Convention on the Physical Protection of Nuclear Material (INFCIRC/274). Part I contains reservations/declarations made upon or following signature and Part II contains reservations/declarations made upon or following deposit of instrument of consent to be bound. The status of signature, ratification, acceptance, approval or accession by States or organizations as of 31 July 1990 is presented in an attachment

  1. Convention on the physical protection of nuclear material

    International Nuclear Information System (INIS)

    1982-01-01

    The document presents the original draft for a Convention on the Physical Protection of Nuclear Material, full reports of all the discussions held by representatives of Member States at meetings called by the IAEA, texts of written comments provided by Member States and the final agreed text of the Convention, list of original signatory States and status of the list of signatory States at the date of publication

  2. Collaborative Russian-US work in nuclear material protection, control and accounting at the Institute of Physics and Power Engineering. II. extension to additional facilities

    International Nuclear Information System (INIS)

    Kuzin, V.V.; Pshakin, G.M.; Belov, A.P.

    1996-01-01

    During 1995, collaborative Russian-US nuclear material protection, control and accounting (MPC ampersand A) tasks at the Institute of Physics and Power Engineering (IPPE) in Obninsk, Russia focused on improving the protection of nuclear materials at the BFS Fast Critical Facility. BFS has thousands of fuel disks containing highly enriched uranium and weapons-grade plutonium that are used to simulate the core configurations of experimental reactors in two critical assemblies. Completed tasks culminated in demonstrations of newly implemented equipment and methods that enhanced the MPC ampersand A at BFS through computerized accounting, nondestructive inventory verification measurements, personnel identification and assess control, physical inventory taking, physical protection, and video surveillance. The collaborative work is now being extended. The additional tasks encompass communications and tamper-indicating devices; new storage alternatives; and systemization of the MPC ampersand A elements that are being implemented

  3. Computerizing primary schools in rural kenya

    DEFF Research Database (Denmark)

    Ogembo, J.G.; Ngugi, B.; Pelowski, Matthew John

    2012-01-01

    questions surrounding this endeavour. Specifically: 1.) what problems do rural schools actually want to solve with computerization; 2.) is computerization the most important priority for rural schools; 3.) are schools ready, in terms of infrastructure, for a computer in the classroom; or 4.) might...... and protective roofing -posing severe challenges to the outstanding conception of computerization. We consider these results and make recommendations for better adapting programs for computer introduction, and also suggest the use of new innovative devices, such as cell phones, which might already have overcome......This paper investigates the outstanding challenges facing primary schools' computerization in rural Kenya. Computerization of schools is often envisaged as a 'magic', or at least a particularly efficient, solution to many of the problems that developing countries face in improving primary school...

  4. Transport of radioactive materials: the need for radiation protection programmes

    International Nuclear Information System (INIS)

    Masinza, S.A.

    2004-01-01

    The increase in the use of radioactive materials worldwide requires that these materials be moved from production sites to the end user or in the case of radioactive waste, from the waste generator to the repository. Tens of millions of packages containing radioactive material are consigned for transport each year throughout the world. The amount of radioactive material in these packages varies from negligible quantities in shipments of consumer products to very large quantities of shipments of irradiated nuclear fuel. Transport is the main way in which the radioactive materials being moved get into the public domain. The public is generally unaware of the lurking danger when transporting these hazardous goods. Thus radiation protection programmes are important to assure the public of the certainty of their safety during conveyance of these materials. Radioactive material is transported by land (road and rail), inland waterways, sea/ocean and air. These modes of transport are regulated by international 'modal' regulations. The international community has formulated controls to reduce the number of accidents and mitigate their consequences should they happen. When accidents involving the transport of radioactive material occur, it could result in injury, loss of life and pollution of the environment. In order to ensure the safety of people, property and the environment, national and international transport regulations have been developed. The appropriate authorities in each state utilise them to control the transport of radioactive material. Stringent measures are required in these regulations to ensure adequate containment, shielding and the prevention of criticality in all spheres of transport, i.e. routine, minor incidents and accident conditions. Despite the extensive application of these stringent safety controls, transport accidents involving packages containing radioactive material have occurred and will continue to occur. When a transport accident occurs, it

  5. Computerized simulation of the mechanical behavior of wood-filled shock absorbers of radioactive materials transport casks

    International Nuclear Information System (INIS)

    Neumann, Martin; Wille, Frank

    2011-01-01

    In Germany the mechanical component inspection of transport containers for radioactive materials is performed by BAM (Bundesanstalt fuer Materialforschung und -pruefung) under consideration of national and international standards and guidelines. Experimental and calculative (analytical and numerical) techniques combined with material and/or component testing are the basis of assessment concepts according the state of the art. The authors describe the experiences of BAM concerning assessment and description of the mechanical behavior of shock absorbing components, including modeling strategies, material models, drop tests and experiment-calculation comparison. Energy absorbing components are used to reduce the impact forces at the container in case of a transport accident. In Germany wood filled thin-walled constructions are used. The deformation behavior of the wood is a main part of the calculative simulation procedures in comparison with experimental tests.

  6. [Computerized medical record: deontology and legislation].

    Science.gov (United States)

    Allaert, F A; Dusserre, L

    1996-02-01

    Computerization of medical records is making headway for patients' follow-up, scientific research, and health expenses control, but it must not alter the guarantees provided to the patients by the medical code of ethics and the law of January 6, 1978. This law, modified on July 1, 1994, requires to register all computerized records of personal data and establishes rights to protect privacy against computer misdemeanor. All medical practitioners using computerized medical records must be aware that the infringement of this law may provoke suing in professional, civil or criminal court.

  7. Shellac/nanoparticles dispersions as protective materials for wood

    Science.gov (United States)

    Weththimuni, Maduka L.; Capsoni, Doretta; Malagodi, Marco; Milanese, Chiara; Licchelli, Maurizio

    2016-12-01

    Wood is a natural material that finds numerous and widespread applications, but is subject to different decay processes. Surface coating is the most common method used to protect wood against deterioration and to improve and stabilize its distinctive appearance. Shellac is a natural resin that has been widely used as a protective material for wooden artefacts (e.g. furniture, musical instruments), due to its excellent properties. Nevertheless, diffusion of shellac-based varnishes has significantly declined during the last decades, because of some limitations such as the softness of the coating, photo-degradation, and sensitivity to alcoholic solvents and to pH variations. In the present study, different inorganic nanoparticles were dispersed into dewaxed natural shellac and the resulting materials were investigated even after application on wood specimens in order to assess variations of the coating properties. Analyses performed by a variety of experimental techniques have shown that dispersed nanoparticles do not significantly affect some distinctive and desirable features of the shellac varnish such as chromatic aspect, film-forming ability, water repellence, and adhesion. On the other hand, the obtained results suggested that some weak points of the coating, such as low hardness and poor resistance to UV-induced ageing, can be improved by adding ZrO2 and ZnO nanoparticles, respectively.

  8. Mechanical Testing of Carbon Based Woven Thermal Protection Materials

    Science.gov (United States)

    Pham, John; Agrawal, Parul; Arnold, James O.; Peterson, Keith; Venkatapathy, Ethiraj

    2013-01-01

    Three Dimensional Woven thermal protection system (TPS) materials are one of the enabling technologies for mechanically deployable hypersonic decelerator systems. These materials have been shown capable of serving a dual purpose as TPS and as structural load bearing members during entry and descent operations. In order to ensure successful structural performance, it is important to characterize the mechanical properties of these materials prior to and post exposure to entry-like heating conditions. This research focuses on the changes in load bearing capacity of woven TPS materials after being subjected to arcjet simulations of entry heating. Preliminary testing of arcjet tested materials [1] has shown a mechanical degradation. However, their residual strength is significantly more than the requirements for a mission to Venus [2]. A systematic investigation at the macro and microstructural scales is reported here to explore the potential causes of this degradation. The effects of heating on the sizing (an epoxy resin coating used to reduce friction and wear during fiber handling) are discussed as one of the possible causes for the decrease in mechanical properties. This investigation also provides valuable guidelines for margin policies for future mechanically deployable entry systems.

  9. Development of Processing Techniques for Advanced Thermal Protection Materials

    Science.gov (United States)

    Selvaduray, Guna; Cox, Michael; Srinivasan, Vijayakumar

    1997-01-01

    Thermal Protection Materials Branch (TPMB) has been involved in various research programs to improve the properties and structural integrity of the existing aerospace high temperature materials. Specimens from various research programs were brought into the analytical laboratory for the purpose of obtaining and refining the material characterization. The analytical laboratory in TPMB has many different instruments which were utilized to determine the physical and chemical characteristics of materials. Some of the instruments that were utilized by the SJSU students are: Scanning Electron Microscopy (SEM), Energy Dispersive X-ray analysis (EDX), X-ray Diffraction Spectrometer (XRD), Fourier Transform-Infrared Spectroscopy (FTIR), Ultra Violet Spectroscopy/Visible Spectroscopy (UV/VIS), Particle Size Analyzer (PSA), and Inductively Coupled Plasma Atomic Emission Spectrometer (ICP-AES). The above mentioned analytical instruments were utilized in the material characterization process of the specimens from research programs such as: aerogel ceramics (I) and (II), X-33 Blankets, ARC-Jet specimens, QUICFIX specimens and gas permeability of lightweight ceramic ablators. In addition to analytical instruments in the analytical laboratory at TPMB, there are several on-going experiments. One particular experiment allows the measurement of permeability of ceramic ablators. From these measurements, physical characteristics of the ceramic ablators can be derived.

  10. Composite materials for protection against electromagnetic microwave radiation

    International Nuclear Information System (INIS)

    Senyk, IV; Barsukov, VZ; Savchenko, BM; Shevchenko, KL; Plavan, VP; Shpak, Yu V; Kruykova, OA

    2016-01-01

    A fairly wide range of carbon-polymer composite materials was synthesized and studied in terms of their potential to protect people and electronic equipment from exposure to electromagnetic radiation (EMR). The materials studied included three main groups: (1) PVC polymer composites filled with various carbon-containing fillers (colloidal graphite, thermally expanded graphite, acetylene black, graphitized carbon black, carbon nanotubes, graphene) at concentrations ranging from 5 to 20%; (2) carbon cloth - commercial and modified with nanometal additives (e.g., nanoparticles of Cu, TiN, etc.); (3) highly-filled polymer-carbon composites in the form of paint. The transmission rate a of electromagnetic radiation was investigated for such materials in the frequency range of 10 GHz as well as their electrical conductivity. The results showed that the shielding ability of the materials of group (2) is significantly higher than that of the materials of group (1), which is probably due to the presence of strong internal skeleton of conductivity. Nevertheless, some highly-filled mixed polymer-carbon composites in the form of paint demonstrate even more shielding ability than carbon cloth and could be used for the defense against EMR. (paper)

  11. On the activities in building a computerized system of nuclear materials accounting and control at the SChK radiochemical plant

    International Nuclear Information System (INIS)

    Skuratov, V.A.; Purygin, V.Ya.; Savchuk, O.A.

    1999-01-01

    The project: Development of the nuclear materials (NM) control and accountancy system model on the example of the SCP Radiochemical Plant (RCP) has been fulfilled by the Siberian Chemical Plant in collaboration with a number of organization since October 1992 through October 1996. One of the key goals of the project was the use of new criteria and approaches to NM control and accounting, including step-by-step implementation for all the NM flows measurement principles. The work on project has resulted in the development of the model for NM control and accountancy system at RCP. When designing the model, the single RCP balance area on uranium and plutonium was broken down to four NM balance areas. The model developed within the project is being implemented in a few ways: introduction of innovative NM measurement techniques, working out regulatory documents, adaptation of computers for control and accountancy. An aim to secure safety in the most problematic area MBA-2 (plutonium dioxide production) transition to the real-time cannot be resolved without implementation of computerized system of NM control and accountancy [ru

  12. Radiation protection measures for the handling of unsealed radioactive materials

    International Nuclear Information System (INIS)

    Moehrle, G.

    1975-03-01

    The radiation protective medical measures are described which are required after contamination by radioactive materials or their incorporation. In the case of skin contamination, penetration by diffusion is explained and the maximum permissible value with regard to the various types of radiation is given. A detailed description of the decontamination measures including the necessary equipment follows. Indications for the treatment of injuries are given. In addition, incorporation due to inhalation, ingestion with intake through the skin are described, direct and indirect incorporation detection are explained, and the therapeutical possibilities and measures are gone into. (ORU/LH) [de

  13. Application of radiation protection programmes to transport of radioactive material

    International Nuclear Information System (INIS)

    Lopez Vietri, Jorge; Capadona, Nancy; Barenghi, Leonardo

    2008-01-01

    Full text: The principles for implementing radiation protection programmes (RPP) are detailed in the draft IAEA safety guide TS-G-1.5 'Radiation protection programmes for transport of radioactive material'. The document is described in this paper and analysis is made for typical applications to current operations carried out by consignors, carriers and consignees. Systematic establishment and application of RPPs is a way to control radiological protection during different steps of transport activity. The most widely transported packages in the world are radiopharmaceuticals by road. It is described an application of RPP for an organization involved in road transport of Type A packages containing radiopharmaceuticals. Considerations based on the radionuclides, quantities and activities transported are the basis to design and establish the scope of the RPP for the organizations involved in transport. Next stage is the determination of roles and responsibilities for each activity related to transport of radioactive materials. An approach to the dose received by workers is evaluated considering the type, category and quantity of packages, the radionuclides, the frequency of consignments and how long are the storages. The average of transports made in the last years must be taken into account and special measures intended to optimize the protection are evaluated. Tasks like monitoring, control of surface contamination and segregation measures, are designed based on the dose evaluation and optimization. The RPP also indicates main measures to follow in case of emergency during transport taking account of radionuclides, activities and category of packages for different accident scenarios. Basis for training personnel involved in handling of radioactive materials to insure they have appropriate knowledge about preparing packages, measuring dose rates, calculating transport index, labelling, marking and placarding, transport documents, etc, are considered. The RPP is a part

  14. Protective coatings on structural materials for energy conversion systems

    International Nuclear Information System (INIS)

    John, J.T.; De, P.K.; Srinivasa, R.S.

    2000-01-01

    Full text: Structural Materials and Components used in coal fired energy conversion systems, crude oil refineries and coal gasification plants are subjected to degradation due to oxidation, sulfidation, carbonization and halogenation. Suitable protective coatings can significantly enhance their life. Protective coatings work by forming a highly stable, self-healing and slow growing protective scale at the operating temperatures. These scales act as barriers between the corrosive environment and the alloy and prevent degradation of the substitute. Three types of scales that provide such protection are based on Al 2 O 3 , Cr 2 O 3 and SiO 2 . Aluminide coatings are major alumina forming protecting coatings, applied on nickel, cobalt and iron base alloys. Aluminide coatings are prepared by enriching the surface of a component by aluminum. In this paper the formation of aluminide coatings of nickel, IN738, Alloy 800, Zircaloy-2 and pure iron by chemical vapor deposition has been described. In this technique, Aluminum chloride vapors from bath kept at 353-373 K are carried in a stream of hydrogen gas into a Hot Walled CVD chamber kept at 1173-1373 K. The AlCl 3 vapors were allowed to react with pure aluminum whereby aluminum sub-chlorides like AlCl and AlCl 2 are produced which deposit aluminum on the substrates. At the high temperature of the deposition, aluminum diffuses into the substrate and forms the aluminide coating. The process can be represented by the reaction Al (i) + AlCl 3(g) AlCl 2(s) + AlCl 2 (g) . XRD and optical microscopic studies have characterized the coatings. On pure nickel and Alloy 800 the coating consists of Ni 2 Al 3 and NiAl respectively. On pure iron the coatings consisted of FeAl. On Zircaloy-2, ZrAl 2 was also detected. The CVD coating process, XRD and optical microscopy data will be discussed further

  15. Terahertz Computed Tomography of NASA Thermal Protection System Materials

    Science.gov (United States)

    Roth, D. J.; Reyes-Rodriguez, S.; Zimdars, D. A.; Rauser, R. W.; Ussery, W. W.

    2011-01-01

    A terahertz axial computed tomography system has been developed that uses time domain measurements in order to form cross-sectional image slices and three-dimensional volume renderings of terahertz-transparent materials. The system can inspect samples as large as 0.0283 cubic meters (1 cubic foot) with no safety concerns as for x-ray computed tomography. In this study, the system is evaluated for its ability to detect and characterize flat bottom holes, drilled holes, and embedded voids in foam materials utilized as thermal protection on the external fuel tanks for the Space Shuttle. X-ray micro-computed tomography was also performed on the samples to compare against the terahertz computed tomography results and better define embedded voids. Limits of detectability based on depth and size for the samples used in this study are loosely defined. Image sharpness and morphology characterization ability for terahertz computed tomography are qualitatively described.

  16. Security Culture in Physical Protection of Nuclear Material and Facility

    International Nuclear Information System (INIS)

    Susyanta-Widyatmaka; Koraag, Venuesiana-Dewi; Taswanda-Taryo

    2005-01-01

    In nuclear related field, there are three different cultures: safety, safeguards and security culture. Safety culture has established mostly in nuclear industries, meanwhile safeguards and security culture are relatively new and still developing. The latter is intended to improve the physical protection of material and nuclear facility. This paper describes concept, properties and factors affecting security culture and interactions among these cultures. The analysis indicates that anybody involving in nuclear material and facility should have strong commitment and awareness of such culture to establish it. It is concluded that the assessment of security culture outlined in this paper is still preliminary for developing and conduction rigorous security culture implemented in a much more complex facility such as nuclear power plant

  17. Computerized crystal-chemical classification of silicates and related materials with CRYSTANA and formula notation for classified structures

    International Nuclear Information System (INIS)

    Klein, Hans-Joachim; Liebau, Friedrich

    2008-01-01

    The computer program CRYSTANA is described which implements a method for the crystal-chemical classification of silicates and related materials. This method is mainly based upon the topological structure of the connected units of a compound and can be applied when the units are built from tetrahedra as coordination polyhedra. The classification parameters and the rules which have to be applied for their determination are summarized and a formalization of the method is provided based upon a finite graph representation of the units. A description of how CRYSTANA can be used and which kind of output it produces is included. From this output crystal-chemical formulas can be derived, which differ slightly from an existing notation in order to meet recommendations of the International Union of Crystallography. - The computer program CRYSTANA is described which implements a method for the crystal-chemical classification of silicates and related materials. The implementation is based upon a graph-theoretical formalization of the classification method. An extended notation of crystal-chemical formulas is introduced. The formulas can be derived from the output of the program

  18. IMPORTANCE OF MATERIAL BALANCES AND THEIR STATISTICAL EVALUATION IN RUSSIAN MATERIAL, PROTECTION, CONTROL AND ACCOUNTING

    International Nuclear Information System (INIS)

    Fishbone, L.G.

    1999-01-01

    While substantial work has been performed in the Russian MPC and A Program, much more needs to be done at Russian nuclear facilities to complete four necessary steps. These are (1) periodically measuring the physical inventory of nuclear material, (2) continuously measuring the flows of nuclear material, (3) using the results to close the material balance, particularly at bulk processing facilities, and (4) statistically evaluating any apparent loss of nuclear material. The periodic closing of material balances provides an objective test of the facility's system of nuclear material protection, control and accounting. The statistical evaluation using the uncertainties associated with individual measurement systems involved in the calculation of the material balance provides a fair standard for concluding whether the apparent loss of nuclear material means a diversion or whether the facility's accounting system needs improvement. In particular, if unattractive flow material at a facility is not measured well, the accounting system cannot readily detect the loss of attractive material if the latter substantially derives from the former

  19. Fingerprinting of nuclear material to strengthen physical protection

    International Nuclear Information System (INIS)

    Mueck, K.; Lindauer, H.; Falta, G.

    2002-01-01

    Full text: Physical protection of nuclear material against diversion and stealing presents a major step to prevent abuse of nuclear material for military or terrorist purposes. If such material had been diverted, however, and discovered by border traffic control, police control or other methods of investigation, identifying the site and time of diversion is of utmost importance to ensure that the point of possible diversion is closed and the possible delivery and end-use point becomes known. The quicker and more comprehensive these investigations are performed, the greater are the chances to find the criminal persons and the point of diversion. The paper, therefore, deals with fingerprinting methods used to obtain enough and comprehensive background information for investigators to find out the source of diversion and the channels through which it might have reached the point of discovery and the possible point of ultimate destination (end-use of the material). On the example of the round-robin test for the identification of illicit nuclear material performed by EURATOM in 1999, and the conclusions obtained by our laboratory it is demonstrated that a high amount of information can be drawn from a single sample and that this information can be used by investigators world-wide to find the point of origin of the material and its possible point of diversion. The set of information is segmented into 3 different levels: information gained in the first 24 hours after arrival of the unknown material, information gained up to one week after uptake and information gained up to one month after. The first information is to inform the investigators about the hazard and the relevance of the material, about preliminary investigation results and support the investigating judge on the justification to further detain the person(s). The second information should contain more detail on the material and the possible point of diversion and assist the investigators to decide on proper

  20. Physical protection concepts of nuclear materials. The French experience

    International Nuclear Information System (INIS)

    Arnaud, G.; Artaud, R.

    1995-01-01

    As the nuclear energy was being developed, it appeared necessary to set up protections against its potential hazards, that should be more complete and elaborate than those implemented on the other industrial installations. This had to be done both in the safety field to prevent the environment and the populations from the consequences of severe casualties, and in the security field to avoid the risk of proliferation and limit to an acceptable level the results of voluntarily provoked accidents and sabotages. Taking advantage of the gathered experience, this document gives consideration to the concepts used in France in order to ensure the physical protection of the nuclear materials. The following topics are tackled: context inside which are envisaged the specific measures, coherence with the general dispositions taken to protect industrial installations, importance and limitations of the part played by the regulations, respective responsibilities of the plant operators and the public authorities, compromise between objectives in view and means to implement, adjustment between the physical protection system and the operating requirements. In addition, the ways in which these systems should be implemented are discussed, underlining the necessity to make progressive steps under a permanent will, in order, first, to update and bring under conformity the old installations, and second, to ensure the maintenance of the systems, taking account of the evolutions of needs and techniques. Those points are commented on examples taken among the different types of installations to be found in France, showing the differences in approach coming from the type and the age of the facilities, and giving the present trends for the new plants. (authors). 1 annexe

  1. Collaborative Russian-US work in nuclear material protection, control and accounting at the Institute of Physics and Power Engineering

    International Nuclear Information System (INIS)

    Matveenko, I.P.; Pshakin, G.M.; Mozhaev, V.K.

    1995-01-01

    The Institute of Physics and Power Engineering (IPPE) is a leading research center under the Ministry of Atomic Energy of the Russian Federation. IPPE encompasses many installations and many specialists who perform fundamental and applied investigations in nuclear power and technology for the national nuclear program. IPPE has a key role in the national nuclear material protection, control, and accounting (MPC ampersand A) system both as a nuclear facility and also as a training center for MPC ampersand A. As a participant in the US-Russian Laboratory-to-Laboratory Cooperative Program in MPC ampersand A, IPPE is conducting several tasks in collaboration with US Department of Energy national laboratories. The main goal of these tasks is the rapid improvement of MPC ampersand A at one of the most sensitive operating IPPE installations, the BFS critical facility, which has large numbers of fuel items containing highly enriched uranium and weapons-grade plutonium. After the completion of several test, evaluation, and demonstration tasks, it is hoped that the tested and adopted methods and procedures can be applied not only to the entire population of BFS fuel items, but also to other facilities at IPPE and other Russian nuclear institutes and operating facilities. The collaborative tasks cover seven areas: computerized nuclear material accounting, entry control and portals, item control and inventory, design evaluation and analysis, gamma and neutron assay, an integrated demonstration, and physical protection elements and test bed

  2. Smart responsive phosphorescent materials for data recording and security protection.

    Science.gov (United States)

    Sun, Huibin; Liu, Shujuan; Lin, Wenpeng; Zhang, Kenneth Yin; Lv, Wen; Huang, Xiao; Huo, Fengwei; Yang, Huiran; Jenkins, Gareth; Zhao, Qiang; Huang, Wei

    2014-04-07

    Smart luminescent materials that are responsive to external stimuli have received considerable interest. Here we report ionic iridium (III) complexes simultaneously exhibiting mechanochromic, vapochromic and electrochromic phosphorescence. These complexes share the same phosphorescent iridium (III) cation with a N-H moiety in the N^N ligand and contain different anions, including hexafluorophosphate, tetrafluoroborate, iodide, bromide and chloride. The anionic counterions cause a variation in the emission colours of the complexes from yellow to green by forming hydrogen bonds with the N-H proton. The electronic effect of the N-H moiety is sensitive towards mechanical grinding, solvent vapour and electric field, resulting in mechanochromic, vapochromic and electrochromic phosphorescence. On the basis of these findings, we construct a data-recording device and demonstrate data encryption and decryption via fluorescence lifetime imaging and time-gated luminescence imaging techniques. Our results suggest that rationally designed phosphorescent complexes may be promising candidates for advanced data recording and security protection.

  3. Material Protection, Accounting, and Control Technologies (MPACT) Advanced Integration Roadmap

    Energy Technology Data Exchange (ETDEWEB)

    Durkee, Joe W. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Cipiti, Ben [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Demuth, Scott Francis [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Fallgren, Andrew James [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Jarman, Ken [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Li, Shelly [Argonne National Lab. (ANL), Argonne, IL (United States); Meier, Dave [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Miller, Mike [Argonne National Lab. (ANL), Argonne, IL (United States); Osburn, Laura Ann [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Pereira, Candido [Argonne National Lab. (ANL), Argonne, IL (United States); Dasari, Venkateswara Rao [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Ticknor, Lawrence O. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Yoo, Tae-Sic [Argonne National Lab. (ANL), Argonne, IL (United States)

    2016-09-30

    The development of sustainable advanced nuclear fuel cycles is a long-term goal of the Office of Nuclear Energy’s (DOE-NE) Fuel Cycle Technologies program. The Material Protection, Accounting, and Control Technologies (MPACT) campaign is supporting research and development (R&D) of advanced instrumentation, analysis tools, and integration methodologies to meet this goal (Miller, 2015). This advanced R&D is intended to facilitate safeguards and security by design of fuel cycle facilities. The lab-scale demonstration of a virtual facility, distributed test bed, that connects the individual tools being developed at National Laboratories and university research establishments, is a key program milestone for 2020. These tools will consist of instrumentation and devices as well as computer software for modeling, simulation and integration.

  4. Material Protection, Accounting, and Control Technologies (MPACT) Advanced Integration Roadmap

    Energy Technology Data Exchange (ETDEWEB)

    Miller, Mike [Idaho National Lab. (INL), Idaho Falls, ID (United States); Cipiti, Ben [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Demuth, Scott Francis [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Durkee, Jr., Joe W. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Fallgren, Andrew James [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Jarman, Ken [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Li, Shelly [Idaho National Lab. (INL), Idaho Falls, ID (United States); Meier, Dave [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Osburn, Laura Ann [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Pereira, Candido [Argonne National Lab. (ANL), Argonne, IL (United States); Dasari, Venkateswara Rao [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Ticknor, Lawrence O. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Yoo, Tae-Sic [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2017-01-30

    The development of sustainable advanced nuclear fuel cycles is a long-term goal of the Office of Nuclear Energy’s (DOE-NE) Fuel Cycle Technologies program. The Material Protection, Accounting, and Control Technologies (MPACT) campaign is supporting research and development (R&D) of advanced instrumentation, analysis tools, and integration methodologies to meet this goal (Miller, 2015). This advanced R&D is intended to facilitate safeguards and security by design of fuel cycle facilities. The lab-scale demonstration of a virtual facility, distributed test bed, that connects the individual tools being developed at National Laboratories and university research establishments, is a key program milestone for 2020. These tools will consist of instrumentation and devices as well as computer software for modeling, simulation and integration.

  5. Physical protection of nuclear facilities and materials. Safeguards and the role of the IAEA in physical protection

    International Nuclear Information System (INIS)

    Smolej, M.

    1999-01-01

    The physical protection and security of nuclear facilities and materials concerns utilities, manufactures, the general public, and those who are responsible for licensing and regulating such facilities. The requirements and process to ensure an acceptable physical protection and security system have been evolutionary in nature. This paper reviews the first step of such process: the State's safeguards system and the international safeguards system of the International Atomic Energy Agency (IAEA), including the relationship between these two safeguards systems. The elements of these systems that are reviewed include the State System of Accounting for and Control of Nuclear Material, physical protection measures, and containment and surveillance measures. In addition, the interactions between the State, the facility operator, and the IAEA are described. The paper addresses the IAEA safeguards system, including material accountancy and containment and surveillance; the State safeguards system, including material control and accountancy, and physical protection; the role of the IAEA in physical protection; a summary of safeguards system interactions.(author)

  6. Micro-radiography and micro-computerized tomography with absorption and phase contrast for materials characterization; Mikro-Radiografie und Mikro-Computertomografie mit Absorptions- und Phasenkontrast fuer die Materialcharakterisierung

    Energy Technology Data Exchange (ETDEWEB)

    Kastner, Johann [FH Oberoesterreich, Wels (Austria)

    2017-08-01

    The contribution describes modern techniques in micro-radiography and micro-computerized tomography for materials characterization using absorption and phase contrast. Using micro- and nano-focus tubes and adequate high.-resolution detectors it is possible to reach resolutions significantly below 1 micron. The CT technology allows in-situ deformation testing to study the damaging mechanism of materials. The application of the Talbot-Lau interferometer with CT a differential phase contrast tomography is available. Dark-field tomography is used to study individual carbon fiber bundles in carbon fiber reinforced laminates.

  7. Computerized accounting methods. Final report

    International Nuclear Information System (INIS)

    1994-01-01

    This report summarizes the results of the research performed under the Task Order on computerized accounting methods in a period from 03 August to 31 December 1994. Computerized nuclear material accounting methods are analyzed and evaluated. Selected methods are implemented in a hardware-software complex developed as a prototype of the local network-based CONMIT system. This complex has been put into trial operation for test and evaluation of the selected methods at two selected ''Kurchatov Institute'' Russian Research Center (''KI'' RRC) nuclear facilities. Trial operation is carried out since the beginning of Initial Physical Inventory Taking in these facilities that was performed in November 1994. Operation of CONMIT prototype system was demonstrated in the middle of December 1994. Results of evaluation of CONMIT prototype system features and functioning under real operating conditions are considered. Conclusions are formulated on the ways of further development of computerized nuclear material accounting methods. The most important conclusion is a need to strengthen computer and information security features supported by the operating environment. Security provisions as well as other LANL Client/Server System approaches being developed by Los Alamos National Laboratory are recommended for selection of software and hardware components to be integrated into production version of CONMIT system for KI RRC

  8. Radioactive materials' transportation main routes in Brazil. Radiation protection aspects about radioactive materials transportation

    International Nuclear Information System (INIS)

    Vaz, Solange dos Reis e; Andrade, Fernando de Menezes; Aleixo, Luiz Claudio Martins

    2007-01-01

    The heavy transportation in Brazil is generally done by highways. The radioactive material transportation follow this same rule. Whenever a radioactive material is carried by the road, by the sea or by the air, in some cases, a kind of combination of those transportation ways, the transport manager has to create a Transportation Plan and submit it to CNEN. Only after CNEN's approval, the transportation can be done. The plan must have the main action on Radiation Protection, giving responsibilities and showing all the directing that will be take. Although, the Brazilian's highways are not in good conditions, one could say that some of them are not good enough for any kind of transportation. But we are facing radioactive material use increase but the hospitals and industries, that the reason it's much more common that kind of transportation nowadays. So, because of that, a special attention by the governments must be provide to those activities. This paper goal is to show the real conditions of some important highways in Brazil in a radioactive protection's perspective and give some suggestions to adjust some of those roads to this new reality. (author)

  9. 29 CFR 1926.1000 - Rollover protective structures (ROPS) for material handling equipment.

    Science.gov (United States)

    2010-07-01

    ... 29 Labor 8 2010-07-01 2010-07-01 false Rollover protective structures (ROPS) for material handling equipment. 1926.1000 Section 1926.1000 Labor Regulations Relating to Labor (Continued) OCCUPATIONAL SAFETY... CONSTRUCTION Rollover Protective Structures; Overhead Protection § 1926.1000 Rollover protective structures...

  10. Radioactive waste computerized management

    International Nuclear Information System (INIS)

    Communaux, M.; Lantes, B.

    1993-01-01

    Since December 31, 1990, the management of the nuclear wastes for all the power stations has been computerized, using the DRA module of the Power Generation and Transmission Group's data processing master plan. So now EDF has a software package which centralizes all the data, enabling it to declare the characteristics of the nuclear wastes which are to be stored on the sites operated by the National Radioactive Waste Management Agency (ANDRA). Among other uses, this application makes it possible for EDF, by real time data exchange with ANDRA, to constitute an inventory of validated, shippable packs. It also constitutes a data base for all the wastes produced on the various sites. This application was developed to meet the following requirements: give the producers of radioactive waste a means to fully manage all the characteristics and materials that are necessary to condition their waste correctly; guarantee the traceability and safety of data and automatically assure the transmission of this data in real time between the producers and the ANDRA; give the Central Services of EDF an operation and statistical tool permitting an experienced feed-back based on the complete national production (single, centralized data base); and integrate the application within the products of the processing master plan in order to assure its maintenance and evolution

  11. Application of Synthetic Mineral Alloys as Materials for Bulletproof Vests and Products for Different Objects Protection

    Directory of Open Access Journals (Sweden)

    Anna Ignatova.

    2015-11-01

    Full Text Available Authors study ballistic properties of the material which has never been used for impact protection and the presented results prove that synthetic mineral alloys belong to the field of bulletproof ballistic protection and particularly to the means of objects’ protection from kinetic threats. Although the material has been described in connection with such specific embodiments as SVD and a cumulative jet, it is evident that many alternatives and modifications of their application for various protective articles are possible.

  12. Concepts on integration of physical protection and material accounting functions in a safeguards system

    International Nuclear Information System (INIS)

    Reynolds, D.A.

    1981-01-01

    Concepts on integration of physical protection and material accounting systems to enhance overall safeguards capability are developed and presented. These concepts identify ways in which material accounting systems can be used to enable effective monitoring of authorized movement of nuclear material through physical protection boundaries. Concepts are also discussed for monitoring user access to nuclear material and for tagging user identification to material accounting transactions through physical protection functions. These result in benefits in detecting diversion and in positively tracing material movement. Finally, coordination of safeguards information from both subsystems in such an integrated system through a safeguards coordination center is addressed with emphasis on appropriate response in case of discrepancies

  13. Material Protection, Control, and Accountancy (MPC and A) Sustainability

    International Nuclear Information System (INIS)

    Baumann, Mark; Farmer, James; Haase, Michael; Mann, Greg; Soo Hoo, Mark; Toth, William

    1999-01-01

    To date, the Department of Energy's (DOE) Material Protection, Control, and Accountancy (MPC and A) program has assisted in the implementation of operational site-wide MPC and A systems at several nuclear facilities in Russia. Eleven sites from the civilian sector have completed the site-wide installations and two have completed sub-site installations. By the end of 1999, several additional sites will have completed site-wide and sub-site system installations through DOE assistance. the effort at the completed sites has focused primarily on the design, integration, and installation of upgraded MPC and A systems. In most cases, little work has been performed to ensure that the installed systems will be sustained. Because of concerns that the installed systems would not be operated in the future, DOE established a sustainability pilot program involving the 11 sites. The purpose of DOE's MPC and A Sustainability Program is to ensure that MPC and A upgrades installed at sites in Russia are effective and will continue to operate over the long term. The program mission is to work with sites where rapid upgrades have been completed to cultivate enduring and consistent MPC and A practices. The program attempts to assist the Russian sites to develop MPC and A organizations that will operate, maintain, and continue to improve the systems and procedures. Future assistance will strive to understand and incorporate culturally sensitive approaches so that the sites take ownership for all MPC and A matters. This paper describes the efforts of the sustainability program to date

  14. Advanced Thermal Protection Systems (ATPS), Aerospace Grade Carbon Bonded Carbon Fiber Material, Phase II

    Data.gov (United States)

    National Aeronautics and Space Administration — Carbon bonded carbon fiber (CBCF) insulating material is the basis for several highly successful NASA developed thermal protection systems (TPS). Included among...

  15. U.S. and Russian cooperative efforts to enhance nuclear material protection, control, and accountability at the Siberian Chemical Combine at Tomsk-7

    International Nuclear Information System (INIS)

    Kreykes, J.; Petrushev, V.I.; Griggs, J.

    1996-01-01

    The US partners in the Laboratory-to-Laboratory Program in Nuclear Materials Protection, Control, and Accountability (MPC and A) have reached signed agreements with the Siberian Chemical Combine (SKhK) to rapidly enhance the protection, control, and accountability of nuclear material at all of its facilities. SKhK is the largest multi-function production center of the Russian nuclear complex and, until recently, its facilities produced and processed special nuclear materials for the Russian Defense Ministry. SKhK produces heat and electricity, enriches uranium for commercial reactor fuel, reprocesses irradiated fuel, and converts highly enriched uranium metal into oxide for blending into low-enriched reactor-grade uranium, and manufactures civilian products. SKhK is aggressively pursuing a program to enhance MPC and A which includes the installation of pedestrian and vehicle radiation monitors, rapid inventory methods, tamper-indicating devices, computerized accounting systems, and physical protection measures. This work is a collaboration between technical experts from Brookhaven, Lawrence Livermore, Los Alamos, Oak Ridge, pacific Northwest, and Sandia National Laboratories and their Russian counterparts at SKhK. This paper reviews the status of this initial effort and outlines plans for continuing the work in 1996

  16. Thermal Protection System Materials (TPSM): 3D MAT

    Data.gov (United States)

    National Aeronautics and Space Administration — The 3D MAT Project seeks to design and develop a game changing Woven Thermal Protection System (TPS) technology tailored to meet the needs of the Orion Multi-Purpose...

  17. 75 FR 33901 - Physical Protection of Byproduct Material

    Science.gov (United States)

    2010-06-15

    ... positioning system (GPS) tracking as a national requirement for vehicles transporting highly radioactive..., Maryland. NRC's Agencywide Documents Access and Management System (ADAMS): Publicly available documents... also proposed to establish physical protection systems to detect, assess, and respond to unauthorized...

  18. The adhesion characteristics of protective coating materials for the containment structure in nuclear power plants

    International Nuclear Information System (INIS)

    Lee, Sang-Kook; Shin, Jae-Chul

    2003-01-01

    Protective coating materials used in the containment structures should be durable for the designed 30 to 40 year lifetime of a nuclear power plant. At the present, these materials have not yet been developed. Therefore it is very important to keep the durability of the protective coating materials through persistent maintenance, and in order to achieve this, understanding the adhesion characteristics of the coating materials is of utmost importance. Therefore, this study attempts to find any methods for durability maintenance of these protective coating materials. To accomplish these aims, this study applied an experimental deterioration environment condition relevant to Loss of Coolant Accident (LOCA) and Main Steam Line Break (MSLB), categorized as of Design Basis Accident (DBA), onto steel liner plate specimens covered with protective coating materials. Adhesion tests were performed on these deteriorated coating materials to characterize the physical properties and through these tests, the quantitative adhesion characteristics according to the history of deterioration environment were found

  19. Radiation protection programmes for the transport of radioactive material. Safety guide

    International Nuclear Information System (INIS)

    2007-01-01

    This Safety Guide provides guidance on meeting the requirements for the establishment of radiation protection programmes (RPPs) for the transport of radioactive material, to optimize radiation protection in order to meet the requirements for radiation protection that underlie the Regulations for the Safe Transport of Radioactive Material. This Guide covers general aspects of meeting the requirements for radiation protection, but does not cover criticality safety or other possible hazardous properties of radioactive material. The annexes of this Guide include examples of RPPs, relevant excerpts from the Transport Regulations, examples of total dose per transport index handled, a checklist for road transport, specific segregation distances and emergency instructions for vehicle operators

  20. Legal Aspects of international cooperation in the physical protection of nuclear facilities and materials

    International Nuclear Information System (INIS)

    Herron, L.W.

    1981-10-01

    This paper provides a detailed analysis of developments in the number field having led the IAEA to promote international cooperation in ensuring adequate physical protection of nuclear facilities and materials. This work resulted in the establishment of recommendations and guidelines in this respect and culminated in the development of the 1980 Convention on the Physical Protection of Nuclear Materials. (NEA) [fr

  1. Concept of a Conducting Composite Material for Lightning Strike Protection

    OpenAIRE

    Katunin A.; Krukiewicz K.; Herega A.; Catalanotti G.

    2016-01-01

    The paper focuses on development of a multifunctional material which allows conducting of electrical current and simultaneously holds mechanical properties of a polymeric composite. Such material could be applied for exterior fuselage elements of an aircraft in order to minimize damage occurring during lightning strikes. The concept introduced in this paper is presented from the points of view of various scientific disciplines including materials science, chemistry, structural physics and mec...

  2. FIRE PROTECTION OF TIMBER STRUCTURES STRENGTHENED WITH FRP MATERIALS

    Directory of Open Access Journals (Sweden)

    Radek Zigler

    2015-12-01

    Full Text Available Modern, progressive methods of structures’ strengthening based on the use of composite materials composed of high strength fibers (carbon, glass, aramid or basalt and matrices based on epoxy resins brings, among many indisputable advantages (low weight, high effectiveness, easy application etc. also some disadvantages. One of the major disadvantages is a low fire resistance of these materials due to the low glass transition temperature Tg of the resin used. Based on an extensive research of strengthening of historic structures with FRP materials [1], the article outlines possible approaches to this problem, especially while strengthening timber load- bearing structures of historic buildings.

  3. Computerization of the safeguards analysis decision process

    International Nuclear Information System (INIS)

    Ehinger, M.H.

    1990-01-01

    This paper reports that safeguards regulations are evolving to meet new demands for timeliness and sensitivity in detecting the loss or unauthorized use of sensitive nuclear materials. The opportunities to meet new rules, particularly in bulk processing plants, involve developing techniques which use modern, computerized process control and information systems. Using these computerized systems in the safeguards analysis involves all the challenges of the man-machine interface experienced in the typical process control application and adds new dimensions to accuracy requirements, data analysis, and alarm resolution in the regulatory environment

  4. Dust Erosion Performance of Candidate Motorcase Thermal Protection Materials.

    Science.gov (United States)

    1980-03-10

    REFERENCE DESCRIPTION SOURCE NUMBER 4.01 NBR B. F. Goodrich Aerospace and Defense Products (Nitrile butadiene 500 South Main Street rubber ) Akron, Ohio...material degradation occurs. 5.3 BALLISTIC RANGES Ballistic ranges are widely used for reentry erosion testing for two reasons: 1) no other type of facility...DET REFERENCE OTHER COMMENTS NUMBER DESIGNATION 2002 KEVLAR-EPOXY STAGE 3 MOTORCASE MATERIAL MOTORCAS E 2402 NBR 68 2403 NBR 69 2404 NBR -19709-6A (60

  5. Protection of nuclear facilities and nuclear materials against malevolent actions

    International Nuclear Information System (INIS)

    Cornu, P.; Aurelle, J.; Jalouneix, J.

    2001-01-01

    The french approach for considering malevolent actions affecting the design and operation of nuclear facilities is aimed at determining the extent to which the facilities are protected. When carrying out these studies, operating organizations have to demonstrate that their are complying with the objectives set by the Competent Authority for reducing the risk of internal or external malevolent actions. The approach to be followed consist to determine the sensitivity of each zone and to estimate the vulnerability of the most critical zones to each type of aggression. The sensitivity can be defined by the level of the radiological consequences resulting from a malevolent action. The estimation of the vulnerability is made of the extent to which it is difficult to carry out a malevolent action. if need be, counter-measures are taken to protect zones for which the consequences would be unacceptable compared to the force of the aggression. Counter-measures are intended both to minimise sensitivity and make it more difficult to carry out the aggression envisaged. Acceptable consequences are taken as being those leading to levels of radioactive releases less than, or equal to, those taken into account in the facility safety case. This implies that the vulnerability of the most sensitive zones should be reduced to a minimum so that an acceptable level of protection can be provided for these areas. Emphasis will be paid on the defence in depth approach organized around prevention, management and mitigation measures. (authors)

  6. Celebral computerized tomography

    International Nuclear Information System (INIS)

    Lofteroed, B.; Sortland, O.

    1985-01-01

    Indications for cerebral computerized tomography (CT) and the diagnostic results from this examination are evaluated in 127 children. Pathological changes were found in 31 children, mostly based on such indications as increasing head size, suspicion of brain tumor, cerebral paresis, delayed psychomotor development and epileptic seizures. A list of indications for CT in children is given

  7. A cabinet for the handling or treatment of materials therein in a protected atmosphere

    International Nuclear Information System (INIS)

    Landy, J.J.

    1978-01-01

    A cabinet is described in which the atmosphere is arranged to move in a recirculatory filtered closed system. It is stated to be suitable for the handling of materials in a protected atmosphere, for example the handling of biohazardous materials, radioactive materials, etc. Full constructional details are given. (U.K.)

  8. Bioinspired Design of Building Materials for Blast and Ballistic Protection

    Directory of Open Access Journals (Sweden)

    Yu-Yan Sun

    2016-01-01

    Full Text Available Nacre in abalone shell exhibits high toughness despite the brittle nature of its major constituent (i.e., aragonite. Its specific structure is a major contributor to the energy absorption capacity of nacre. This paper reviews the mechanisms behind the performance of nacre under shear, uniaxial tension, compression, and bending conditions. The remarkable combination of stiffness and toughness on nacre can motivate the development of bioinspired building materials for impact resistance applications, and the possible toughness designs of cement-based and clay-based composite materials with a layered and staggered structure were discussed.

  9. The distribution property of shielding materials used in radiological protection

    International Nuclear Information System (INIS)

    Costa, Paulo R.

    1996-01-01

    A parametric model for the distribution of the radiation scattered by shielding materials is proposed. The advantages regarding to chemical composition or to linear attenuation coefficient of the media as a function of energy are presented. Comparative results between the model and experimental data are reported

  10. Protecting Superconducting HTS-Antennas by Meta-Material Cloaks

    Science.gov (United States)

    2014-04-30

    to the cloak are not quantified. Thus, one can only visually judge the performance of the cloaking ability of the structure. In this project, a...materials composed of only s-shaped resonators,” Phys. Rev. E, vol. 70, p. 057605, Nov 2004. 8, 9 [25] J. Pendry, A. Holden, D. Robbins , and W

  11. Coated silicon comprising material for protection against environmental corrosion

    Science.gov (United States)

    Hazel, Brian Thomas (Inventor)

    2009-01-01

    In accordance with an embodiment of the invention, an article is disclosed. The article comprises a gas turbine engine component substrate comprising a silicon material; and an environmental barrier coating overlying the substrate, wherein the environmental barrier coating comprises cerium oxide, and the cerium oxide reduces formation of silicate glass on the substrate upon exposure to corrodant sulfates.

  12. Protection of nuclear installations and materials against malevolent actions

    International Nuclear Information System (INIS)

    Aurelle, J.

    2001-01-01

    Full text: The approach adopted in France for considering malevolent actions affecting the design and operation of nuclear facilities is aimed at determining the extent to which the facilities are protected. When carrying out these studies, operating organizations have to demonstrate that they are complying with the objectives set by the Competent Authority for reducing the risk of internal or external malevolent actions. The operating organization studies are assessed by the technical support body of the Competent Authority. The technical support body submits the assessments to an interministerial advisory group that sends its comments and any specific technical instructions which may be necessary to the Competent Authority. The approach to be followed can be summed up as follows: 1) The sensitivity of each zone is determined; this can be characterised by the level of the radiological consequences resulting from a malevolent action. Sensitivity is determined by taking into account: the radioactive product inventory; possible accident situations; an estimate of the consequences of these accidents. Depending on the gravity of the consequences of a malevolent action, three types of zone have been defined: zones or systems at risk, when an action is not serious enough to lead to radiological consequences; to cause a significant accident, at least two zones or systems at risk have to be affected; critical zones or systems, when an action leads to radiological consequences deemed acceptable from a safety point of view; vital zones or systems, when an action leads to more serious radiological consequences than those taken into account in the safety case. 2) The vulnerability of the various zones to each type of aggression is estimated, in other words, an estimate is made of the extent to which it is difficult to carry out a malevolent action in the zone in question. The vulnerability assessment of the zones and systems identified previously can be broken down into two

  13. DOE transporation programs - computerized techniques

    Energy Technology Data Exchange (ETDEWEB)

    Joy, D.S.; Johnson, P.E.; Fore, C.S.; Peterson, B.E.

    1983-01-01

    One of the major thrusts of the transportation programs at the Oak Ridge National Laboratory has been the development of a number of computerized transportation programs and data bases. The U.S. Department of Energy (DOE) is supporting these efforts through the Transportation Technology Center at Sandia National Laboratories and the Tranportation Operations and Traffic Management (TOTM) organization at DOE Headquarters. Initially this project was centered upon research activities. However, since these tools provide traffic managers and key personnel involved in preshipment planning with a unique resource for ensuring that the movement of radioactive materials can be properly accomplished, additional interest and support is coming from the operational side of DOE. The major accomplishments include the development of two routing models (one for rail shipments and the other for highway shipments), an emergency response assistance program, and two data bases containing pertinent legislative and regulatory information. This paper discusses the mose recent advances in, and additions to, these computerized techniques and provides examples of how they are used.

  14. Advanced materials and protective coatings in aero-engines application

    OpenAIRE

    M. Hetmańczyk; L. Swadźba; B. Mendala

    2007-01-01

    Purpose: The following article demonstrates the characteristics of the materials applied as parts of aircraft engine turbines and the stationary gas turbines. The principal technologies for manufacturing the heat resistant coatings and the erosion and corrosion resistant coatings were characterized. Sample applications for the aforementioned coatings are presented: on turbine blades, compressor blades and on parts of combustion chambers of aircraft engines.Design/methodology/approach: The nic...

  15. Covering materials used in protected agriculture; Nogyoyo hifuku shizai

    Energy Technology Data Exchange (ETDEWEB)

    Naito, Y.

    1998-03-01

    Forty and a few years have passed away since the start of facilities agriculture using plastic covering materials. The facilities have been divided into heavily equipped type and simplified type. The former includes heating, ventilation, irrigation water, and nutritious solution culture facilities. The latter includes pipe house, tunnel, and rain shelter facilities. For the heavily equipped type, all season, long life-time and large-scale facilities have been diffused. Hard plates and hard films with durability equivalent to glass are used. Especially, utilization of hard films has been increased, recently. Soft films are also widely used for heavily equipped type facilities in spite of their disadvantage of taking large labor for renewal. However, enhancement of durability is also required for the soft films. Their life-time has become five years from the former one or two years. The significant problem of covering materials is the treatment of used plastics. Measures for enhancing the reproduction have been promoted. Furthermore, the development of naturally decomposed materials with biological and optical degradation properties has been also promoted. 11 refs., 2 figs., 2 tabs.

  16. Surface treatments for material protection in nuclear power plants

    International Nuclear Information System (INIS)

    De, P.K.; Gadiyar, H.S.

    1987-01-01

    The paper highlights some of the surface treatment methods used in nuclear power plants to improve their performance. The corrosion resistance of zirconium alloys results from the formation of an adherent and protective film of ZrO 2 . Graphite coating of zircaloy-2 cladding minimizes the susceptibility to environmental induced cracking. Magnetite formation during the hot conditioning operation improves the corrosion resistance of carbon steel as well as controls the spread of radioactivity. It has been illustrated how the surface treatment is helpful for redistributing residual stress to facilitate conversion of tensile stress to compressive stress to mitigate failures due to stress corrosion and fatigue corrosion. Inhibitors and passivators can modify the surface conditions (in situ) of condenser tubes and cooling water systems. These aspects have been dealt in the text of the paper. (author). 8 refs., 3 figures

  17. UV-Curable Hybrid Nanocomposite Coating to Protect Tether Polymer Materials, Phase I

    Data.gov (United States)

    National Aeronautics and Space Administration — To address the NASA need for coatings to protect and strengthen tether materials for Momentum-exchange Electrodynamic Reboost (MXER) technology, Luminit, LLC,...

  18. Physical protection in the transport of nuclear materials (Legal aspects of the domestic system)

    International Nuclear Information System (INIS)

    Novais, F.J.G.

    1978-04-01

    A study of the physical protection system is made. Emphasis is given to some considerations in the nuclear material transport area, mainly the details of the domestic system, from a juridic pont of view. (Author) [pt

  19. Utilization of Self-Healing Materials in Thermal Protection System Applications

    Data.gov (United States)

    National Aeronautics and Space Administration — The proposed project is the Utilization of Self-Healing Materials for Thermal Protection System (TPS) Applications. Currently, the technology for repairing TPS from...

  20. Resistance of gloves and protective clothing materials to permeation of cytostatic solutions

    OpenAIRE

    Sylwia Krzemińska; Małgorzata Pośniak; Małgorzata Szewczyńska

    2018-01-01

    Objectives The objective of the work was to determine the resistance of selected protective clothing and glove materials to permeation of cytostatics such as docetaxel, fluorouracil, and doxorubicin. Material and Methods The following glove materials were used: natural rubber latex (code A), acrylonitrile-butadiene rubber (code B) and chloroprene rubber (code C). In addition, we tested a layered material composed of a non-woven polyester (PES), a polypropylene (PP) film, ...

  1. 10 CFR 76.111 - Physical security, material control and accounting, and protection of certain information.

    Science.gov (United States)

    2010-01-01

    ... significance (Category III), and for protection of Restricted Data, National Security Information, Safeguards... 10 Energy 2 2010-01-01 2010-01-01 false Physical security, material control and accounting, and protection of certain information. 76.111 Section 76.111 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED...

  2. Radiation protection and the naturally occurring radioactive materials (NORM)

    International Nuclear Information System (INIS)

    Paschoa, A.S.; MacDowell, P.

    1996-01-01

    There are many industries dealing with naturally occurring radioactive materials (NORM), some of them without knowing that their industrial processes and/or their regular wastes involve radioactivity. However, an increasing number of industries that produce NORM wastes are being sued, wherever there is a legal framework to do so. In particular, NORM wastes produced for a long time by the oil industry became foci of legal battles in the United States and elsewhere. The ripple effect of these judicial battles will influence the decision making processes of NORM wastes producing industries, mostly because of the costs incurred by remedial and preventive actions concerning NORM contamination. The regulation of NORM will occur sooner or later, and such actions may become mandatory. A foreseeable consequence of such regulation is a change in attitude concerning the sources and materials associated with NORM. Among those industries likely to be affected one can mention: niobium; rare earth processing; oil production; phosphate; uranium mining and milling; zircon; water treatment; and waste water treatment. The paper will briefly review data on exempt concentration activities, as suggested by the basic safety standards based on realistic environmental and dosimetric models. These activity concentrations are compared with those found in a number of extractive industries, and may be used to establish derived limits from a pre-established dose limit. (author)

  3. Highly resolving computerized tomography

    International Nuclear Information System (INIS)

    Kurtz, B.; Petersen, D.; Walter, E.

    1984-01-01

    With the development of highly-resolving devices for computerized tomography, CT diagnosis of the lumbar vertebral column has gained increasing importance. As an ambulatory, non-invasive method it has proved in comparative studies to be at least equivalent to myelography in the detection of dislocations of inter-vertebral disks (4,6,7,15). Because with modern devices not alone the bones, but especially the spinal soft part structures are clearly and precisely presented with a resolution of distinctly below 1 mm, a further improvement of the results is expected as experience will increase. The authors report on the diagnosis of the lumbar vertebral column with the aid of a modern device for computerized tomography and wish to draw particular attention to the possibility of doing this investigation as a routine, and to the diagnostic value of secondary reconstructions. (BWU) [de

  4. Highly resolving computerized tomography

    Energy Technology Data Exchange (ETDEWEB)

    Kurtz, B.; Petersen, D.; Walter, E.

    1984-01-01

    With the development of highly-resolving devices for computerized tomography, CT diagnosis of the lumbar vertebral column has gained increasing importance. As an ambulatory, non-invasive method it has proved in comparative studies to be at least equivalent to myelography in the detection of dislocations of inter-vertebral disks (4,6,7,15). Because with modern devices not alone the bones, but especially the spinal soft part structures are clearly and precisely presented with a resolution of distinctly below 1 mm, a further improvement of the results is expected as experience will increase. The authors report on the diagnosis of the lumbar vertebral column with the aid of a modern device for computerized tomography and wish to draw particular attention to the possibility of doing this investigation as a routine, and to the diagnostic value of secondary reconstructions.

  5. Systematic Approach to Training and Professional Development Specialists of Physical Protection, Accounting and Control of Nuclear Materials in Ukraine

    International Nuclear Information System (INIS)

    Klos, Nataliia

    2014-01-01

    Conclusion: 1. Ukraine has created the State system for professional training, retraining and professional development of specialists in physical protection, accounting and control of nuclear materials. 2. Ukraine has founded profession physical protection, accounting and control of nuclear materials

  6. Computerized plant maintenance management

    International Nuclear Information System (INIS)

    Kozusko, A.M.

    1986-01-01

    The evolution of the computer has and continues to have a great impact on industry. We are in an adjustment cycle with the current computer evolution, and will need to adapt to make the changes for the coming decade. Hardware and software are continually being enhanced. Computers are becoming more powerful and will eventually provide an effective man-machine interface. This paper shares experiences encountered during implementations of computerized maintenance systems

  7. Computerized medical convocations

    International Nuclear Information System (INIS)

    Roche, Annie; Gilbert, Jean-Francois; Chiadot, Pierre; Vanzetto, Rene; Darnault, Jean

    1969-06-01

    Thanks to a close collaboration between the Medical and Social department and the Numerical Calculation Laboratory, a computerized convocation system has been implemented to reduce the administrative workload and to introduce more rigor in medical management, patient historical background and statistics. This work comprises: - a preliminary study of the data generating medical convocations and the related practical requirements; - the programming work according to these data; - the realisation of the mechano-graphical file covering the overall personnel [fr

  8. Collaborative Russian-US work in nuclear material protection, control and accounting at the Institute of Physics and Power Engineering. 3: Emphasis on site-wide issues

    International Nuclear Information System (INIS)

    Kuzin, V.V.; Pshakin, G.M.; Belov, A.P.

    1997-07-01

    During 1997, collaborative Russian-US nuclear material protection, control, and accounting (MPC and A) tasks at the Institute of Physics and Power Engineering (IPPE) in Obninsk, Russia are focusing increasingly on site-wide issues, though there is continued work at several major facilities: the Fast Critical Facility, the Technological Laboratory for Fuel Fabrication, and the (new and existing) Central Storage Facility. The collaborative work is being done with US Department of Energy National Laboratories. IPPE's emphasis on site-wide issues has resulted in the formation of a separate division for MPC and A. This new division reports directly to the IPPE Chief Engineer. It is a separate scientific and engineering operating division responsible for coordination and harmonization of MPC and A at IPPE, as well as for audit, assessment and inspection. By virtue of the organizational independence of this new division, IPPE has significantly strengthened the role of MPC and A. Two specific site-wide accomplishments are the consolidation of nuclear material from many buildings to a smaller number, and, as a major part of this strategy, the construction of a nuclear island surrounding the Fast Critical Facility and the new Central Storage Facility. Most of IPPE's weapons-grade nuclear materials will be concentrated within the nuclear island. The paper summarizes the following technical elements: computerized accounting, bar coding, weight measurements, gamma-ray measurements, tamper indicating devices, procedures for physical inventory taking and material balance closure, and video monitoring systems for storage and critical assembly areas

  9. Guidance and considerations for implementation of INFCIRC/225/Rev.3, the physical protection of nuclear material

    International Nuclear Information System (INIS)

    1997-09-01

    The Physical Protection of Nuclear Material, INFCIRC/225/Rev.3, provides recommendations for the physical protection of nuclear material against theft in use, storage and transport, whether national or international and whether peaceful or military, and contains provisions relating to the sabotage of nuclear material or facilities. The recommendations contained in INFCIRC/225/Rev.3 detail the elements that should be included in a State's system of physical protection. It also recognizes the adverse health and safety consequences arising from the theft of nuclear material and the sabotage of nuclear material or facilities. Most industrial and developing countries use these recommendations to some extent in the establishment and operation of their physical protection systems. Although INFCIRC/225/Rev.3 provides recommendations for protecting materials and facilities from theft or sabotage, it does not provide in-depth details for these recommendations. In June 1996, the IAEA convened a consultants meeting to consider this matter. This report is the result of continuing discussions and drafts over a period of nine months. The intent of this guidance is to provide a broader basis for relevant State organizations to prescribe appropriate requirements for the use of nuclear materials which are compatible with accepted international practice

  10. Application of radiation chemistry in materials modification and environmental protection

    International Nuclear Information System (INIS)

    Chmielewski, A.G.

    2007-01-01

    Radiation chemistry is a part of the physical chemistry similarly like photo-chemistry, plasma-chemistry, ultrasonic-chemistry etc. Ionizing radiation produces abundant secondary electrons. Following these primary events, the ions, secondary electrons and excited molecules undergo further transformations, exchanging charges and energy and reacting with surrounding molecules, thereby producing free radicals and other reactive species which finally evolve into new stable products. Three main sources of radiation are applied for radiation processing. These are electron accelerators, gamma sources and X-ray unit based on e-/X conversion process. Radiation processing was used early on for polymer modification. The intermediates formed during material irradiation can follow several reaction paths that result in disproportion, hydrogen abstraction, arrangements and/or the formation of new bonds. Nowadays, the modification of polymers covers radiation cross-linking, radiation-induced polymerization (graft polymerization and curing) and the degradation of polymers. Some polymers predominantly undergo crosslinking other degradation. However new techniques allow crosslinking of polymers which were considered to be degradable only, like PTFE and cellulose derivatives. Regarding natural polymers the biggest application concerns rubber pre-crosslinking in tire industry. The processing of natural polymers is also being developed to elaborate new biodegradable materials. The radiation crosslinked wires and cables show excellent heat resistance (long-term thermal stability and short-term thermal stability) as well as abrasion resistance. Other big application is crosslinking of XLPE type pipes which are widely used for hot water and floor heating [30]. Polybutelene terephthalate (PBT), which is a plastic for electronic industry, can be crosslinked by radiation and lead free soldering materials can be applied in such a case. This method of crosslinking is also applied to manufacture

  11. Innovative plant protection means prepared natural raw materials

    Directory of Open Access Journals (Sweden)

    Omar Lomtadze

    2018-03-01

    terms of growth and development index. It should also be noted that no harmful diseases were found on the treated seedlings.The developed compositional formulations can be successfully used for integrated protection of plants against pests and diseases. Their use is absolutely safe for the human and the environment. Keywords: Peach, Apple, Pests, Diseases, Acaricide, Fungicide

  12. Physical Protection of Nuclear Material and Nuclear Facilities (Implementation of INFCIRC/225/Revision 5). Implementing Guide

    International Nuclear Information System (INIS)

    2018-01-01

    This publication is the lead Implementing Guide in a suite of guidance on implementing the Nuclear Security Recommendations on Physical Protection of Nuclear Material and Nuclear Facilities (INFCIRC/225/Revision 5), IAEA Nuclear Security Series No. 13. It provides guidance and suggestions to assist States and their competent authorities in establishing, strengthening and sustaining their national physical protection regime and implementing the associated systems and measures, including operators’ physical protection systems. The structure of this publication is as follows. After this introduction, Section 2 describes the objectives of physical protection and the overall approach to managing the risks of the unauthorized removal of nuclear material and the sabotage of nuclear facilities. Section 3 provides guidance for the State and its competent authorities on the physical protection elements of the nuclear security regime; this guidance is based on the fundamental principles set out in the Recommendations publication. Section 4 provides guidance on the operator’s physical protection system and describes a systematic, integrated approach. Appendix I gives an annotated outline of the typical contents of an operator’s security plan. Appendix II provides similar guidance for the contingency plan. Appendix III provides a description of nuclear material aggregation that can be used to categorize nuclear material and determine the appropriate level of protection against unauthorized removal. Appendix IV presents a table of paragraph cross-references between the Recommendations publication and this Implementing Guide.

  13. Criteria and application methodology of physical protection of nuclear materials within the national and regional boundaries

    International Nuclear Information System (INIS)

    Rodriguez, C.E.; Cesario, R.H.; Giustina, D.H.; Canibano, J.

    1998-01-01

    Full text: The physical protection against robbery, diversion of nuclear materials and sabotage of nuclear installations by individuals or groups, has been for long time the reason of national and international concern. Even though, the obligation to create and implement an effective physical protection system for nuclear materials and installations in the territory of a given State, fall entirely on the State's Government, whether this obligation is fulfilled or not, and if it does, in what measure or up to what extent, it also concerns the rest of the States. Therefore, physical protection has become the reason for a regional co-operation. It is evident the need of co-operation in those cases where the physical protection efficiency within the territory of a given State depends also on the appropriate measures other States are taken, specially when dealing with materials been transported through national borders. The above mentioned constitute an important framework for the regional co-operation for the physical protection of nuclear materials. For that reason, the Nuclear Regulatory Authority established criteria and conditions aimed at mitigate diversions, robberies and sabotage to nuclear installations. As a working philosophy, it was established a simplify physical protection model of application in Argentina who, through the ARCAL No. 23 project, will be extrapolated to the whole Latin-American region, concluding that the application of the appropriated physical protection systems at regional level will lead to the strengthening of it at national level. (author) [es

  14. Aspects of investment protection in the case of raw material projects; Aspekte des Investitionsschutzes bei Rohstoffprojekten

    Energy Technology Data Exchange (ETDEWEB)

    Wolkewitz, Mathias [Wintershall Holding GmbH, Kassel (Germany). Bereich Recht, Steuern und Versicherungen; TU Clausthal (Germany). Inst. fuer Energierecht

    2011-04-15

    Addressing the question of investment protection currently is of particular importance under the tree aspects: (a) Due to the financial crisis and economic crisis, foreign investment in the years 2008 and 2009 have been drastically reduced; (b) There is a growing critique at the system of international investment protection; (c) For the first time, the Articles 206 and 207 of the Treaty of Lisbon of the European Union show a competence for foreign direct investment. These three aspects seem partly contradictory, but have a considerable changing potential in the area of investment protection. The author of the contribution under consideration describes the tools of investment protection as those are used for raw material projects. Subsequently the author picks out investment protection agreements and deals with some aspects that are important for practical applications in business companies. Raw material projects are projects for the exploration and production of oil and gas in foreign states.

  15. The National Shipbuilding Research Program, 1990 Ship Production Symposium, Paper No. 4B-1: Solving SARA Compliance with Computerized Hazardous Materials Tracking

    National Research Council Canada - National Science Library

    Johnston, Don; Schoenleber, Dave

    1990-01-01

    ...) has forced facilities to keep track of hazardous materials as never before. EPCRA contains five major reporting requirements including planning notification, emergency release notification, Material Safety Data Sheet (MSDS...

  16. Manual of use and accounting of radioactive material and procedures of radiological protection for nuclear medicine

    International Nuclear Information System (INIS)

    Chavez, Miguel

    1997-03-01

    This manual of use and accounting of material radioactive and procedures of radiological safety tries to facilitate workings of protection of material radioactive in services of medicine nuclear, during diagnosis (examinations with x-rays, or those that are made in nuclear medicine), or during the processing of diseases, mainly of the carcinomas (x-ray)

  17. Strengthened implementation of physical protection of nuclear material and nuclear facilities in the Republic of Korea

    International Nuclear Information System (INIS)

    Shim, H.-W.; Lee, J.-U.

    2005-01-01

    Full text: Since the 9.11 terror, strengthening physical protection has been an accelerated trend internationally. IAEA has been requesting that member states implement a strengthened physical protection of nuclear facilities on the basis of threat assessments. In order to cope with this demand, the Korean government promulgated the 'Law for Physical Protection and Radiological Emergency Preparedness (LPPRE)' as a substantial countermeasure against possible threats. Pursuant to LPPRE, which entered into force on February 16, 2004, nuclear enterprisers are obliged to implement an effective physical protection of nuclear materials, get approval for its physical protection system, and be constantly inspected on. The Ministry of Science and Technology (MOST) approved physical protection regulations of 24 domestic facilities operated by 14 enterprisers. National Nuclear management and Control Agency (NNCA) is entrusted with physical protection related duty and has been conducting physical protection inspection on nuclear materials in use, storage and transport. In addition, NNCA has established the methodology of threat assessment that entails organizing the threat assessment working group to develop a design basis threat (DBT). Korea is putting its best efforts to construct the threat assessment system and strengthen domestic physical protection regime in cooperation with competent authorities. (author)

  18. Order of 31 July 1987 on protection and control of nuclear materials carried by air

    International Nuclear Information System (INIS)

    1987-01-01

    This Order is part of a series of texts on protection and control of nuclear materials which include: the Act of 25 July 1980 and the Decree of 12 May 1981 made in its implementation and, as regards the specific aspect of protection and control of materials during transport, the Order of 26 March 1982 amended in 1986. The 1987 Order lays down the conditions which must be complied with by approved carriers (the French or the foreign holders of a licence under the above-mentioned Act of 1980) in case of transport of such materials by air [fr

  19. A Road map for Establishing the Physical Protection Regime of Nuclear Materials and Facilities

    International Nuclear Information System (INIS)

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

    2007-01-01

    The importance of physical protection for nuclear materials and facilities that can be an objective for terrorists has never been more stressed. The responsibility for physical protection within a State does not rest entirely with that state because cross-border transactions related to nuclear materials increase as nuclear related industries expand. The international community has prepared measures to strengthen the regime of physical protection such as the IAEA's proposal of the 'Nuclear Security Plan for 2006-2009' and UN's resolution on 'the International Convention for the Suppression of Acts of Nuclear Terrorism'. In order to cope with this, Korea has also made efforts to establish the implementation system for physical protection in the field of nuclear industries since the law for Physical Protection of Nuclear Material and Facility and Radiological Emergency Preparedness (LPPREP) was promulgated in 2004. The detailed plans should be prepared to accomplish this. This study has been performed to derive the items for establishing the regime of physical protection. The items derived were classified as short, mid and long-term depending on their characteristics and environmental circumstances. The regime of national physical protection will be established if the studies on these items are carried out successfully and tangible results are obtained

  20. Computerized operator decision aids

    International Nuclear Information System (INIS)

    Long, A.B.

    1984-01-01

    This article explores the potential benefits associated with the use of computers in nuclear plants by the operating crew as an aid in making decisions. Pertinent findings are presented from recently completed projects to establish the context in which operating decisions have to be made. Key factors influencing the decision-making process itself are also identified. Safety parameter display systems, which are being implemented in various forms by the nuclear industry, are described within the context of decision making. In addition, relevant worldwide research and development activities are examined as potential enhancements to computerized operator decision aids to further improve plant safety and availability

  1. Computerized procedures system

    Science.gov (United States)

    Lipner, Melvin H.; Mundy, Roger A.; Franusich, Michael D.

    2010-10-12

    An online data driven computerized procedures system that guides an operator through a complex process facility's operating procedures. The system monitors plant data, processes the data and then, based upon this processing, presents the status of the current procedure step and/or substep to the operator. The system supports multiple users and a single procedure definition supports several interface formats that can be tailored to the individual user. Layered security controls access privileges and revisions are version controlled. The procedures run on a server that is platform independent of the user workstations that the server interfaces with and the user interface supports diverse procedural views.

  2. Computerized spleen volumetry

    International Nuclear Information System (INIS)

    Jahnke, T.; Mohring, R.; Schertel, L.

    1981-01-01

    We examined in experimental studies and clinical investigations on 34 patients in how far volumetry of the spleen can be carried out with a commonly available program, a whole-body computerized tomograph (SOMATOM) and an analytic equipment (EVALUSKOP). In this connection the authors tried to find also other ways of spleen volumetry by means of this unit combination. Our final result was that the given program for the usage of labelled areas presents itself as the best-suited technique for spleen volumetry which is also applicable in practice. (orig./MG) [de

  3. Implementation of physical protection of nuclear material in Yugoslavia and Slovenia - recent and planned activities

    International Nuclear Information System (INIS)

    Pesic, M.; Nikolic, A.; Nikoli, D.; Stegnar, P.

    2002-01-01

    Full text: In more than ten last years region of South-Europe, especially countries originated from previous the Socialistic Federal Republics of Yugoslavia, are involved or surrounded, at least, by various conflicts including wars of different intensities. These unfavorable environment conditions have put additional focus at nuclear material kept in various institutions in the region. Following the IAEA recommendation on straighten the physical protection of nuclear material various actions are done or planned in the Yugoslavia and Slovenia to increase level of physical protection of nuclear material during its different usage and storage. Especial attention is drawn to update the administration rules, education of the involved personnel and redundancy of different physical protection modes of protection to prevent thieves and smuggling of nuclear material in the country or at country borders. The financial and experts help were offered by the IAEA at low level scale to Yugoslavia in 1996/97 to increase the physical protection of the fresh high-enriched uranium fuel stored and controlled regularly by the inspectors of the safeguard department of the IAEA. The further help and financial support is expected from the IAEA and relevant EU organization in aim to tighter the country borders to prevent the illegal traffic of nuclear material through the Europe. (author)

  4. Build Your Own Inventory System. Annual Cost: $100.00 (Approximate). Fixed Assets, Materials and Supplies. The Practical Elements for a Computerized, Continuing Inventory System in Schools and Use in Determining a Measure for Instructional Cost.

    Science.gov (United States)

    Payne, Arnold, Comp.

    This publication presents performance flow charts and other accompanying forms that are elements of an economical computerized continuing inventory system. The system described here is intended to serve school systems as an adequate fixed asset system and to provide a computerized inventory model that offers support for costs of future educational…

  5. Computerized adaptive testing item selection in computerized adaptive learning systems

    NARCIS (Netherlands)

    Eggen, Theodorus Johannes Hendrikus Maria; Eggen, T.J.H.M.; Veldkamp, B.P.

    2012-01-01

    Item selection methods traditionally developed for computerized adaptive testing (CAT) are explored for their usefulness in item-based computerized adaptive learning (CAL) systems. While in CAT Fisher information-based selection is optimal, for recovering learning populations in CAL systems item

  6. Lightweight Ablative and Ceramic Thermal Protection System Materials for NASA Exploration Systems Vehicles

    Science.gov (United States)

    Valentine, Peter G.; Lawrence, Timothy W.; Gubert, Michael K.; Milos, Frank S.; Kiser, James D.; Ohlhorst, Craig W.; Koenig, John R.

    2006-01-01

    As a collaborative effort among NASA Centers, the "Lightweight Nonmetallic Thermal Protection Materials Technology" Project was set up to assist mission/vehicle design trade studies, to support risk reduction in thermal protection system (TPS) material selections, to facilitate vehicle mass optimization, and to aid development of human-rated TPS qualification and certification plans. Missions performing aerocapture, aerobraking, or direct aeroentry rely on advanced heatshields that allow reductions in spacecraft mass by minimizing propellant requirements. Information will be presented on candidate materials for such reentry approaches and on screening tests conducted (material property and space environmental effects tests) to evaluate viable candidates. Seventeen materials, in three classes (ablatives, tiles, and ceramic matrix composites), were studied. In additional to physical, mechanical, and thermal property tests, high heat flux laser tests and simulated-reentry oxidation tests were performed. Space environmental effects testing, which included exposures to electrons, atomic oxygen, and hypervelocity impacts, was also conducted.

  7. An analysis of the development and application of plant protection UAV based on advanced materials

    Science.gov (United States)

    Huang, Yuan-hui; Wei, Neng; Quan, Zhi-cheng; Huang, Yu-rong

    2018-06-01

    The development and application of a number of advanced materials plant protection unmanned aerial vehicle (UAV) is an important part of the comprehensive production of agricultural modernization. The paper is taken as an example of Guangxi No. 1 agricultural service aviation science and Technology Co., Ltd. This paper introduces the internal and external environment of the research and development of the plant protection UAV for the advanced materials of the company. The external environment focuses on the role of the plant protection UAV on the development of the agricultural mechanization; the internal environment focuses on the advantages of the UAV in technology research, market promotion and application, which is imperative. Finally, according to the background of the whole industry, we put forward some suggestions for the developing opportunities and challenges faced by plant protection UAV, hoping to proving some ideas for operators, experts and scholars engaged in agricultural industry.

  8. Order of 26 March 1982 on the protection and control of nuclear materials during transport

    International Nuclear Information System (INIS)

    1982-01-01

    This Order was made in implementation of Act No. 80-572 of 25th July 1980 on protection and control of nuclear materials and in particular, of Decree No. 81-512 of 12th May 1981, which was itself made in pursuance of the Act. In accordance with the Decree, this Order determines the rules applicable to the protection and control of nuclear materials in course of carriage, especially in connection with the supervision of the conditions in which such transport is carried out and the authorities warned in case of an incident, accident or any occurrence whatsoever which is likely to delay or jeopardize execution of the planned transport operation or protection of the nuclear material concerned. (NEA) [fr

  9. Occupational radiation protection in the mining and processing of raw materials

    International Nuclear Information System (INIS)

    2004-01-01

    The mining and processing of uranium ore, thorium ore and other raw materials containing natural radionuclides are carried out in a number of Member States. There is a clear need to update the guidance on the radiation protection of the workers involved, and this Safety Guide provides such updated guidance. Material from two previous publications has been adapted for inclusion in this Safety Guide. These previous publications - Radiation Monitoring in the Mining and Milling of Radioactive Ores (Safety Series No. 95) and Radiation Protection of Workers in the Mining and Milling of Radioactive Ores (Safety Series No. 26, hereby superseded) - dealt principally with activities involving uranium ore and thorium ore. Activity concentrations of naturally occurring radionuclides are elevated in other mineral deposits such as heavy mineral sands and phosphate rock. Furthermore, high radon levels may be found in mines, irrespective of the activity concentrations of natural radionuclides in the raw material being extracted. In recognition of these circumstances, this Safety Guide is intended to apply also to the mining and processing of any raw material for which radiation protection measures need to be considered. The IAEA Safety Fundamentals publication on Radiation Protection and the Safety of Radiation Sources presents the principles, concepts and objectives of protection and safety. Safety requirements based on the objectives and principles specified in these Safety Fundamentals, including requirements for the protection of workers exposed to ionizing radiation, are established in the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources (the Basic Safety Standards or Bss). These requirements also reflect the recommendations of the International Commission on Radiological Protection (ICRP). Safety Guides provide recommendations on the basis of international experience on the fulfilment of the requirements

  10. Establishment of computerized numerical databases on thermophysical and other properties of molten as well as solid materials and data evaluation and validation for generating recommended reliable reference data

    Science.gov (United States)

    Ho, C. Y.

    1993-01-01

    The Center for Information and Numerical Data Analysis and Synthesis, (CINDAS), measures and maintains databases on thermophysical, thermoradiative, mechanical, optical, electronic, ablation, and physical properties of materials. Emphasis is on aerospace structural materials especially composites and on infrared detector/sensor materials. Within CINDAS, the Department of Defense sponsors at Purdue several centers: the High Temperature Material Information Analysis Center (HTMIAC), the Ceramics Information Analysis Center (CIAC) and the Metals Information Analysis Center (MIAC). The responsibilities of CINDAS are extremely broad encompassing basic and applied research, measurement of the properties of thin wires and thin foils as well as bulk materials, acquisition and search of world-wide literature, critical evaluation of data, generation of estimated values to fill data voids, investigation of constitutive, structural, processing, environmental, and rapid heating and loading effects, and dissemination of data. Liquids, gases, molten materials and solids are all considered. The responsibility of maintaining widely used databases includes data evaluation, analysis, correlation, and synthesis. Material property data recorded on the literature are often conflicting, diverging, and subject to large uncertainties. It is admittedly difficult to accurately measure materials properties. Systematic and random errors both enter. Some errors result from lack of characterization of the material itself (impurity effects). In some cases assumed boundary conditions corresponding to a theoretical model are not obtained in the experiments. Stray heat flows and losses must be accounted for. Some experimental methods are inappropriate and in other cases appropriate methods are carried out with poor technique. Conflicts in data may be resolved by curve fitting of the data to theoretical or empirical models or correlation in terms of various affecting parameters. Reasons (e.g. phase

  11. Effect of Flow Velocity on Corrosion Rate and Corrosion Protection Current of Marine Material

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Seong Jong [Kunsan National University, Kunsan (Korea, Republic of); Han, Min Su; Jang, Seok Ki; Kim, Seong Jong [Mokpo National Maritime University, Mokpo (Korea, Republic of)

    2015-10-15

    In spite of highly advanced paint coating techniques, corrosion damage of marine metal and alloys increase more and more due to inherent micro-cracks and porosities in coatings formed during the coating process. Furthermore, flowing seawater conditions promote the breakdown of the protective oxide of the materials introducing more oxygen into marine environments, leading to the acceleration of corrosion. Various corrosion protection methods are available to prevent steel from marine corrosion. Cathodic protection is one of the useful corrosion protection methods by which the potential of the corroded metal is intentionally lowered to an immune state having the advantage of providing additional protection barriers to steel exposed to aqueous corrosion or soil corrosion, in addition to the coating. In the present investigation, the effect of flow velocity was examined for the determination of the optimum corrosion protection current density in cathodic protection as well as the corrosion rate of the steel. It is demonstrated from the result that the material corrosion under dynamic flowing conditions seems more prone to corrosion than under static conditions.

  12. The role of spin–orbit coupling in topologically protected interface states in Dirac materials

    International Nuclear Information System (INIS)

    Abergel, D S L; Balatsky, Alexander V; Edge, Jonathan M

    2014-01-01

    We highlight the fact that two-dimensional (2D) materials with Dirac-like low energy band structures and spin–orbit coupling (SOC) will produce linearly dispersing topologically protected Jackiw–Rebbi modes at interfaces where the Dirac mass changes sign. These modes may support persistent spin or valley currents parallel to the interface, and the exact arrangement of such topologically protected currents depends crucially on the details of the SOC in the material. As examples, we discuss buckled 2D hexagonal lattices such as silicene or germanene, and transition metal dichalcogenides such as MoS 2 . (paper)

  13. A procedure for a mechanical evaluation of an undefined osteo-protective material.

    Science.gov (United States)

    Marques, Marco; Terroso, Miguel; Freitas, Ricardo; Marques, AntÓnio Torres; Gabriel, Joaquim; Simoes, Ricardo

    2015-02-01

    Falls represent a major care and cost problem to health and social services world-widely, since 50% of falls result in an injury. In this work, is proposed a methodology to evaluate protective pads materials and geometry performance, in order to reduce impact results in a fall event. Since the material properties and the pad geometry are the key factors to make the protection possible when a fall event occurs, our approach relies on the use of mechanical tests to evaluate the properties of the material and in the study of the pad response during a fall. For this, were used compression, tensile and instrumented falling weight tests, that allow a fully characterization of the materials that can be employed in the protective pads. Likewise, to gather precise information on falls events, in order to study the pad response during a fall, a set of laboratory fall trials were created using a camera-less inertial motion capture (mocap) system. This allow the acquisition of dynamic information of falls, namely acceleration and velocity that can be used to create a finite element analysis (FEA) model, where different segments from the human body can be evaluated when the protective pad is associated to it. Through the proposed methodology, different materials and pad geometries can be studied towards maximizing the performance of protection pads for falls. The mocap system allows the acquisition of fall data, and also the creation of a human body geometrical model, representative of the fall. From the mechanical trials, was showed that the spacer fabric embedded with silicone has the higher ability to reduce the peak force in case of impact when compared with all the other specimens. The compression and the tensile tests allow the mechanical definition of the material, and with this the material definition on the FEA model. Copyright © 2014 Elsevier Ltd. All rights reserved.

  14. 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

  15. Implementation of physical protection of nuclear material in Yugoslavia and Slovenia - recent and planned activities

    International Nuclear Information System (INIS)

    Pesic, M.; Nikolic, A.; Nikolic, D.; Stegnar, P.

    2002-09-01

    In more than ten last years region of South-East Europe (especially countries originated from previous the Socialistic Federal Republics of Yugoslavia) was involved (or surrounded, at least) by various conflicts, including wars of different intensities. These unfavourable conditions have put additional focus at nuclear material stored in various institutions in the region. Following the recommendations of the International Atomic Energy Agency (IAEA) on straighten the physical protection of nuclear material, various actions were done or are planned in the Yugoslavia and Slovenia in aim to increase level of physical protection of nuclear material during its different usage and storage. Especial attention is drawn to update the administration rules, education of the involved personnel and redundancy of different physical protection modes to prevent stealing and smuggling of nuclear material in both the countries or at country borders. The financial and expert help at low-level scale were offered by the IAEA and US government to Yugoslavia in 1996/97. It was used to increase the physical protection of fresh high-enriched uranium fuel stored and controlled regularly by the inspectors of the Safeguard Department of the IAEA. The further help and financial support is expected from the IAEA, USA and relevant European Union (EU) organisations in aim to tighter the borders of both the countries to prevent the illegal traffic of nuclear materials through the Europe. (author)

  16. Proposal for guidelines for the physical protection of nuclear materials, plants and transports in Denmark

    International Nuclear Information System (INIS)

    1978-03-01

    The guidelines are based on recommendations in the IAEA's ''Physical Protection of Nuclear Material,'' INFCIRC/225/rev.1. In accordance with practice in other countries, the guidelines give more detailed requirements for the protection of reactor plants than those given in the IAEA's present recommendations, which put more emphasis on the protection of nuclear materials. The measures to be taken for nuclear plants, or nuclear transports, are proposed made to fit the potential risk that the more closely defined actions imply. It is suggested that the more detailed rules for the scope of the protection of plants or materials should be laid down by the National Agency on the basis of recommendations made by the Inspectorate of Nuclear Installations, which in turn are based on the safety documentation of the plant/material owners. It is further proposed that the National Agency, again on a recommendation from the Inspectorate, should lay down more detailed guidelines for the reporting of changes in stocks or transports of nuclear materials. (author)

  17. Replacement of Ablators with Phase-Change Material for Thermal Protection of STS Elements

    Science.gov (United States)

    Kaul, Raj K.; Stuckey, Irvin; Munafo, Paul M. (Technical Monitor)

    2002-01-01

    As part of the research and development program to develop new Thermal Protection System (TPS) materials for aerospace applications at NASA's Marshall Space Flight Center (MSFC), an experimental study was conducted on a new concept for a non-ablative TPS material. Potential loss of TPS material and ablation by-products from the External Tank (ET) or Solid Rocket Booster (SRB) during Shuttle flight with the related Orbiter tile damage necessitates development of a non-ablative thermal protection system. The new Thermal Management Coating (TMC) consists of phase-change material encapsulated in micro spheres and a two-part resin system to adhere the coating to the structure material. The TMC uses a phase-change material to dissipate the heat produced during supersonic flight rather than an ablative material. This new material absorbs energy as it goes through a phase change during the heating portion of the flight profile and then the energy is slowly released as the phase-change material cools and returns to its solid state inside the micro spheres. The coating was subjected to different test conditions simulating design flight environments at the NASA/MSFC Improved Hot Gas Facility (IHGF) to study its performance.

  18. Measuring the spectral emissivity of thermal protection materials during atmospheric reentry simulation

    Science.gov (United States)

    Marble, Elizabeth

    1996-01-01

    Hypersonic spacecraft reentering the earth's atmosphere encounter extreme heat due to atmospheric friction. Thermal Protection System (TPS) materials shield the craft from this searing heat, which can reach temperatures of 2900 F. Various thermophysical and optical properties of TPS materials are tested at the Johnson Space Center Atmospheric Reentry Materials and Structures Evaluation Facility, which has the capability to simulate critical environmental conditions associated with entry into the earth's atmosphere. Emissivity is an optical property that determines how well a material will reradiate incident heat back into the atmosphere upon reentry, thus protecting the spacecraft from the intense frictional heat. This report describes a method of measuring TPS emissivities using the SR5000 Scanning Spectroradiometer, and includes system characteristics, sample data, and operational procedures developed for arc-jet applications.

  19. Computerized tomographic system

    International Nuclear Information System (INIS)

    Godbarsen, R.; Barrett, D.M.; Garrott, P.M.; Foley, L.E.; Redington, R.W.; Lambert, T.W.; Edelheit, L.S.

    1981-01-01

    A computerized tomographic system for examining human breasts is described in detail. Conventional X-ray scanning apparatus has difficulty in achieving the levels of image definition and examination speeds required for mass screening. A novel method of scanning successive layers of the breast with a rotating X-ray beam is discussed and details of the control circuitry and sequence steps are given. The method involves immersing the breast in an inner fluid (e.g. water) filled container which is stationary during an examination and is surrounded by a large outer container which is also filled with the fluid; the inner and outer containers are always maintained at a constant height and the X-ray absorption across the fan-shaped beam is as close as possible to constant. (U.K.)

  20. Advantages obtained in radiation protection when using computerized radiography tests - CR (digital) in processing plants; Vantagens obtidas em radioprotecao quando do uso do ensaio de radiografia computadorizada - RC (digital) em plantas de processo

    Energy Technology Data Exchange (ETDEWEB)

    Jose, Joao Carlos Videira; Milani, Hilton Sergio B.; Paes, Eliseu Almir de Oliveira; Boita, Mario de [ARCtest Servicos Tecnicos de Inspecao e Manutencao Industrial Ltda., Sao Paulo, SP (Brazil)]. E-mail: tecnica@arctest.com.br; Souza, Laercio de; Serra, Flavio Augusto dos Santos [PETROBRAS, Paulinia, SP, RJ (Brazil). Refinaria do Planalto Paulista (REPLAN)]. E-mails: laerciosouza@petrobras.com.br; serra@petrobras.com.br

    2002-07-01

    During the year 2000, the ARCtest initiated the development of the research for adapting the Computerized Radiography - CR, originally conceived for medical applications, for the Industry, trying initially to attend the requirements of the processing plants, concerning to the detection of deterioration mechanisms (evaluation of the piping integrity). Due to the obtained excellent results, the possibility of utilization the Computerized Radiography - CR in the radiographic inspection were studied during the shutdown of the Catalytic Cracking Unit of the PETROBRAS-REPLAN, specifically in the replacement of the CO boiler superheater, where a large number of the small diameter welded joints have been predicted.

  1. Protection of environmental contamination by radioactive materials and remediation of environment

    International Nuclear Information System (INIS)

    2003-05-01

    This report consisted of the environmental contamination of radioactive and non-radioactive materials. 38 important accident examples of environmental contamination of radioactive materials in the world from 1944 to 2001 are stated. Heavily polluted areas by accidents are explained, for example, Chernobyl, atomic reactor accidents, development of nuclear weapon in USA and USSR, radioactive waste in the sea. The environmental contamination ability caused by using radioactive materials, medical use, operating reactor, disposal, transferring, crashing of airplane and artificial satellite, release are reported. It contains measurements and monitor technologies, remediation technologies of environmental contamination and separation and transmutation of radioactive materials. On the environmental contamination by non-radioactive materials, transformation of the soil contamination in Japan and its control technologies are explained. Protection and countermeasure of environmental contamination of radioactive and non-radioactive materials in Japan and the international organs are presented. There are summary and proposal in the seventh chapter. (S.Y.)

  2. Physical protection of export/import and transportation of nuclear material in the Slovak Republic

    International Nuclear Information System (INIS)

    Vaclav, J

    2002-01-01

    Full text: The paper contains short overview about average amount of nuclear materials transported on the territory of the Slovak Republic in a year, and the physical protection of these nuclear materials. There are several types of transportation and export/import of nuclear materials in the SR: fresh fuel import; import of other unirradiated nuclear materials (e.g. depleted uranium, natural uranium); export of unirradiated nuclear materials (e.g. natural uranium); internal transportation of fresh fuel; internal transportation of other unirradiated nuclear materials; internal transportation of spent fuel. The main objective of the nuclear regulatory authority SR is to supervise observation of the national legislation as follows: the act no. 130 / 1998 on peaceful use of nuclear energy; UJD SR's regulation no. 186/1999 which details the physical protection of the nuclear facilities, nuclear materials, and radioactive waste (following requirements of INFCIRC 225 / Rev. 4); UJD SR's regulation no. 284 / 1999 which details conditions of nuclear material and radioactive wastes transportation. (author)

  3. Dealing with the regional challenge of physical protection of nuclear materials

    International Nuclear Information System (INIS)

    Paschoa, A.S.

    2002-01-01

    Full text: The problem of protecting sensitive fissile and fissionable nuclear materials of misuses by governments has been the subject of the convention on physical protection of nuclear material (CPPNM), which entered into force on February 8, 1987. However, in May 2001 the final report of the expert meeting had already recognized 'a clear need to strengthen the international physical protection regime'. The board of governors of the International Atomic Energy Agency (IAEA) decided then to convene a group, which would meet in Vienna from 3 to 7 December 2001, to draft on amendment to the CPPNM. The tragic occurrences of September 11, 2001, however, changed the then generally accepted view on the problem of physical protection, because nuclear materials had to be protected from falling into the hands of terrorists rather than of governments thirst of nuclear sensitive materials. Moreover, crude explosive devices could be made by terrorists, or hired scientists, using readily available radioactive materials, like 226 Ra or 137 Cs to inflict damage to civilians. Thus physical protection of those and other radioactive materials became an instant challenge for national and international authorities to prevent the use of such materials in terrorist actions. The prevention of illicit trafficking of radioactive materials is now in the priority list of these authorities. Fortunately; an international conference on 'Measures to Detect, Intercept and Respond to the Illicit Uses of Nuclear Materials and Radioactive Sources' was held in Stockholm, Sweden, in May 2001. An IAEA document - GOV/2001/37-GC(45)/20 - recommended in its plan of activities a series of projects to be implemented between 2002 and 2005, which included developing and providing assistance for the application of: (i) standards for physical protection of nuclear materials and nuclear facilities in member states; (ii) norms and guidelines for nuclear material accounting and control in member states; (iii

  4. Text of the Convention on the Physical Protection of Nuclear Material

    International Nuclear Information System (INIS)

    1979-11-01

    The Final Act of the Meeting of Governmental Representatives to Consider the Drafting of a Convention on the Physical Protection of Nuclear Material was signed on 26 October 1979. According to paragraph 11 of the Final Act, ''The Meeting recommended that the text of the Convention be transmitted for information to the Twenty-Third General Conference of the International Atomic Energy Agency.''

  5. Use of respirators for protection of workers against airborne radioactive materials

    International Nuclear Information System (INIS)

    Revoir, W.H.

    1990-01-01

    The various types of respirators and the requirements for an effective respirator program are outlined. The use of specific types of respirators to protect workers against inhalation of airborne radioactive materials is discussed. Problems encountered in using respirators in the nuclear industry which have resulted in worker injury and death are described

  6. The effect of air permeability of chemical protective clothing material on clothing vapour resistance

    NARCIS (Netherlands)

    Havenith, G.; Vuister, R.; Wammes, L.

    1996-01-01

    One of the major problems associated with Chemical Warfare Protective Clothing (CW) is the additional heat load created by the garments. For CW-overgarments, research in the direction of reducing material thickness and thus heat and vapour resistance have not resulted in major improvements. The

  7. Announcement concerning the convention on the physical protection of nuclear material of March 3, 1980

    International Nuclear Information System (INIS)

    1987-01-01

    The State Council of the German Democratic Republic ratified the convention on physical protection of nuclear material which was signed on 21 May 1980 and deposited with the Director General on 5 February 1981. The convention entered into force in accordance with its article 19 on 8 February 1987. The German and English texts of this convention are presented

  8. Strengthening global practices for protecting nuclear material (NUMAT). Book of Abstracts

    International Nuclear Information System (INIS)

    Steinhaeusler, F.; Heissl, C.

    2002-08-01

    The International Conference on Physical Protection 'Strengthening Global Practices for Protecting Nuclear Material' was organized by the Institute of Physics and Biophysics, Salzburg University in cooperation with/supported by the European Commission, Lawrence Livermore National Laboratory, European Forum of the Stanford University's Institute for International Studies and Austria Institute for European Security. Its purpose was fostering exchange of information on the policy and technical aspects require to ensure the security of nuclear material around the world. There is a general concern that the international community needs to establish effective measures to counter theft, sabotage, and other illicit uses of nuclear fissile and other radioactive materials. The main subjects addressed by this conference were: a) global and local threat development and 'design basis'; b) standards for physical protection (PP), its adequacy and future needs; c) national practices in PP of nuclear materials (how to strengthen national security culture?); d) current R and D in security and detection technologies (identification of focus points for future R and D); e) programmes to aid in training, design, and implementation of physical protection systems (how to improve efficiency and assure sustainability of assistance programmes?). (nevyjel)

  9. GCD TechPort Data Sheets Thermal Protection System Materials (TPSM) Project

    Science.gov (United States)

    Chinnapongse, Ronald L.

    2014-01-01

    The Thermal Protection System Materials (TPSM) Project consists of three distinct project elements: the 3-Dimensional Multifunctional Ablative Thermal Protection System (3D MAT) project element; the Conformal Ablative Thermal Protection System (CA-TPS) project element; and the Heatshield for Extreme Entry Environment Technology (HEEET) project element. 3D MAT seeks to design, develop and deliver a game changing material solution based on 3-dimensional weaving and resin infusion approach for manufacturing a material that can function as a robust structure as well as a thermal protection system. CA-TPS seeks to develop and deliver a conformal ablative material designed to be efficient and capable of withstanding peak heat flux up to 500 W/ sq cm, peak pressure up to 0.4 atm, and shear up to 500 Pa. HEEET is developing a new ablative TPS that takes advantage of state-of-the-art 3D weaving technologies and traditional manufacturing processes to infuse woven preforms with a resin, machine them to shape, and assemble them as a tiled solution on the entry vehicle substructure or heatshield.

  10. Selection of sorption material for tests of pesticide permeation through protective clothing fabrics.

    Science.gov (United States)

    Krzemińska, Sylwia; Nazimek, Teresa

    2004-01-01

    The paper presents the results of studies on selecting a solid sorption material for absorbing liquid crop protection agents which permeate samples of protective clothing fabrics. The sorption materials were investigated and selected with an assumption that they should have a high recovery coefficient for biologically active substances, used as active ingredients in crop protection agents, at a presumed, acceptably high level. The selected substances were determined with a gas chromatograph equipped with an electron capture detector (dichlorvos, cypermethrin and 2,4-D) and a nitrogen-phosphorus detector (carbofuran). The tests demonstrated that polypropylene melt-blown type unwoven cloth had high recovery coefficients for all 4 active ingredients proposed for the study. The highest recovery coefficient, -.97, was obtained for carbofuran. The recovery coefficients obtained for the 3 remaining substances were lower: .89 for cypermethrin and 2,4-D, and .84 for dichlorvos.

  11. The declaration regime: An efficient tool to improve control and protection of nuclear materials in France

    International Nuclear Information System (INIS)

    Pillette-Cousin, L.

    2001-01-01

    Full text: The French Government set up a national safeguards system under the authority of the Ministry for Industry to control nuclear materials within national boundaries and to ensure physical protection for nuclear materials, even for the small quantities held by users in industrial, medical and research areas. The main nuclear materials detained by small owners are depleted uranium and thorium. These materials are present in manufactured equipment (radiation shielding in industrial gammagraphy and radiotherapy, collimation devices and other accessories) which are used or unused, which may be damaged or left as scraps. The French protection and control system of nuclear materials is an original system based on detailed and comprehensive regulations, taking into account in a specific way the small users of nuclear materials. The decree no. 81-512 of 12 May 1981 establishes three different regimes: licensing, declaration and exemption, according to the nature and quantity of nuclear materials involved. Typically, the declaration regime applies to quantities of depleted uranium or thorium, greater than 1 kg and lower than 500 kg. The Order of 14 March 1984 sets the requirements related to the control and physical protection of nuclear materials in the frame of the declaration regime. A declaration must be established every year by the operator and sent to the IPSN, acting as technical support body of the national authority. This declaration provides the stock of all nuclear materials held by the operator and stock variations occurred during the previous year, including the identification of senders and receivers. Before fulfilling its annual declaration, the operator must carry out a physical inventory of all nuclear material, both used and unused. The declaration also describes the main features concerning facility layout related to surveillance and physical protection of materials. With respect to physical protection requirements, nuclear materials should be

  12. Novel material and structural design for large-scale marine protective devices

    International Nuclear Information System (INIS)

    Qiu, Ang; Lin, Wei; Ma, Yong; Zhao, Chengbi; Tang, Youhong

    2015-01-01

    Highlights: • Large-scale protective devices with different structural designs have been optimized. • Large-scale protective devices with novel material designs have been optimized. • Protective devices constructed of sandwich panels have the best anti-collision performance. • Protective devices with novel material design can reduce weight and construction cost. - Abstract: Large-scale protective devices must endure the impact of severe forces, large structural deformation, the increased stress and strain rate effects, and multiple coupling effects. In evaluation of the safety of conceptual design through simulation, several key parameters considered in this research are maximum impact force, energy dissipated by the impactor (e.g. a ship) and energy absorbed by the device and the impactor stroke. During impact, the main function of the ring beam structure is to resist and buffer the impact force between ship and bridge pile caps, which could guarantee that the magnitude of impact force meets the corresponding requirements. The means of improving anti-collision performance can be to increase the strength of the beam section or to exchange the steel material with novel fiber reinforced polymer laminates. The main function of the buoyancy tank is to absorb and transfer the ship’s kinetic energy through large plastic deformation, damage, or friction occurring within itself. The energy absorption effect can be improved by structure optimization or by the use of new sandwich panels. Structural and material optimization schemes are proposed on the basis of conceptual design in this research, and protective devices constructed of sandwich panels prove to have the best anti-collision performance

  13. Pseudo-icosahedral Cr55Al232 -δ as a high-temperature protective material

    Science.gov (United States)

    Rosa, R.; Bhattacharya, S.; Pabla, J.; He, H.; Misuraca, J.; Nakajima, Y.; Bender, A. D.; Antonacci, A. K.; Adrip, W.; McNally, D. E.; Zebro, A.; Kamenov, P.; Geschwind, G.; Ghose, S.; Dooryhee, E.; Ibrahim, A.; Tritt, T. M.; Aronson, M. C.; Simonson, J. W.

    2018-03-01

    We report here a course of basic research into the potential suitability of a pseudo-icosahedral Cr aluminide as a material for high-temperature protective coatings. Cr55Al232 -δ [ δ =2.70 (6 ) ] exhibits high hardness at room temperature as well as low thermal conductivity and excellent oxidation resistance at 973 K, with an oxidation rate comparable to those of softer, denser benchmark materials. The origin of these promising properties can be traced to competing long-range and short-range symmetries within the pseudo-icosahedral crystal structure, suggesting new criteria for future materials research.

  14. Nuclear materials management handbook. Safeguards, physical protection of nuclear material. 1995 ed.

    International Nuclear Information System (INIS)

    1995-01-01

    Now, very safe and stable supply of electric power has become to be obtained by nuclear energy, and Japan has steadily promoted nuclear power as the basic energy that contributes to overcome the unstable structure of energy supply in Japan highly depending on foreign countries, as shown in the long term plan of the research, development and utilization of nuclear power. Great progress was observed in nuclear fuel recycling in Japan such as the attainment of initial criticality of the prototype FBR 'Monju' and the start of construction of the commercial fuel reprocessing plant in Rokkasho. Recently the recognition of the importance of nuclear substance management has heightened, and the measures for maintaining and strengthening the reliability of nuclear nonproliferation system are investigated. It is important that Japan strictly observes the nuclear nonproliferation system based on the NPT which was extended infinitely. In this handbook, the outline of the measures for nuclear nonproliferation and safeguard and the protection of nuclear substances, the treaties and agreements and the national laws related to these are described. (K.I.)

  15. Physical protection of small amounts of nuclear material or contaminated parts

    International Nuclear Information System (INIS)

    Zipper, R.

    2002-01-01

    In July 2001 an incident was recognized where a worker occupied with decontamination of structures in a shut down reprocessing plant for spent fuel illegally removed a small amount of radioactive material from the facility site. The investigations exhibited that he brought this material to the apartment of his partner in life and she incorporated significantly α-activity in the form of plutonium. Immediately after the incident was discovered the supervisory authorities and the operating company of the facility took action to minimize the harms to third parties arising from the radioactive material released and to prevent a similar event to occur. As the overall inventory of radioactive material in the shut down facility at the time the theft occurred was below the limit where measures of physical protection are required by the German regulatory work discussions were raised on consequences to be drawn from this incident to close this obvious gap. The German Federal Ministry for Environment, Nature Protection and Reactor Safety (BMU) as the superior competent authority therefore ordered GRS to draft a set of fundamental requirements for future rules to make a repetition of the initiating incident unlikely. Further discussions of the authorities involved on supplementary rules and guidelines aiming to better protect small amounts of radioactive material from being illegally removed out of nuclear facilities and laboratories are based on these fundamentals defined by GRS but not yet finished. (orig.)

  16. Hazardous materials management and control program at Oak Ridge National Laboratory - environmental protection

    International Nuclear Information System (INIS)

    Eisenhower, B.M.; Oakes, T.W.

    1982-01-01

    In the Federal Register of May 19, 1980, the US Environmental Protection Agency promulgated final hazardous waste regulations according to the Resource Conservation and Recovery Act (RCRA) of 1976. The major substantive portions of these regulations went into effect on November 19, 1980, and established a federal program to provide comprehensive regulation of hazardous waste from its generation to its disposal. In an effort to comply with these regulations, a Hazardous Materials Management and Control Program was established at Oak Ridge National Laboratory. The program is administered by two Hazardous Materials Coordinators, who together with various support groups, ensure that all hazardous materials and wastes are handled in such a manner that all personnel, the general public, and the environment are adequately protected

  17. Materials and means for protection of personnel performing liquidation of the Chernobyl' NPP acident consequences

    International Nuclear Information System (INIS)

    Pavlenko, Yu.N.; Sysoev, V.N.; Talachev, A.S.; Frid, E.S.

    1992-01-01

    Composite materials (CM) on the basis of lead has been developed. Special polyethylene-polyisobutylene mixture or polyethylene were used as binding materials. This CM was made as plates with film pressed surface. Sheet of CM with 10 mm thickness may attenuate gamma radiation till 10 times. Cast polymer composition based on polyurethane has been developed for containment of the leed sheets. This composition was capable of hadening in operation process and having technical parameters needed for production of workpieces. Sn-50, Ce-58, Gd-64, W-74, Bi-83 were used for low-energy gamma radiation protection. They were introduced as powders of the elements or their mixtures in dissimilar polymer binders. The materials with high protective parameters were worked out. 1 fig

  18. Meeting Radiation Protection Requirements and Reducing Spacecraft Mass - A Multifunctional Materials Approach

    Science.gov (United States)

    Atwell, William; Koontz, Steve; Reddell, Brandon; Rojdev, Kristina; Franklin, Jennifer

    2010-01-01

    Both crew and radio-sensitive systems, especially electronics must be protected from the effects of the space radiation environment. One method of mitigating this radiation exposure is to use passive-shielding materials. In previous vehicle designs such as the International Space Station (ISS), materials such as aluminum and polyethylene have been used as parasitic shielding to protect crew and electronics from exposure, but these designs add mass and decrease the amount of usable volume inside the vehicle. Thus, it is of interest to understand whether structural materials can also be designed to provide the radiation shielding capability needed for crew and electronics, while still providing weight savings and increased useable volume when compared against previous vehicle shielding designs. In this paper, we present calculations and analysis using the HZETRN (deterministic) and FLUKA (Monte Carlo) codes to investigate the radiation mitigation properties of these structural shielding materials, which includes graded-Z and composite materials. This work is also a follow-on to an earlier paper, that compared computational results for three radiation transport codes, HZETRN, HETC, and FLUKA, using the Feb. 1956 solar particle event (SPE) spectrum. In the following analysis, we consider the October 1989 Ground Level Enhanced (GLE) SPE as the input source term based on the Band function fitting method. Using HZETRN and FLUKA, parametric absorbed doses at the center of a hemispherical structure on the lunar surface are calculated for various thicknesses of graded-Z layups and an all-aluminum structure. HZETRN and FLUKA calculations are compared and are in reasonable (18% to 27%) agreement. Both codes are in agreement with respect to the predicted shielding material performance trends. The results from both HZETRN and FLUKA are analyzed and the radiation protection properties and potential weight savings of various materials and materials lay-ups are compared.

  19. Steps to implement the legal and regulatory infrastructure for physical protection of nuclear material in Peru

    International Nuclear Information System (INIS)

    Ramirez Quijada, R.

    2001-01-01

    Full text: The signature of Peru to become part of the Convention of Physical Protection of Nuclear Material in 1995 has implied an obligation to formalize the legal and regulatory infrastructure for this purpose. As first step, physical protection measures were formalized on the two nuclear facilities: one critical assembly of zero power (RP0) and another research reactor of 10 Mw thermal power (RP10). Both of the installations use low enriched uranium nuclear fuel (Material and Testing Material - MTR type). On the other side, even thorium was put in perspective to control; currently it is being used for non-nuclear purposes and has not been included inside the physical protection measures. Its physical and chemical form and its small quantity do not warrant for applying the Convention. The physical protection measures implemented in the research reactor are well depicted and it is concluded that the physical protection system meets the recommendations of INFCIRC/225/Rev.3. The critical facility (RP0), as having nuclear material categorized III, has implemented a less restrictive system but enough to meet the requirements. In 1999 an evaluation of all physical protection systems was performed for these two nuclear installations. This evaluation took into account the recommendations of INFCIRC/225/Rev.4. The general conclusion was that the performance of physical protection system was suitable to the categories of nuclear material - II and III - and that the installations where nuclear material is used were suitably protected against non-authorized or illegal removal of nuclear material and sabotage. However, some of components of the system were not appropriately working and could make all of the system weak. Another of the identified problems was the lack of a rule on physical protection and also the lack of the Design Basis Threat, although this fact was well known due the social conditions in the country. The second undertaking has been to prepare the rule on

  20. Radiation Protection training WEB site to hold pedagogical material for developing courses a distance way

    International Nuclear Information System (INIS)

    Marco, M.; Rodriguez, M.; Hernando, E.; Falcon, S.; Rodriguez, M.; Villarroel, R.

    2003-01-01

    Radiation Protection Training (RPT) System in Spain are is well defined in the local local regulations related to radioactive facilities licensing and radiation protection. A system of personnel licenses is established considering two levels of required radiation protection training-supervisor and operator according to responsibilities assigned during the operation of the radioactive facilities. This paper present the major advances already done in the educational web site maintained on the CIEMAT server and accessible through the CSN web. The project includes training material for sixteen applied courses and the design of a educational web site to hold pedagogical material for developing distant learning courses. The main objective of this project is to provide training materials for course organisers, trainers and for professional participants and to promote the exchange of expertise between workers involved in all activities using radiation sources. The project also aims to provide necessary mechanism for standardisation of the radiation protection knowledge made available to the exposed workers, including theoretical and practical training. The developed training material included in the project will cover all uses of radioactive sources including medical diagnosis. The web site is being developed of provide educational material on a modular design and in Spanish. The paper presents the initial results of this useful tool for practitioners. Courses are based on core modules with basic and specific modules involving different targets groups, and the contents can be easily adapted for other target groups. For each one of the modules should be included in the web site: objectives, syllabus, lessons and practical sessions, demo and lab exercises, etc. The project includes training tools for sixteen courses based in the standard syllabus content in the Spanish legal framework. In the next future complete materials for trainers will be available to case courses

  1. Application of Advanced Materials Protecting from Influence of Free Space Environment

    Science.gov (United States)

    Dotsenko, Oleg; Shovkoplyas, Yuriy

    2016-07-01

    High cost and low availability of the components certified for use in the space environment forces satellite designers to using industrial and even commercial items. Risks associated with insufficient knowledge about behavior of these components in radiation environment are parried, mainly, by careful radiating designing of a satellite where application of special protective materials with improved space radiation shielding characteristics is one of the most widely used practices. Another advantage of protective materials application appears when a satellite designer needs using equipment in more severe space environment conditions then it has been provided at the equipment development. In such cases only expensive repeated qualification of the equipment hardness can be alternative to protective materials application. But mostly this way is unacceptable for satellite developers, being within strong financial and temporal restrictions. To apply protective materials effectively, the developer should have possibility to answer the question: "Where inside a satellite shall I place these materials and what shall be their shape to meet the requirements on space radiation hardness with minimal mass and volume expenses?" At that, the minimum set of requirements on space radiation hardness include: ionizing dose, nonionizing dose, single events, and internal charging. The standard calculative models and experimental techniques, now in use for space radiation hardness assurance of a satellite are unsuitable for the problem solving in such formulation. The sector analysis methodology, widely used in satellite radiating designing, is applicable only for aluminium shielding and doesn't allow taking into account advantages of protective materials. The programs simulating transport of space radiations through a substance with the use of Monte-Carlo technique, such as GEANT4, FLUKA, HZETRN and others, are fully applicable in view of their capabilities; but time required for

  2. Benefits of a relational database for computerized management

    International Nuclear Information System (INIS)

    Shepherd, W.W.

    1991-01-01

    This paper reports on a computerized relational database which is the basis for a hazardous materials information management system which is comprehensive, effective, flexible and efficient. The system includes product information for Material Safety Data Sheets (MSDSs), labels, shipping, and the environment and is used in Dowell Schlumberger (DS) operations worldwide for a number of programs including planning, training, emergency response and regulatory compliance

  3. Computerized analysis of brain perfusion parameter images

    International Nuclear Information System (INIS)

    Turowski, B.; Haenggi, D.; Wittsack, H.J.; Beck, A.; Aurich, V.

    2007-01-01

    Purpose: The development of a computerized method which allows a direct quantitative comparison of perfusion parameters. The display should allow a clear direct comparison of brain perfusion parameters in different vascular territories and over the course of time. The analysis is intended to be the basis for further evaluation of cerebral vasospasm after subarachnoid hemorrhage (SAH). The method should permit early diagnosis of cerebral vasospasm. Materials and Methods: The Angiotux 2D-ECCET software was developed with a close cooperation between computer scientists and clinicians. Starting from parameter images of brain perfusion, the cortex was marked, segmented and assigned to definite vascular territories. The underlying values were averages for each segment and were displayed in a graph. If a follow-up was available, the mean values of the perfusion parameters were displayed in relation to time. The method was developed under consideration of CT perfusion values but is applicable for other methods of perfusion imaging. Results: Computerized analysis of brain perfusion parameter images allows an immediate comparison of these parameters and follow-up of mean values in a clear and concise manner. Values are related to definite vascular territories. The tabular output facilitates further statistic evaluations. The computerized analysis is precisely reproducible, i. e., repetitions result in exactly the same output. (orig.)

  4. Physical protection system of nuclear material in the Federal Republic of Germany

    International Nuclear Information System (INIS)

    Bueker, H.; Jungclaus, D.; von Eyss, H.J.; von Osten, W.

    1980-01-01

    The objective of physical protection, its statutory and other bases as well as the parties involved in the licensing process are described. The facilities are grouped in categories reflecting their hazard potentials: the possibility of a theft of nuclear fuels in an approach similar to INFCIRC 225 and, in addition, the possibility of a release of radioactive materials. Physical protection follows the concept of detection, alert of police force, delay, prevention of the act by police force. The schematic layout of a Category I facility is presented

  5. Detection capabilities and accuracy requirements of concentrations of radioactive material in air for radiation protection purposes

    International Nuclear Information System (INIS)

    Brodsky, A.

    1987-01-01

    Recent developments in the formulation of detection capability and accuracy criteria for bioassay measurements will be interpreted and adapted to provide similar criteria for the measurement of air concentrations of radioactive material for radiation protection purposes. Considerations of accuracy will be related to the known variability of measurement processes, as well as the uncertainties in the calculated limits of intake that serve as the basis of regulatory and voluntary standards of practice. Formulations and criteria will be presented for minimum detection amounts (MDA) and precision and bias of measurements for radiation protection purposes. 17 references

  6. Regulatory problems relating to physical protection of nuclear plants and materials in Italy

    International Nuclear Information System (INIS)

    Nocera, F.

    1981-10-01

    Although the questions raised by physical protection have an international charater, it is important to know of national regulations in that field since exchange of information and study of common problems help to achieve satisfactory results. This paper analyses the Italian situation, by illustrating legislative and administrative actions undertaken as well as the practices adopted in Italy to meet problems of prevention of malevolent acts against nuclear installations and substances, until such time an Act is passed in this respect. Finally, the author is in favour of the 1980 Convention of Physical Protection of Nuclear Material being ratified soon by a large number of countries. (NEA) [fr

  7. Resistance of gloves and protective clothing materials to permeation of cytostatic solutions.

    Science.gov (United States)

    Krzemińska, Sylwia; Pośniak, Małgorzata; Szewczyńska, Małgorzata

    2018-01-15

    The objective of the work was to determine the resistance of selected protective clothing and glove materials to permeation of cytostatics such as docetaxel, fluorouracil, and doxorubicin. The following glove materials were used: natural rubber latex (code A), acrylonitrile-butadiene rubber (code B) and chloroprene rubber (code C). In addition, we tested a layered material composed of a non-woven polyester (PES), a polypropylene (PP) film, and a non-woven PP used for protective coats (code D). The cytostatics were analyzed by liquid chromatography with diode array detection. The tested samples were placed in a purpose-built permeation cell modified to be different from that specified in the standard EN 6529:2001. The tested materials were characterized by good resistance to solutions containing 2 out of the 3 selected cytostatics: doxorubicin and 5-fluorouracil, as indicated by a breakthrough time of over 480 min. Equally high resistance to permeation of the third cytostatic (docetaxel) was exhibited by natural rubber latex, acrylonitrile-butadiene rubber, and chloroprene rubber. However, docetaxel permeated much more readily through the clothing layered material, compromising its barrier properties. It was found that the presence of additional components in cytostatic preparations accelerated permeation through material samples, thus deteriorating their barrier properties. Int J Occup Med Environ Health 2018;31(3):341-350. This work is available in Open Access model and licensed under a CC BY-NC 3.0 PL license.

  8. Innovative protection cookbook

    International Nuclear Information System (INIS)

    Lambert, D.L.

    2002-01-01

    Full text: A large portion of the international community relies on expert judgment and military expertise to form the protection strategy of weapons-grade nuclear materials. This approach can be less than effectual for two primary reasons. First, much of the nuclear material that needs the most protection is not in a static form and located in easily secured storage locations. Some of the most effective measures for protection of in-process material are administrative and procedural in nature. There are basic protection differences between countries just like there are differences in baking bread. However, the necessary steps to produce bread are basically the same around the world. Certain ingredients are required to give it flavor, make it rise, and have a certain texture. So it is in the development of protection systems. A measure of intrusion detection, some access controls and searches, a pinch of computerized accounting, a layer of delay barriers, and a smidgen of armed response--and the basis for a 'cookbook' is born. Any and all protection systems can begin with simple elements that can be just as effective as the most sophisticated modern components. This paper will describe some of those simple, but effective, innovative protection measures. (author)

  9. Computerized tomography in myotonic dystrophy

    International Nuclear Information System (INIS)

    Gellerich, I.; Mueller, D.; Koch, R.D.

    1986-01-01

    Besides clinical symptoms, progress and electromyography computerized tomography improves the diagnostics of myotonic dystrophy. Even small changes in muscular structure are detectable and especially the musculus soleus exhibits early and pronounced alterations. By means of density distribution pattern an improved characterization of the disease is possible. Additional information is obtained by cerebral computerized tomography. Atrophy of brain tissue is to be expected in all patients with myotonic dystrophy. (author)

  10. Computerized radiation treatment planning

    International Nuclear Information System (INIS)

    Laarse, R. van der.

    1981-01-01

    Following a general introduction, a chain consisting of three computer programs which has been developed for treatment planning of external beam radiotherapy without manual intervention is described. New score functions used for determination of optimal incidence directions are presented and the calculation of the position of the isocentre for each optimum combination of incidence directions is explained. A description of how a set of applicators, covering fields with dimensions of 4 to 20 cm, for the 6 to 20 MeV electron beams of a MEL SL75-20 linear accelerator was developed, is given. A computer program for three dimensional electron beam treatment planning is presented. A microprocessor based treatment planning system for the Selectron remote controlled afterloading system for intracavitary radiotherapy is described. The main differences in treatment planning procedures for external beam therapy with neutrons instead of photons is discussed. A microprocessor based densitometer for plotting isodensity lines in film dosimetry is described. A computer program for dose planning of brachytherapy is presented. Finally a general discussion about the different aspects of computerized treatment planning as presented in this thesis is given. (Auth.)

  11. A Computerized Approach to Trickle-Process, Random Assignment.

    Science.gov (United States)

    Braucht, G. Nicholas; Reichardt, Charles S.

    1993-01-01

    Procedures for implementing random assignment with trickle processing and ways they can be corrupted are described. A computerized method for implementing random assignment with trickle processing is presented as a desirable alternative in many situations and a way of protecting against threats to assignment validity. (SLD)

  12. Synthesis, characterization and catalytic activity of acid-base bifunctional materials through protection of amino groups

    Energy Technology Data Exchange (ETDEWEB)

    Shao, Yanqiu [College of Chemistry, Jilin University, Changchun 130023 (China); College of Chemistry, Mudanjiang Normal University, Mudanjiang 157012 (China); Liu, Heng; Yu, Xiaofang [College of Chemistry, Jilin University, Changchun 130023 (China); Guan, Jingqi, E-mail: guanjq@jlu.edu.cn [College of Chemistry, Jilin University, Changchun 130023 (China); Kan, Qiubin, E-mail: qkan@mail.jlu.edu.cn [College of Chemistry, Jilin University, Changchun 130023 (China)

    2012-03-15

    Graphical abstract: Acid-base bifunctional mesoporous material SO{sub 3}H-SBA-15-NH{sub 2} was successfully synthesized under low acidic medium through protection of amino groups. Highlights: Black-Right-Pointing-Pointer The acid-base bifunctional material SO{sub 3}H-SBA-15-NH{sub 2} was successfully synthesized through protection of amino groups. Black-Right-Pointing-Pointer The obtained bifunctional material was tested for aldol condensation. Black-Right-Pointing-Pointer The SO{sub 3}H-SBA-15-NH{sub 2} catalyst containing amine and sulfonic acid groups exhibited excellent acid-basic properties. -- Abstract: Acid-base bifunctional mesoporous material SO{sub 3}H-SBA-15-NH{sub 2} was successfully synthesized under low acidic medium through protection of amino groups. X-ray diffraction (XRD), N{sub 2} adsorption-desorption, transmission electron micrographs (TEM), back titration, {sup 13}C magic-angle spinning (MAS) NMR and {sup 29}Si magic-angle spinning (MAS) NMR were employed to characterize the synthesized materials. The obtained bifunctional material was tested for aldol condensation reaction between acetone and 4-nitrobenzaldehyde. Compared with monofunctional catalysts of SO{sub 3}H-SBA-15 and SBA-15-NH{sub 2}, the bifunctional sample of SO{sub 3}H-SBA-15-NH{sub 2} containing amine and sulfonic acid groups exhibited excellent acid-basic properties, which make it possess high activity for the aldol condensation.

  13. Durable protection of the surface of wood used outdoors: material constraints, problems and approaches to solutions

    Directory of Open Access Journals (Sweden)

    Merlin A.

    2018-01-01

    Full Text Available The aesthetic durability of wooden structures is a major challenge for the use of this material in construction. Wood is used for its technical performances but also for its architectural qualities and its aesthetic perception. The premature aging of the wooden structures is detrimental because these disorders, even if they do not affect the strength of the structures, are mostly irremediable. The surface protection of wood is generally ensured by the use of a finish, whose essential role is to protect wood from climatic aggressions (water, solar radiation, oxygen, .... The secondary wood processing industry consists of a series of manufacturing and processing activities, each containing a portion of the added value of the product. The application of a finish on a wood-based work is usually the last and most visible step in this value chain.In outdoor use, the protection of the wood surface with transparent finishes is not yet sufficiently durable to be able to compete with materials used in industrial carpentry such as PVC or aluminum. Opaque finishes generally provide more durable protection but they mask the appearance of the wood sought by users.With the aim of positioning wood in this construction sector, research on transparent finishes has focused on the efficiency and improvement of the durability of the protection of the surface appearance of structures. Faced with climatic aggressions, the optimum conservation of a structure is not only linked to the performance of the finish but also to the characteristics of the wood material. In particular, in order to fulfill its protective function, the finish film must be able to follow the dimensional variations of the wood it covers without breaking and without detachment. In addition to the criteria for the effectiveness of finishes in the protection of structures, the environmental impact must be considered with increasing attention. Currently, more than 80% of composite or solid wood

  14. Conception for the protection of mineable raw materials in the Land of Brandenburg (Germany)

    International Nuclear Information System (INIS)

    Kopf, M.

    1995-01-01

    The pit and quarry industry in Brandenburg will within a few years the same importance as the lignite industry. Both industries together may have up to 20 000 employees beyond the year 2000. The same number of employees could result in the enterprises of local and other subcontractors and mine suppliers. The government of Brandenburg creates at present the legal prerequisites to secure the supply with mineable raw materials. The regulation of the protection of mineable raw materials is proposed to be realised within the scope of the second plan for the development of the country, and within the regional plannings. The protection of the basic conditions for mining industries is a permanent task for administration and politics. By encouraged engagement in the case of opposed interests, those of mining can be considered with acceptable results provided the parties are ready to compromise. (orig.) [de

  15. Role of physical protection and safeguards technology used to Nuclear Material Security

    International Nuclear Information System (INIS)

    Djoko-Irianto, Ign.

    2005-01-01

    The presence of nuclear materials at any nuclear facility must be in secure and must be known as safeguards purpose such as its position, from or type and amount. The clarification of the amount be reported to the national regulatory body and International Atomic Energy Agency (IAEA) as the International regulatory body. The national regulatory body and IAEA will then verify that report. The verification must be done to know there is no difference of the amount, and to give the assurance to the International community that any diversion of safeguarded nuclear material from civil use to a prescribed military purpose would be detected. To carry out verification, several verification techniques such as non-destructive analysis, surveillance, unattended and remote monitoring and environmental sampling are explained to convey the impression how those techniques are implemented. According to the security requirement, the physical protection system including all components of physical protection system have to be effectively designed

  16. Concepts on integration of physical protection and material accounting functions in a safeguards system

    International Nuclear Information System (INIS)

    Reynolds, D.A.

    1981-01-01

    Concepts on integration of physical protection and material accounting systems to enhance overall safeguards capability are developed and presented. Integration is approached by coordinating all safeguards information through a safeguards coordination center. This center represents a higher level in a communication, data-processing, and decision-making structure which is needed for efficient real-time operation of the integrated system. The safeguards coordination center functions to assess alarm and warning data required to resolve threats in the safeguards system, coordinate information and interaction involving the material accounting, physical protection, and facility monitoring and control systems, and present a single unified interface for interaction with facility management, facility operations, safeguards system personnel, and response forces

  17. Multiscale Modeling of Carbon/Phenolic Composite Thermal Protection Materials: Atomistic to Effective Properties

    Science.gov (United States)

    Arnold, Steven M.; Murthy, Pappu L.; Bednarcyk, Brett A.; Lawson, John W.; Monk, Joshua D.; Bauschlicher, Charles W., Jr.

    2016-01-01

    Next generation ablative thermal protection systems are expected to consist of 3D woven composite architectures. It is well known that composites can be tailored to achieve desired mechanical and thermal properties in various directions and thus can be made fit-for-purpose if the proper combination of constituent materials and microstructures can be realized. In the present work, the first, multiscale, atomistically-informed, computational analysis of mechanical and thermal properties of a present day - Carbon/Phenolic composite Thermal Protection System (TPS) material is conducted. Model results are compared to measured in-plane and out-of-plane mechanical and thermal properties to validate the computational approach. Results indicate that given sufficient microstructural fidelity, along with lowerscale, constituent properties derived from molecular dynamics simulations, accurate composite level (effective) thermo-elastic properties can be obtained. This suggests that next generation TPS properties can be accurately estimated via atomistically informed multiscale analysis.

  18. Material protection control and accounting program activities at the Urals electrochemical integrated plant

    International Nuclear Information System (INIS)

    McAllister, S.

    1997-01-01

    The Urals Electrochemical Integrated Plant (UEIP) is the Russian Federation's largest uranium enrichment plant and one of three sites in Russia blending high enriched uranium (HEU) into commercial grade low enriched uranium. UEIP is located approximately 70 km north of Yekaterinburg in the closed city of Novouralsk (formerly Sverdlovsk- 44). DOE's MPC ampersand A program first met with UEIP in June of 1996, however because of some contractual issues the work did not start until September of 1997. The six national laboratories participating in DOE's Material Protection Control and Accounting program are cooperating with UEIP to enhance the capabilities of the physical protection, access control, and nuclear material control and accounting systems. The MPC ampersand A work at UEIP is expected to be completed during fiscal year 2001

  19. 10th meeting of the International Conference on Protection of Materials and Structures from Space Environment

    CERN Document Server

    Tagawa, Masahito; Kimoto, Yugo; Protection of Materials and Structures From the Space Environment

    2013-01-01

    The goals of the 10th International Space Conference on “Protection of Materials and Structures from Space Environment” ICPMSE-10J, since its inception in 1992, have been to facilitate exchanges between members of the various engineering and science disciplines involved in the development of space materials, including aspects of LEO, GEO and Deep Space environments, ground-based qualification, and in-flight experiments and lessons learned from operational vehicles that are closely interrelated to disciplines of the atmospheric sciences, solar-terrestrial interactions and space life sciences. The knowledge of environmental conditions on and around the Moon, Mars, Venus and the low Earth orbit as well as other possible candidates for landing such as asteroids have become an important issue, and protecting both hardware and human life from the effects of space environments has taken on a new meaning in light of the increased interest in space travel and colonization of other planets.  And while many materia...

  20. Considerations on Dop (Depth Of Penetration) Test for Evaluation of Ceramics Materials Used in Ballistic Protection

    Science.gov (United States)

    Popa, Ioan-Dan; Dobriţa, Florin

    2017-12-01

    Tremendous amount of funds and other resorces were invested in studying the response of ceramic materials under ballistic impact, the main goal being to find a way to increase the protection of soldiers and the vehicles used in the modern battlespace. Using of ceramic materials especially carbon based (carbides), nitrogen based (nitrides) and oxygen based (oxides) ceramics in order to increase the protection level of ballistic equipment could be, sometimes, a big challenge when trying to use the proper test in order to evaluate and compare their performances. The role of the tests is to provide a better understanding of their response in different situations and, as a consequence, to make them more efficient as armour components through future improvements. The paper presents shortly the main tests which are used and eventually standardised for evaluating the ballistic behaviour of the ceramics and other armour components, with a special focus to DOP (Depth of Penetration) Tests.

  1. International conference in Stockholm to address protection of nuclear material and radioactive sources from illicit trafficking

    International Nuclear Information System (INIS)

    2001-01-01

    The Conference will look at approaches for enhancing security of material in general as well as protecting facilities against terrorism and sabotage. More specifically it will address measures for interception and response to illicit trafficking and discuss the practices and measures currently being used to minimize the possibilities of the unauthorized removal and movement of nuclear materials and critical equipment. It will also consider the importance of closer co-operation with law enforcement authorities and intelligence agencies and the necessity of applying new technologies to this effort

  2. Plasma-aided surface technology for modification of materials referred to fire protection

    International Nuclear Information System (INIS)

    Dineff, P.; Gospodinova, D.; Kostova, L.; Vladkova, T.; Chen, E.

    2008-01-01

    There has been considerable interest in dielectric barrier air discharge at atmospheric pressure and room temperature over the past decade due to the increased number of industrial applications. New plasma-aided capillary impregnation technology for flame spreading stop and fire protection of porous materials was developed. Research, based on thermogravimetric analysis (TGA), differential thermal analysis (DTA), and differential scanning calorimetry (DSC), proves that plasma-chemical surface pre-treatment exert material change on chemical interaction between phosphorus containing flame retardant and wood matrix (Pinus sylvestris, Bulgaria; Pseudotsuga, Canada)

  3. 11th International Space Conference on Protection of Materials and Structures from Space Environment

    CERN Document Server

    2017-01-01

    The proceedings published in this book document and foster the goals of the 11th International Space Conference on “Protection of Materials and Structures from Space Environment” ICPMSE-11 to facilitate exchanges between members of the various engineering and science disciplines involved in the development of space materials. Contributions cover aspects of interaction with space environment of LEO, GEO, Deep Space, Planetary environments, ground-based qualification and in-flight experiments, as well as lessons learned from operational vehicles that are closely interrelated to disciplines of atmospheric sciences, solar-terrestrial interactions and space life sciences.

  4. Upgrade of the Nuclear Material Protection, Control and Accounting System at the VNIIEF Industrial Zone

    International Nuclear Information System (INIS)

    Lewis, J.C.; Maltsev, V.; Singh, S.P.

    1999-01-01

    The Industrial Zone at the Russian Federal Nuclear Center/All-Russian Scientific Research Institute of Experimental Physics (RFNC/VNEEF) consists of ten guarded areas with twenty two material balance areas (A and As). The type of facilities in the Industrial Zone include storage sites, machine shops, research facilities, and training facilities. Modernization of the Material Protection, Control and Accounting (MPC and A) System at the Industrial Zone started in 1997. This paper provides a description of, the methodology/strategy used in the upgrade of the MFC and A system

  5. Physical protection of nuclear materials: Experience in regulation, implementation and operations. Proceedings of a conference

    International Nuclear Information System (INIS)

    1998-01-01

    The conference was held at IAEA Headquarters in Vienna from 10 to 14 November 1997. It was attended by 162 registered participants from 42 countries and eight international organizations. The 58 papers presented dealt with the experience of regulators, designers and facility operators, including response forces, in meeting the demands and requirements in this changing area of physical protection of nuclear materials and facilities. Individual abstracts were prepared for each of the papers. Topics covered include contemporary and emerging issues, experience in regulation, implementation at facilities, program assessment and cooperation, hardware and software, illicit trafficking in nuclear materials, and transportation

  6. Raising awareness about protection and control of nuclear materials held by 'small-scale holders'

    International Nuclear Information System (INIS)

    Ladsous, D.; Coulie, E.; Giorgio, M.

    2013-01-01

    In France, the activities carried out by the 'small-scale holders' of nuclear materials are organized by a specific regulatory system which defines in a detailed way their obligations and the means of control of the government. The first part of the article presents the legal framework relating to the use of nuclear materials by small-scale holders in civilian fields. The importance of the declaration of the nuclear material inventory is clearly emphasized and must be prepared and transmitted to the Institute for Radiological Protection and Nuclear Safety (IRSN) every year. The second part describes how this declaration is used to provide basic information for the competent Ministry and the inspectors to check the correct application of the regulatory requirements relating to physical protection and to the control of nuclear materials. Finally, the last part presents the on-site inspections carried out by sworn and accredited inspectors under the authority of the competent Authority, which provide an overall picture and allow an evaluation of the risks of theft, loss or diversion of these materials. (authors)

  7. Radiation protection - Monitoring of workers occupationally exposed to a risk of internal contamination with radioactive material

    International Nuclear Information System (INIS)

    2006-01-01

    In the course of employment, individuals might work with radioactive materials that, under certain circumstances, could be taken into the body. Protecting workers against risks of incorporated radionuclides requires the monitoring of potential intakes and/or the quantification of actual intakes and exposures. The selection of measures and programmes for this purpose requires decisions concerning methods, techniques, frequencies etc. for measurements and dose assessment. The criteria permitting the evaluation of the necessity of such a monitoring programme or for the selection of methods and frequencies of monitoring usually depend upon the legislation, the purpose of the radiation protection programme, the probabilities of potential radionuclide intakes, and the characteristics of the materials handled. This International Standard offers guidance for the decision whether a monitoring programme is required and how it should be designed. Its intention is to optimise the efforts for such a monitoring programme consistent with legal requirements and with the purpose of the radiation protection programme. Recommendations of international expert bodies and international experience with the practical application of these recommendations in radiation protection programmes have been considered in the development of this International Standard. Its application facilitates the exchanges of information between authorities, supervisory institutions and employers. The International Standard is not a substitute for legal requirements. In the International Standard, the word 'shall' is used to denote a requirement and no deviation is allowed. The word 'should' is used to denote a recommendation from which justified deviations are allowed. The word 'may' is used to denote permission

  8. Discussion of and guidance on the optimization of radiation protection in the transport of radioactive material

    International Nuclear Information System (INIS)

    1986-05-01

    The document provides guidance on one of the components of the system of dose limitation as it applies to the transport of radioactive material, namely the optimization of radiation protection. It focuses on the following parts of the transport system: design, maintenance, preparation for transport, transport, storage-in-transit and handling and it considers occupational and public exposures. The application is intended mainly for those transport situations within the regulatory requirements where potential radiation exposures could be beneficially reduced

  9. The Physical Protection of Nuclear Material; Proteccion Fisica Delos Materiales Nucleares

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1993-09-15

    Physical protection against the theft or unauthorized diversion of nuclear materials and against the sabotage of nuclear facilities by individuals or groups has long been a matter of national and international concern. Although responsibility for establishing and operating a comprehensive physical protection system for nuclear materials and facilities within a State rests entirely with the Government of that State, it is not a matter of indifference to other States whether and to what extent that responsibility is fulfilled. Physical protection has therefore become a matter of international concern and co-operation. The need for international cooperation becomes evident in situations where the effectiveness of physical protection in one State depends on the taking by other States also of adequate measures to deter or defeat hostile actions against nuclear facilities and materials, particularly when such materials are transported across national frontiers [French] La proteccion fisica contra el robo o la desviacion no autorizada de materiales nucleares y contra el sabotaje de las instalaciones nucleares por parte de individuos o de grupos ha sido durante largo tiempo motivo de preocupacion nacional e internacional. Aunque la obligacion de crear y hacer funcionar un sistema completo de proteccion fisica para las instalaciones y materiales nucleares en el territorio de un Estado determinado incumbe enteramente al Gobierno de dicho Estado, el que esa obligacion se cumpla o no, y si se cumple, en que medida o hasta que punto, es cosa que no deja indiferentes a los demas Estados. De aqui que la proteccion fisica se haya convertido en motivo de interes y cooperacion internacional. La necesidad de cooperacion internacional se hace evidente en los casos en que la eficacia de la proteccion fisica en el territorio de un Estado depende de que otros Estados tomen tambien medidas apropiadas para evitar o hacer fracasar los actos hostiles dirigidos contra instalaciones y

  10. Betsy Pugel, Tiny houses: Planetary protection-focused materials selection for spaceflight hardware surfaces

    OpenAIRE

    Schriml, Lynn

    2017-01-01

    Betsy Pugel, National Aeronautics and Space Administration Tiny houses: Planetary protection-focused materials selection for spaceflight hardware surfacesOn October 10-12th, 2017 the Alfred P. Sloan Foundation and The National Academies of Sciences, Engineering and Medicine co-hosting MoBE 2017 (Microbiology of the Built Environment Research and Applications Symposium) at the National Academy of Sciences Building to present the current state-of-the-science in understanding the formation and ...

  11. Evaluating skin-protective materials against contact irritants and allergens. An in vivo screening human model.

    Science.gov (United States)

    Zhai, H; Willard, P; Maibach, H I

    1998-03-01

    2 acute irritants and 1 allergen were selected: sodium lauryl sulfate (SLS) representative of irritant household and occupational contact dermatitis, the combination of ammonium hydroxide (NH4OH) and urea to simulate diaper dermatitis, and Rhus to evaluate the effect of model protective materials. The putative protective materials and vehicle were applied to both ventral forearms of 10 subjects in each group, according to a randomized code. Test materials were spread over a marked 2.0 cm2 area, massaged in, allowed to dry for 30 min, and reapplied with another 30 min drying period. The model irritants and allergen were then applied (0.025 ml) to an Al-test occlusive patch, which in turn was placed for 24 h over each of the 8 designated sites. Inflammation was scored according to a clinical scale 72 h post-application. Paraffin wax plus Acetulan in cetyl alcohol, and beeswax plus Acetulan in cetyl alcohol, markedly (p < 0.001) suppressed SLS irritation. Paraffin wax plus beeswax in cetyl alcohol, and Acetulan in cetyl alcohol reduced NH4OH and urea irritation (p < 0.05), paraffin wax in cetyl alcohol significantly (p < 0.01) decreasing Rhus allergic contact dermatitis. This model, provides an easy approach to screening protectants. Its clinical significance requires comparison with an open rather than an occluded challenge.

  12. Computerized data treatment technology

    International Nuclear Information System (INIS)

    Ferguson, R.B.; Maddox, J.H.; Wren, H.F.

    1977-01-01

    The Savannah River Laboratory (SRL) has accepted responsibility for a hydrogeochemical and stream-sediment reconnaissance in 25 eastern states as part of the National Uranium Resource Evaluation (NURE). SRL has developed a computerized program for recording, processing, updating, retrieving, and analyzing hydrogeochemical data from this reconnaissance. This program will handle an expected 150 million bytes of hydrogeochemical data from 150,000 to 200,000 sample sites over the next four years. The SRL--NURE hydrogeochemical data management system is written in FORTRAN IV for an IBM System 360/195 computer and is designed to easily accommodate changes in types of collected data and input format. As the data become available, they are accepted and combined with relevant data already in the system. SRL also developed a sample inventory and control system and a graphics and analysis system. The sample inventory and control system accounts for the movements of all samples and forms from initial receipt through final storage. Approximately six million sample movements are expected. The graphics and analysis system provides easily usable programs for reporting and interpreting data. Because of the large volume of data to be interpreted, the graphics and analysis system plays a central role in the hydrogeochemical program. Programs developed to provide two- and three-dimensional plots of sampled geographic areas show concentrations and locations of individual variables which are displayed and reproduced photographically. Pattern recognition techniques are also available, and they allow multivariate data to be categorized into ''clusters,'' which may indicate sites favorable for uranium exploration

  13. Manual work in cold environments and its impact on selection of materials for protective gloves based on workplace observations.

    Science.gov (United States)

    Irzmańska, Emilia; Wójcik, Paulina; Adamus-Włodarczyk, Agnieszka

    2018-04-01

    This article presents a workplace observations on manual work in cold environments and its impact on the selection of materials for protective gloves. The workplace observations was conducted on 107 workers in 7 companies and involved measurements of the temperature of air and objects in the workplaces; in addition the type of surface and shape of the objects was determined. Laboratory tests were also carried out on 11 materials for protective gloves to be used in cold environments. Protective characteristics, including mechanical properties (wear, cut, tear, and puncture resistance), insulation properties (thermal resistance), functional parameters, and hygienic properties (resistance to surface wetting, material stiffness) were evaluated. Appropriate levels of performance and quality, corresponding to the protective and functional properties of the materials, were determined. Based on the results of manual work and laboratory tests, directions for the selection of materials for the construction of protective gloves were formulated with a view to improving work ergonomics. Copyright © 2017 Elsevier Ltd. All rights reserved.

  14. Bioinspired fabrication and characterization of a synthetic fish skin for the protection of soft materials.

    Science.gov (United States)

    Funk, Natasha; Vera, Marc; Szewciw, Lawrence J; Barthelat, Francois; Stoykovich, Mark P; Vernerey, Franck J

    2015-03-18

    The scaled skin of fish is a high-performance natural armor that represents a source of inspiration for novel engineering designs. In this paper, we present a biomimetic fish skin material, fabricated with a design and components that are simple, that achieves many of the advantageous attributes of natural materials, including the unique combination of flexibility and mechanical robustness. The bioinspired fish skin material is designed to replicate the structural, mechanical, and functional aspects of a natural teleost fish skin comprised of leptoid-like scales, similar to that of the striped red mullet Mullus surmuletus. The man-made fish skin material consists of a low-modulus elastic mesh or "dermis" layer that holds rigid, plastic scales. The mechanics of the synthetic material is characterized under in-plane, bending, and indentation modes of deformation and is successfully described by theoretical deformation models that have been developed. This combined experimental and modeling approach elucidates the critical mechanisms by which the composite material achieves its unique properties and provides design rules that allow for the engineering of scaled skins. Such artificial scaled skins that are flexible, lightweight, transparent, and robust under mechanical deformation may thus have potential as thin protective coatings for soft materials.

  15. Peculiarities of physical protection assurance of the nuclear materials at nuclear installation decommissioning stage

    International Nuclear Information System (INIS)

    Pinchuk, M.G.

    2001-01-01

    On December 15, 2000 Unit 3 of Chernobyl NPP, which is the last one in Ukraine having RBMK-type reactor, was permanently shutdown before the end of its lifetime. A number of projects related to establishing infrastructure for the plant decommissioning are being implemented in compliance with the Ukraine's commitments. Decommissioning stage includes activities on fuel unloading from the cores of Unit I and Unit 3, fuel cooling in the ponds followed by the fuel transportation to the spent fuel dry storage facility (currently under construction) for its safe long-term storage. Special facilities are being created for liquid and solid radioactive waste treatment. Besides, it is planned to implement a number of projects to convert Shelter Object in environmentally safe structure. Physical protection work being an essential part of the nuclear material management is organized in line with the recommendations of the IAEA, and the Laws of Ukraine 'On Nuclear Energy Utilization and Radiation Safety', 'On Physical Protection of Nuclear Installations and Materials', 'Regulations on Physical Protection of Nuclear Materials and Installations', other codes and standards. While organizing physical protection on ChNPP decommissioning stage we have to deal with some specific features, namely: Significant amount of fuel assemblies, which are continuously transferred between various storage and operation facilities; Big amount of odd nuclear material at Shelter Object; 'Theft of new fuel fragments from the central hall of the Shelter Object in 1995 with the intention of their further sale. The thieves were detained and sentenced. The stolen material was withdrawn, that prevented its possible proliferation and illicit trafficking. At present physical protection of ChNPP does not fully satisfy the needs of the decommissioning stage and Ukraine's commitments on non-admission of illicit trafficking. Work is carried out, aimed to improve nuclear material physical protection, whose main

  16. Strengthening global physical protection practices; gaining better information on national practices for protection of weapons-usable material. Keynote address/session 3

    International Nuclear Information System (INIS)

    Bunn, G.; Rinne, R.

    2001-01-01

    Full text: Unlike the Non-Proliferation Treaty requirement that non-nuclear-weapon parties provide 'safeguards' information to the IAEA on their nuclear materials and their state systems for accounting and control, there is no related requirement to provide information on state systems of physical protection. A review of 1997 IAEA and Stanford physical protection conference proceedings showed both the absence of information on important practices from many states and the great variation in practices from state to state. Besides the lack of internationally required standards for domestic protection, reasons for the variations described in Stanford-Sandia National Laboratories research include: differences in states' perceptions of the threats to their materials; differences in their abilities to pay the cost of stronger physical protection; differences in their laws and regulatory practices in general; and differences in their cultural attitudes - for example, attitudes toward whether to arm personnel guarding weapon-usable material or to require clearances for personnel with access to such material. The information presented to the 1997 IAEA and Stanford conferences was supplied voluntarily. The two global documents which provide norms for physical protection do not require submission of such information. These are the 1980 Convention on Physical Protection of Nuclear Material and the 1999 IAEA INFCIRC/225/Rev.4. This means that, without bilateral cooperation, no state can find out how other states are protecting their nuclear material. Yet, as IAEA Director General El Baradei has said, '[I]t is not a matter of indifference to other States whether and to what extent [physical protection] responsibility is fulfilled. ...The need for international cooperation becomes evident in situations - where the effectiveness of physical protection in one State depends on the taking by other States also of adequate measures to deter and defeat hostile actions against nuclear

  17. Establishment and utilization of radiological protection programs for the transport of radioactive material

    International Nuclear Information System (INIS)

    Lopez V, J.; Capadona, N.

    2006-01-01

    The present work has by objective to indicate rules for the establishment and the use of the Radiological Protection Programs (PPR) that are of application to the transport of radioactive materials according to that required by the Transport Regulation of the International Atomic Energy Agency (IAEA). The PPR are established and applied in systematic form for remittent, transport and addressees, to consider the measures of radiological protection and its appropriately control during the transport stages of radioactive material. In particular, in the work it is analyzed the PPR applied to the operative stage, in the one that can be considered as one of the more important documents to use since it summarizes the evaluations and the necessary controls of radiological protection. Also it is analyzed the importance that this document gets ready on the base that it converges in the the analyses, evaluations and data that have been kept in mind during the previous stages of design of bundles and production of packings, the types and quantities of involved bundles, as well as of considering the quantities of expeditions and its frequencies, the ways of transport, etc. It is included a brief description of the parts that the PPR conforms on the base of that suggested in the advanced draft of the TS-G-1.5 Guide 'Radiation Protection Programmes for Transport of Radioactive Material', of October, 2005, of the IAEA: objectives. necessity, scope, basic elements of a PPR in function of the occupational dose. assignment of functions and responsibilities for the establishment of a PPR, evaluation and dose optimization, surface contamination, segregation and other protection measures, responses in emergencies. training and administration systems for baled and transport of radioactive material. Next an example of PPR for the transport of bundles of the A Type by lorry with content of radiopharmaceuticals that are the bundles more used worldwide in the expeditions of radioactive

  18. Dose evaluation in diagnostic for computerized tomography

    International Nuclear Information System (INIS)

    Flores, W.; Borges, J.C.; Mota, H.

    1998-01-01

    The patients which are subjected to computerized tomography tests are exposed to relatively high doses given as result doses on organs that are not matter to test. It was realized a dose levels raising in patients subjected to tests by T C, utilizing to measure this magnitude, TLD-100 thermoluminescent dosemeters which were put directly on the patient, in eye regions, thyroid, breast and navel; founding doses fluctuating between 29.10-49.39 mGy in organs examined and dose values between 0.21-29.10 mGy for organs that no matter to test. The applications of ionizing radiations in medicine do not have dose limits, but paying attention to the radiological protection optimization principle, it is recommended the use of clothes to anti-rays protection for zones not examined, getting with this to reduce the level doses as low as possible, without this to diminish the test quality. (Author)

  19. Thermal Protection Performance of Phase Changing Material Based on Polyethylene Glycol

    Directory of Open Access Journals (Sweden)

    Leila Sadat Ahmadi

    2012-12-01

    Full Text Available Phase change materials (PCM are substances with a high heat of fusion which, through melting and solidifying at certain temperatures, are capable to store or release a large amount of energy. This phenomenon can be utilized in designing heat protective materials as well as in thermal energy storage systems. One of the approaches to avoid materials leaching from a structure, where PCMs are incorporated, is to blend them with suitable polymers. To have a proper blend it is necessary to choose a compatible polymer with a PCM. It is important to assess the optimized concentration of PCM in polymer matrix and the phase structure and morphology of the blend, which causes the best heat protection. In this work, the influence of polyethylene glycol (PEG as PCMs in epoxy resin matrix on heat protection was investigated. A special performance test was designed to study timetemperature behavior of the prepared samples and DSC and SEM tests to observe the melting point, heat of fusion and morphology of the samples. The results indicated that increases in PCM content led to better heat protection and the best concentration for PEG was found to be 60% wt. Time-temperature curves show that increases of temperature for PCM samples is very slow compared with net epoxy sample. PCM samples curves show plateau in melting region. In this region, they show nearly 15°C temperature lower than a net epoxy sample. The plateau region makes a delay time in temperature increment, which is about 22 min for PEG samples compared with a net epoxy.

  20. Evolution of the physical protection and control of nuclear materials in Brazil

    International Nuclear Information System (INIS)

    Paschoa, A.S.; Renha, G.; Mafra, O.Y.

    2005-01-01

    Full text: Brazil started protecting its nuclear materials soon after the end of the World War II, when the Combined Development Trust intended to control the world supply of uranium and thorium. This happened in 1944, but on December 27, 1946, an amendment to the report of Committee II of the United Nations established that the international ownership of the unexplored uranium and thorium would not be mandatory. Brazil nationalized its thorium and uranium reserves in 1951. The Brazil-Germany agreement signed in 1975 enhanced the need for Brazilian nuclear safeguards and security. The physical protection (PP) and control of nuclear materials (CNM) became activities under the supervision of the Brazilian military forces. The System for Protection of the Brazilian Nuclear Program (SIPRON), established on 7 October 1980, took over the responsibilities for PP and other aspects of the Brazilian nuclear program. The central organ of SIPRON was the Brazilian National Security Council (CSN). The Brazilian Nuclear Energy Commission (CNEN) was in charge of coordinating, among others, the PP sector. Earlier that year - on 3 March 1980 - the Convention on the Physical Protection of Nuclear Material (CPPNM) was signed simultaneously in New York and Vienna. The Brazilian congress approved the CPPNM on 27 November 1984, and the Brazilian government deposited the ratification letter on 17 October 1985. On 16 April 1991 the Brazilian government issued a decree to enforce the CPPNM in the Brazilian territory. CNEN published the regulatory documents NE - 2.01 on 19 April 1996, and NN - 2.02 on 21 September 1999 for PP, and CNM, respectively. CNEN has the ultimate responsibility to enforce these regulations. The operational aspects of PP and CNM in Brazil are still improving. Potential nuclear terrorism for example needs to be examined. Activities concerning training personnel and implementing PP and CNM will be described in the paper. (author)

  1. Clearance of material with negligible levels of radioactivity based on the amended German radiation protection ordinance

    International Nuclear Information System (INIS)

    Schaller, G.; Bayer, A.

    2002-01-01

    For the first time the modalities for the clearance of relevant materials have been laid down in the amended Radiation Protection Ordinance in a comprehensive form. A distinction is made between unconditional clearance and cases of clearance in which disposal, recycling, and re-use is prescribed. The focus of attention in the case of unconditional clearance consists in special consideration of large volumes of building rubble and excavated soil. Material can only be released from supervision under the Atomic Energy Act, when the radiation-related risk, and correspondingly, also the dose from material issued with clearance, are at negligible levels. In order to facilitate the practical application of clearance, values have been derived on the basis of scenarios which cover all radiation exposures which can reasonably be considered. (orig.) [de

  2. Study on CPPNM Interpretation of the Physical Protection Regulatory Aspects for International Transport of Nuclear Material

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Woo-jin; Yang, Seong-hyo; Hyung, Sang-chul [Korea Institute of Nuclear Nonproliferation and Control, Daejeon (Korea, Republic of)

    2015-05-15

    Nuclear energy has been regulated by various international agreements or treaties due to the potential dangers. In case of export or import of nuclear material, it is important to comply with international norms and domestic laws related to nonproliferation and physical protection of nuclear material. Because, if non-compliant, it can be taken nuclear sanctions from the international community, and thus the domestic nuclear activities can be under a negative impact. Recently, international interests in nuclear security have been increased, it has become very sensitive to whether or not to join, and to comply with international treaties during international transportation of nuclear materials. Currently it is not discussed yet how to present and interpret the relevant provisions in CPPNM. However, it is necessary to prepare for the dispute among the parties that we don't know when it happens.

  3. The physical protection of radiation sources and radioactive materials in Tanzania

    International Nuclear Information System (INIS)

    Sungita, Y.Y.; Massalu, I.

    2002-01-01

    Full text: In recognition of the legal deficiency and the awareness of radiation safety, the parliament of the United Republic of Tanzania enacted the protection from radiation act no. 5 of 1983, which established the national radiation commission (NRC) as a regulatory authority. The main objective of the act was to provide for a legal framework and guidance of the control of the use of radiation sources and radioactive materials with the view to achieve an assurance for acceptance level of radiation protection and safety standard. Due to trade liberalization that is currently experienced in the country, the increase in the number of radiation practices is observed yearly. medical diagnostic x-ray facilities constitute 72 % of all radiation installations in the country. Radioactive materials used in research, teaching and industrial application constitute 24 % and those used in therapy and nuclear medicine is 4 %. About seven radioactive materials incidents occurred in Tanzania during 1996-2000. Among these cases, some were illegal possession and across-boarder trafficking of radioactive materials. Theft and losses radioactive equipments or sources were also experienced. This presentation discusses the experienced incidents of illegal possession, theft and loss of radioactive materials and the lesson learnt from those events in connection with our operational laws. The needs for improvement of the whole system of notification, authorization, registration and licensing to cope up with increase in radiation practices and cross-border illegal trafficking of radioactive materials. The importance of involving immigration officers, police and custom officer with proper training in radiation safety aspect is emphasized. The recommendation are given in an attempt to rescue the situation. (author)

  4. Thermal Protection Performance of Carbon Aerogels Filled with Magnesium Chloride Hexahydrate as a Phase Change Material

    Directory of Open Access Journals (Sweden)

    Ali Kazemi

    2014-02-01

    Full Text Available Carbon aerogels are comprised of a class of low density open-cell foams with large void space, nanometer pore size and composed of sparsely semi-colloidal nanometer sized particles forming an open porous structure. Phase change materials are those with high heat of fusion that could absorb and release a large amount of energy at the time of phase transition. These materials are mostly used as thermal energy storage materials but in addition they could serve as an obstacle for passage of heat during phase changes and this has led to their use in thermal protection systems. In this study, the effect of magnesium chloride hexahydrate, as a phase change material (melting point 115°C, on thermal properties of carbon aerogels is investigated. Thermal performance tests are designed and used for comparing the temperature-time behavior of the samples. DSC is applied to obtain the latent heat of melting of the phase change materials and the SEM tests are used to analyze the microstructure and morphology of carbon aerogels. The results show that the low percentage of phase change materials in carbon aerogels does not have any significant positive effect on carbon aerogels thermal properties. However, these properties are improved by increasing the percentage of phase change materials. With high percentage of phase change materials, a sample surface at 300°C would display an opposite surface with a significant drop in temperature increases, while at 115-200°C, with carbon aerogels, having no phase change materials, there is a severe reduction in the rate of temperature increase of the sample.

  5. Criminal offences considered in the Convention on the Physical Protection of Nuclear Material

    International Nuclear Information System (INIS)

    Neira, C.C.

    1996-01-01

    The Convention on the Physical Protection of Nuclear Material was signed in Vienna, on April 3, 1980, approved by Law 23.620 on September 28, 1998, and published in the Official Bulletin of the Argentine Republic on November 2, 1988. This Convention considers some aspects of Criminal Law and Criminal Procedural Law and integrates the normative hierarchical structure of the article 31 of the National Constitution. The adequacy of this Convention to the Argentine law is considered through two aspects: The first one examines figures existing in the Argentine Legislation about larceny and robbery of nuclear materials, misappropriation of nuclear materials, obtainment and fraud of nuclear materials, exaction through threat or intimidation, etc., which are considered in different articles of the Argentine Criminal Law. The second one analyses behaviours not foreseen in the Criminal Law and which are not qualified by the current Argentina's Criminal Code, such as exaction of nuclear material through the use of violence, the international perpetration of an act consisting to receive, possess, use, vacate, scatter nuclear material without legal authorization, or in the case that the act causes death, serious injuries to persons and others. The purpose of the future enactment of a new Nuclear Law is to put in order and fill-in gaps referred to different aspects such as civil liability in nuclear damages, characteristics of the nuclear damages, etc [es

  6. Scratch, wear and corrosion resistant organic inorganic hybrid materials for metals protection and barrier

    International Nuclear Information System (INIS)

    Barletta, M.; Gisario, A.; Puopolo, M.; Vesco, S.

    2015-01-01

    Highlights: • Polysiloxane coatings as protective barriers to delay erosion/corrosion of Fe 430 B metal substrates. • Methyl groups feature a very small steric hindrance and confer ductility to the Si–O–Si backbone. • Phenyl groups feature a larger steric hindrance, but they ensure stability and high chemical inertness. • Remarkable adhesion to the substrate, good scratch resistance and high wear endurance. • Innovative ways to design of long lasting protective barriers against corrosion and aggressive chemicals. - Abstract: Polysiloxanes are widely used as protective barriers to delay erosion/corrosion and increase chemical inertness of metal substrates. In the present work, a high molecular weight methyl phenyl polysiloxane resin was designed to manufacture a protective coating for Fe 430 B structural steel. Methyl groups feature very small steric hindrance and confer ductility to the Si–O–Si backbone of the organic inorganic hybrid resin, thus allowing the achievement of high thickness. Phenyl groups feature larger steric hindrance, but they ensure stability and high chemical inertness. Visual appearance and morphology of the coatings were studied by field emission scanning electron microscopy and contact gauge surface profilometry. Micro-mechanical response of the coatings was analyzed by instrumented progressive load scratch, while wear resistance by dry sliding linear reciprocating tribological tests. Lastly, chemical inertness and corrosion endurance of the coatings were evaluated by linear sweep voltammetry and chronoamperometry in aggressive acid environment. The resulting resins yielded protective materials, which feature remarkable adhesion to the substrate, good scratch resistance and high wear endurance, thus laying the foundations to manufacture long lasting protective barriers against corrosion and, more in general, against aggressive chemicals

  7. Physical protection of special nuclear materials in the Federal Republic of Germany

    International Nuclear Information System (INIS)

    Rossnagel, A.

    1987-01-01

    Measures to protect special nuclear materials in West Germany are based on a relatively likely average threat and not on the less-likely but maximum credible threat. The reason is to avoid the costs of maintaining a very high level of security that is seldom needed. The concept of delayed action, which divides the responsibility for security between private protection forces and local police forces, would be insufficient in the event of the maximum credible threat. In principle, sufficient security is possible only when the facilities and transports are constantly protected by a police force large enough to deal with the maximum credible threat without assistance from outside. They must also be adequately armed to avert all possible attackers, and they must be paid by the licensees. The threat of an insider(s) diverting special nuclear material can be addressed only by strengthening the scope and depth of the checks on applicants and employees and the permanent work controls. It is recognized, however, that such security measures may not be compatible with constitutional civil liberties

  8. Study on the Application Mode and Legal Protection of Green Materials in Medical-Nursing Combined Building

    Science.gov (United States)

    Zhiyong, Xian

    2017-09-01

    In the context of green development, green materials are the future trend of Medical-Nursing Combined building. This paper summarizes the concept and types of green building materials. Then, on the basis of existing research, it constructs the green material system framework of Medical-Nursing Combined building, puts forward the application mode of green building materials, and studies the policy and legal protection of green material application.

  9. Computerized accountability program is operating - DYMCAS

    International Nuclear Information System (INIS)

    Combs, S.W.; Mee, W.T.

    1983-01-01

    The nuclear materials control and accountability program in the Oak Ridge Y-12 Plant has been placed on a computerized system identified as DYMCAS (Dynamic Special Nuclear Materials Control and Accountability System). The primary gola of the DYMCAS is to assist in detecting the diversion of special nuclear material (SNM). Secondly, the system is expected to assure quality inventory reconciliations both under normal and emergency situations. The system has been installed and was placed on active status in April 1982. Since that time numerous problems have surfaced and been resolved; i.e., delays of input, hardware breakdown, and misunderstandings of needs. An explanation of these problems, including examples and alterations that have made the system workable, are presented

  10. A computerized accountability program is operating - DYMCAS

    International Nuclear Information System (INIS)

    Combs, S.W.; Mee, W.T.

    1983-01-01

    The nuclear materials control and accountability program in the Oak Ridge Y-12 Plant has been placed on a computerized system identified as DYMCAS (Dynamic Special Nuclear Materials Control and Accountability System). The primary goal of the DYMCAS is to assist in detecting the diversion of special nuclear material (SNM). Secondly, the system is expected to assure quality inventory reconciliations both under normal and emergency situations. The system has been installed and was placed on active status in April 1982. Since that time numerous problems have surfaced and been resolved; i.e., delays of input, hardware breakdown, and misunderstandings of needs. An explanation of these problems, including examples and alterations that have made the system workable, are presented

  11. US-Russian laboratory-to-laboratory cooperation in nuclear materials protection, control, and accounting

    International Nuclear Information System (INIS)

    Mullen, M.; Augustson, R.; Horton, R.

    1995-01-01

    Under the guidance of the Department of Energy (DOE), six DOE laboratories have initiated a new program of cooperation with the Russian Federation's nuclear institutes. The purpose of the program is to accelerate progress toward a common goal shared by both the US and Russia--to reduce the risks of nuclear weapons proliferation, including such threats as theft, diversion, and unauthorized possession of nuclear materials, by strengthening systems of nuclear materials protection, control, and accounting. This new program is called the Laboratory-to-Laboratory Nuclear Materials Protection, Control, and Accounting (Lab-to-Lab MPC and A) Program. It is designed to complement other US-Russian MPC and A programs such as the government-to-government (Nunn-Lugar) programs. The Lab-to-Lab MPC and A program began in 1994 with pilot projects at two sites: Arzamas-16 and the Kurchitov Institute. This paper presents an overview of the Laboratory-to-Laboratory MPC and A Program. It describes the background and need for the program; the objectives and strategy; the participating US and Russian laboratories, institutes and enterprises; highlights of the technical work; and plans for the next several years

  12. Using virtualization to protect the proprietary material science applications in volunteer computing

    Directory of Open Access Journals (Sweden)

    Khrapov Nikolay P.

    2018-04-01

    Full Text Available USPEX is a world-leading software for computational material design. In essence, USPEX splits simulation into a large number of workunits that can be processed independently. This scheme ideally fits the desktop grid architecture. Workunit processing is done by a simulation package aimed at energy minimization. Many of such packages are proprietary and should be protected from unauthorized access when running on a volunteer PC. In this paper we present an original approach based on virtualization. In a nutshell, the proprietary code and input files are stored in an encrypted folder and run inside a virtual machine image that is also password protected. The paper describes this approach in detail and discusses its application in USPEX@home volunteer project.

  13. Using virtualization to protect the proprietary material science applications in volunteer computing

    Science.gov (United States)

    Khrapov, Nikolay P.; Rozen, Valery V.; Samtsevich, Artem I.; Posypkin, Mikhail A.; Sukhomlin, Vladimir A.; Oganov, Artem R.

    2018-04-01

    USPEX is a world-leading software for computational material design. In essence, USPEX splits simulation into a large number of workunits that can be processed independently. This scheme ideally fits the desktop grid architecture. Workunit processing is done by a simulation package aimed at energy minimization. Many of such packages are proprietary and should be protected from unauthorized access when running on a volunteer PC. In this paper we present an original approach based on virtualization. In a nutshell, the proprietary code and input files are stored in an encrypted folder and run inside a virtual machine image that is also password protected. The paper describes this approach in detail and discusses its application in USPEX@home volunteer project.

  14. Guidance and considerations for the implementation of INFCIRC/225/Rev.4, the physical protection of nuclear material and nuclear facilities

    International Nuclear Information System (INIS)

    2000-05-01

    This publication is intended to provide guidance and considerations for a State's competent authority to better understand and prescribe appropriate requirements, consistent with INFCIRC/225/Rev.4 for the protection of nuclear material and nuclear facilities which are compatible with accepted international practice. This report, together with a more detailed report, Handbook on the Physical Protection of Nuclear Material and Facilities, which addresses to the licencee or designer of physical protection systems who has specific implementation and compliance responsibilities, should be used in conjunction to each other to provide better and comprehensive guidance on physical protection

  15. Guidance and considerations for the implementation of INFCIRC/225/Rev.4, the physical protection of nuclear material and nuclear facilities

    International Nuclear Information System (INIS)

    2002-05-01

    This publication is intended to provide guidance and considerations for a State's competent authority to better understand and prescribe appropriate requirements, consistent with INFCIRC/225/Rev.4 for the protection of nuclear material and nuclear facilities which are compatible with accepted international practice. This report, together with a more detailed report, Handbook on the Physical Protection of Nuclear Material and Facilities, which addresses to the licensee or designer of physical protection systems who has specific implementation and compliance responsibilities, should be used in conjunction to each other to provide better and comprehensive guidance on physical protection

  16. Corrosion of metallic materials. Dry corrosion, aqueous corrosion and corrosion by liquid metal, methods of protection

    International Nuclear Information System (INIS)

    Helie, Max

    2015-01-01

    This book is based on a course on materials given in an engineering school. The author first gives an overview of metallurgy issues: metallic materials (pure metals, metallic alloys), defects of crystal lattices (point defects, linear defects or dislocations), equilibrium diagrams, steels and cast, thermal processing of steels, stainless steels, aluminium and its alloys, copper and its alloys. The second part addresses the properties and characterization of surfaces and interfaces: singularity of a metal surface, surface energy of a metal, energy of grain boundaries, adsorption at a material surface, metal-electrolyte interface, surface oxide-electrolyte interface, techniques of surface analysis. The third chapter addresses the electrochemical aspects of corrosion: description of the corrosion phenomenon, free enthalpy of a compound and free enthalpy of a reaction, case of dry corrosion (thermodynamic aspect, Ellingham diagram, oxidation mechanisms, experimental study, macroscopic modelling), case of aqueous corrosion (electrochemical thermodynamics and kinetics, experimental determination of corrosion rate). The fourth part addresses the different forms of aqueous corrosion: generalized corrosion (atmospheric corrosion, mechanisms and tests), localized corrosion (galvanic, pitting, cracking, intergranular, erosion and cavitation), particular cases of stress cracking (stress corrosion, fatigue-corrosion, embrittlement by hydrogen), and bi-corrosion (of non alloyed steels, of stainless steels, and of aluminium and copper alloys). The sixth chapter addresses the struggle and the protection against aqueous corrosion: methods of prevention, scope of use of main alloys, geometry-based protection of pieces, use of corrosion inhibitors, use of organic or metallic coatings, electrochemical protection. The last chapter proposes an overview of corrosion types in industrial practices: in the automotive industry, in the oil industry, in the aircraft industry, and in the

  17. Nuclear Security Recommendations on Physical Protection of Nuclear Material and Nuclear Facilities (INFCIRC/225/Revision 5): Recommendations

    International Nuclear Information System (INIS)

    2011-01-01

    This publication, Revision 5 of Physical Protection of Nuclear Material and Nuclear Facilities (INFCIRC/225), is intended to provide guidance to States and their competent authorities on how to develop or enhance, implement and maintain a physical protection regime for nuclear material and nuclear facilities, through the establishment or improvement of their capabilities to implement legislative and regulatory programmes. The recommendations presented in this publication reflect a broad consensus among IAEA Member States on the requirements which should be met for the physical protection of nuclear materials and nuclear facilities.

  18. 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

  19. The Russian Nuclear Material Protection, Control and Accounting Program: Analysis and prospect

    International Nuclear Information System (INIS)

    Kempf, C.R.

    1998-01-01

    This paper summarizes an analysis of the US-Russian Nuclear Material Protection, Control and Accounting (MPC and A) Program, developed on the basis of extensive discussions with US laboratory participants as well as personal experience. Results of the discussions have been organized into three main areas: Technical/MPC and A Progress; Programmatic and Administrative Issues; and Professional Aspects. Implications for MPC and A effectiveness, for MPC and A sustainability, and for future relations and collaboration are derived. Suggested next steps are given

  20. Technologies in computerized lexicography | Kruyt | Lexikos

    African Journals Online (AJOL)

    Although the topic of this paper is technology, focus is on functional rather than technical aspects of computerized lexicography. Keywords: computerized lexicography, electronic dictionary, electronic text corpus, lexicographer's workbench, integrated language database, automatic linguistic analysis, information retrieval, ...

  1. State planning policy 2/07: protection of extractive resources results in certainty of materials supply

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-09-15

    Extractive resources are primary source materials used for building infrastructure such as roads, ports, airports, bridges, railways, factories, hospitals, schools and homes. The Policy seeks to protect those essential and finite construction materials for future and existing extraction purposes. Population increases in south-east Queensland the upgrading of rail and port facilities to export coal and other minerals will form a major part in the expansion of extractive industry. Over $4 billion has been committed by the Government and industry to coal infrastructure developments such as upgrades at RG Tanna, Barney Point and the proposed Wiggins Island coal terminals at Gladstone, the Dalryample Bay and Hay Point terminals near Mackay and the Abbot Point coal terminal near Bower. The new Bauhinia regional railway will service the Rolleston coal mines.

  2. A Study on Salt Attack Protection of Structural and Finishing Materials in Power Plant Structures

    Energy Technology Data Exchange (ETDEWEB)

    Kim, W B; Kweon, K J; Suh, Y P; Nah, H S; Lee, K J; Park, D S; Jo, Y K [Korea Electric Power Research Institute, Taejeon (Korea, Republic of)

    1998-12-31

    This is a final report written by both KEPRI and KICT as a co-operative research titled {sup A} study on Salt Protection of Structural and Finishings in Power Plant Structures{sup .} This study presented the methods to prevent the chloride-induced corrosion of power plant structures through collection and analysis of research datum relating to design, construction and maintenance for the prevention of structural and finishing materials, thru material performance tests for anti-corrosion under many kinds of chloride-induced corrosion environments. As a result, this study proposed the guidelines for design, construction and maintenance of power plant structures due to chloride-induced corrosion. (author). 257 refs., 111 figs., 86 tabs.

  3. Supporting the material control and accountancy system with physical protection system features

    International Nuclear Information System (INIS)

    Miyoshi, D.S.; Olson, C.E.; Caskey, D.L.

    1984-01-01

    Most physical security functions can be accomplished by a range of alternative features. Careful design can provide comparable levels of security regardless of which option is chosen, albeit with possible differences in cost and efficiency. However, the effectiveness and especially the cost and efficiency of the material control and accounting system may be strongly influenced by the selection of a particular design approach to physical security. In this paper, a series of examples are cited to illustrate the effects that particular physical protection design choices may have. The examples have been chosen from several systems engineering projects at facilities within the DOE nuclear community. These examples are generalized, and a series of design principles are proposed for integrating physical security with material control and accounting by appropriate selection of alternative features. 2 references, 6 figures

  4. A Study on Salt Attack Protection of Structural and Finishing Materials in Power Plant Structures

    Energy Technology Data Exchange (ETDEWEB)

    Kim, W.B.; Kweon, K.J.; Suh, Y.P.; Nah, H.S.; Lee, K.J.; Park, D.S.; Jo, Y.K. [Korea Electric Power Research Institute, Taejeon (Korea, Republic of)

    1997-12-31

    This is a final report written by both KEPRI and KICT as a co-operative research titled {sup A} study on Salt Protection of Structural and Finishings in Power Plant Structures{sup .} This study presented the methods to prevent the chloride-induced corrosion of power plant structures through collection and analysis of research datum relating to design, construction and maintenance for the prevention of structural and finishing materials, thru material performance tests for anti-corrosion under many kinds of chloride-induced corrosion environments. As a result, this study proposed the guidelines for design, construction and maintenance of power plant structures due to chloride-induced corrosion. (author). 257 refs., 111 figs., 86 tabs.

  5. Computerized Proof Techniques for Undergraduates

    Science.gov (United States)

    Smith, Christopher J.; Tefera, Akalu; Zeleke, Aklilu

    2012-01-01

    The use of computer algebra systems such as Maple and Mathematica is becoming increasingly important and widespread in mathematics learning, teaching and research. In this article, we present computerized proof techniques of Gosper, Wilf-Zeilberger and Zeilberger that can be used for enhancing the teaching and learning of topics in discrete…

  6. Computerized adaptive testing in computer assisted learning?

    NARCIS (Netherlands)

    Veldkamp, Bernard P.; Matteucci, Mariagiulia; Eggen, Theodorus Johannes Hendrikus Maria; De Wannemacker, Stefan; Clarebout, Geraldine; De Causmaecker, Patrick

    2011-01-01

    A major goal in computerized learning systems is to optimize learning, while in computerized adaptive tests (CAT) efficient measurement of the proficiency of students is the main focus. There seems to be a common interest to integrate computerized adaptive item selection in learning systems and

  7. Material and cultural assets. Part of radiation protection of the environment?; Sach- und Kulturgueter. Teil eines Strahlenschutzes der Umwelt?

    Energy Technology Data Exchange (ETDEWEB)

    Gellermann, R.G. [Nuclear Control and Consulting GmbH, Braunschweig (Germany); Loebner, W.

    2015-07-01

    Since several years the protection of the environment has been discussed at various international levels as part of radiation protection. ICRP has published a number of recommendations which relate primarily to the evaluation of radiation exposures to non-human species. Nevertheless, not least because of the declaratory mention of the environment in national legislative documents, the question arises how the environment can be integrated into the radiation protection or whether the radiation protection must be even expanded to new fields. A less discussed aspect here covers material and cultural assets that are classified in environmental law as objects worthy of protection. The paper describes some issues that arise in this context and outlines a framework for the consideration of material assets in radiation protection.

  8. Phenomena in the interaction among a core melt and protective and sacrificial materials

    International Nuclear Information System (INIS)

    Steinwarz, W.; Koller, W.; Dyllong, N.; Fischer, M.; Hellmann, S.; Lansmann, V.; Nie, M.; Haefner, W.; Alkan, Z.; Andrae, P.; Rensing, B.

    2000-01-01

    In a postulated core meltdown accident in a light water reactor there are bound to be interactions, in the ex-vessel phase, among the core melt and the structural materials within and below the reactor cavity. In existing plants, these structural materials normally are structural concrete, while future, evolutionary reactor lines are to have sacrificial and protective materials specially designed for this hypothetical case. To add to the state of knowledge about the phenomena occurring, experiments need to be conducted under conditions as realistic as possible. Within the research programs funded by the European Union, the German Federal Ministry for Economics, and the German nuclear power plant operators, experiments on a laboratory as well as an industrial scale on these problems are being carried out in the two projects called CORESA (COrium on REfractory and SAcrificial materials) and ECOSTAR (Ex-vessel COre melt STAbilization Research). The experiments are accompanied by an extensive analytical theoretical program also serving to advance and validate computer codes on the problems under investigation. The projects, which are carried out with international European participation, are expected to allow a concept to be developed for managing postulated accident scenarios involving core meltdown for innovative nuclear power plants, and to provide findings on risk evaluation of plants now in operation so as to further develop accident management measures. (orig.) [de

  9. The Development of HfO2-Rare Earth Based Oxide Materials and Barrier Coatings for Thermal Protection Systems

    Science.gov (United States)

    Zhu, Dongming; Harder, Bryan James

    2014-01-01

    Advanced hafnia-rare earth oxides, rare earth aluminates and silicates have been developed for thermal environmental barrier systems for aerospace propulsion engine and thermal protection applications. The high temperature stability, low thermal conductivity, excellent oxidation resistance and mechanical properties of these oxide material systems make them attractive and potentially viable for thermal protection systems. This paper will focus on the development of the high performance and high temperature capable ZrO2HfO2-rare earth based alloy and compound oxide materials, processed as protective coating systems using state-or-the-art processing techniques. The emphasis has been in particular placed on assessing their temperature capability, stability and suitability for advanced space vehicle entry thermal protection systems. Fundamental thermophysical and thermomechanical properties of the material systems have been investigated at high temperatures. Laser high-heat-flux testing has also been developed to validate the material systems, and demonstrating durability under space entry high heat flux conditions.

  10. Engineered nano materials and the U.S. Environmental Protection Agency: Research at the Western Ecology Division in Oregon, USA

    Science.gov (United States)

    Engineered nanoparticles represent a unique hazard to human health and the environment because their inherent characteristics differ significantly from commonly used chemicals and bulk forms of materials. The U.S. Environmental Protection Agency (EPA) is responsible for protecti...

  11. Expert training on physical protection of nuclear materials at universities of Russia

    International Nuclear Information System (INIS)

    Pogozhin, N.S.; Bondarev, P.V.; Geraskin, N.I.; Kryuchkov, E.F.; Tolstoy, A.I.

    2002-01-01

    Full text: The expert training on physical protection of nuclear materials in Russia is carry out by the universities on the following directions: 'Physical Protection, Control and Accountability of Nuclear Materials (MPCA)' master educational program. 'Physical and technical problems of atomic engineering' master educational standard. 'Technical Physics' direction. Qualification - master of physics. Duration of training - two years. 'Physical protection of nuclear objects' specialization. 'Nuclear physics and technology' educational standard of a direction for professionally qualified expert training. 'Safety and nonproliferation of nuclear materials' specialty. Qualification - engineer-physician. Duration of training - five years. The Master educational program is intended for the expert training with fundamental knowledge. The masters are assigned to work at the establishments of the Ministry of Atomic Energy of Russia and at the state committee on nuclear supervision (Gosatomnaozor). Many graduates continue their education as post-graduate students. The program is designed for the experts having education of an engineer or a bachelor. The program concept consists in integration in a uniform educational process: profound scientific and technical knowledge; system approach to designing MPCA systems; knowledge of scientific and technical principles, means, devices; MPCA facilities and tools; legal, political and economic aspects of nuclear material management; modern computer and information technologies for MPCA systems; research work and practice of the students. The educational program for 'physical protection of nuclear objects' specialization is intended for the expert training of a practical orientation. Engineer-physicians are assigned as a rule to work at the nuclear objects and are intended for operation and servicing of the certain physical protection systems (PPS). The program concept consists in training not only fundamental aspects of an engineering

  12. Computerized tomographic scanner with shaped radiation filter

    International Nuclear Information System (INIS)

    Carlson, R.W.; Walters, R.G.

    1981-01-01

    The invention comprises a shaped filter and a filter correction circuitry for computerized tomographic scanners. The shaped filter is a generally u-shaped block of filter material which is adapted to be mounted between the source of radiation and the scan circle. The u-shaped block has a parabolic recess. The filter material may be beryllium, aluminum, sulphur, calcium, titanium, erbium, copper, and compounds including oxides and alloys thereof. The filter correction circuit comprises a first filter correction profile adding circuit for adding a first scaler valve to each intensity valve in a data line. The data line is operated on by a beam hardness correction polynomial. After the beam hardness polynomial correction operation, a second filter correction circuit adds a second filter correction profile consisting of a table of scalor values, one corresponding to each intensity reading in the data line

  13. Computerized information management for institutional review boards.

    Science.gov (United States)

    Hood, Maureen N; Gugerty, Brian; Levine, Richard; Ho, Vincent B

    2005-01-01

    The use of human subjects for medical research in most industrialized nations requires the scientific and ethical scrutiny of research proposals by a governing institutional review board (IRB) or its equivalent. As part of their primary charge to protect human subjects, IRBs are responsible for the regulatory oversight of not only the research protocol itself but also the research conduct of the investigators and, if applicable, the funding sponsor. This article will discuss the regulatory requirements for an accurate account of IRB protocols and investigators and present an overview of the general flow of information for an IRB protocol. The current and potential uses of information management systems by IRBs will also be reviewed and accompanied by a discussion of the potential advantages and disadvantages of various computerized information systems for management of clinical research.

  14. Analysis of errors during medical and computerized diagnostics of spherical lung neoplasms

    International Nuclear Information System (INIS)

    Pozmogov, A.I.; Petruk, D.A.

    1985-01-01

    Reasons for errors in medical and computerized diagnostics of spherical lung neoplasms are studied based on material of 212 case records and clinicoroentgenological data; it should promote improvement of their diagnostics

  15. Contribution of the radiation hygiene laboratories network in physical protection of radiation materials in Romania

    International Nuclear Information System (INIS)

    Milu, C.

    2002-01-01

    Full text: The Ministry of Health and Family from Romania has its own radiation protection network, including 23 radiation hygiene laboratories (RHLs), within the Institutes of Public Health-Bucharest, Iassy, Cluj-Napoca and Timisoara and the Directions of Public Health from Arges county, Bihor, Brasov, Mures, Maramures, Cluj, Sibiu, Harghita, Suceava, lassy, Bacau, Neamt, Galati, Constanta, Prahova, Dolj, Caras-Severin, Timis and Bucharest City. The RHLs network has 170 persons (physicians, physicists, engineers, chemists, biologists and technicians) and it is technically co-ordinated by the RHL in the Institute of Public Health-Bucharest. Within the local or national activities for physical protection of radioactive materials, the RHLs network closely co-operates with the Ministry of Internal Affairs (MAI) and with the nuclear regulatory authority, named the National Commission for Nuclear Activities Control (CNCAN). In the particular case of theft, sabotage or illicit traffic of radioactive materials, usually the MAI has the main role in the co-ordination of intervention actions of the three authorities. The RHLs network contributes by the expertise of its staff and by using its intervention facilities. The specific tasks for the RHLs network are: identification of the type and size of the radioactive material (by direct dosimetry and/or by gamma spectroscopy); dose reconstructions for the involved persons, the intervention personnel and the population; health management for overexposed persons and the medical response, including biological dosimetry and epidemiological studies. Recent special situations in this field, were: theft of some fuel (defect) tablets of natural uranium, from a production factory; the illicit traffic of radioactive materials, in transition to Western European Countries; an unauthorized decommissioning of a furnace, determining the uncontrolled dispersion of about 30 cobalt-60 sealed sources and the radiation exposure of nearly 20

  16. A data communications systems for tamper-protected special nuclear materials (SNM) inventory management

    International Nuclear Information System (INIS)

    Hurkamp, A.C.

    1995-01-01

    The Department of Energy (D.O.E.) is responsible for the long term storage and protection of large quantities of Special Nuclear Material (SNM). This material is stored within individual containers located in vaults. Security measures are required to ensure that the SNM remains within the canisters where it is stored and that it is not disturbed in any manner. Conventional security and inventory techniques are manpower intensive and often require exposure to radiation hazards. The Purpose of this D.O.E sponsored project is to develop a cost effective system to monitor Special Nuclear Materials that, when fielded, would result in an extension of manual inventory cycles at a wide variety of SNM storage locations. The system consists of a computer, radio frequency interrogator, and individual miniaturized radio frequency transponders (tags) that are co-located with individual SNM containers. Each tag can perform SNM inventory, tamper alarm, and multiple sensor data transmission to the interrogator under the control of software designed by the user. SNM custodians can customize the system by their choice of packaging, software, and sensors. When implemented in accordance with current department of energy (D.O.E.) Policy on SNM inventory extension, the system has the potential to qualify for maximum extension times thus saving considerable resources through reduction of radiation exposure

  17. Specialists training on nuclear materials control, accounting and physical protection in the Moscow Engineering Physics Institute

    International Nuclear Information System (INIS)

    Khromov, V.V.; Pogozhin, N.S.; Kryuchkov, E.F.; Glebov, V.B.; Geraskin, N.I.

    1998-01-01

    Educational program to train specialists on non-proliferation problems and nuclear materials control, accounting and physical protection systems (NMCA and PP) at the Science Master's level was developed and is being realized in Moscow Sate Institute of Engineering and Physics at the support of the USA Ministry of Energy. The program is intended to train students who already got the Bachelor's degree on physical and technical subjects. The United methodological base of the program comprises lecture courses, practice in laboratories and computer programs. The educational program contains the following parts for training the students. 1) Deep scientific and technical knowledge. 2) System approach to designing and analysis of the NMCA and PP systems. 3) Knowledge of scientific and technical principles, means, devices and procedures used in the NMCA and PP systems. 4) Judicial, international and economical aspects of nuclear materials management. 5) Application of computer and information technologies for nuclear materials control and accounting. 6) Extensive practice in laboratories, using the most up-to-date equipment and devices used in the worldwide practice of NM control

  18. Tritium retention in candidate next-step protection materials: engineering key issues and research requirements

    International Nuclear Information System (INIS)

    Federici, G.; Andrew, P.L.; Wu, C.H.

    1995-01-01

    Although a considerable volume of valuable data on the behaviour of tritium in beryllium and carbon-based armours exposed to hydrogenic fusion plasmas has been compiled over the past years both from operation of present-day tokamaks and from laboratory simulations, knowledge is far from complete and tritium inventory predictions for these materials remain highly uncertain. In this paper we elucidate the main mechanisms responsible for tritium trapping and release in next-step D-T tokamaks, as well as the applicability of some of the presently known data bases for design purposes. Owing to their strong anticipated implications on tritium uptake and release, attention is focused mainly on the interaction of tritium with neutron damage induced defects, on tritium codeposition with eroded carbon and on the effects of oxide and surface contaminants. Some preliminary quantitative estimates are presented based on most recent experimental findings and latest modelling developments as well. The influence of important working conditions such as target temperature, loading particle fluxes, erosion and redeposition rates, as well as material characteristics such as the type of morphology of the protection material (i.e. amorphous plasma-sprayed beryllium vs. solid forms), and design dependent parameters are discussed in this paper. Remaining issues which require additional effort are identified. (orig.)

  19. Testing and modeling the dynamic response of foam materials for blast protection

    Science.gov (United States)

    Fitek, John H.

    The pressure wave released from an explosion can cause injury to the lungs. A personal armor system concept for blast lung injury protection consists of a polymer foam layer behind a rigid armor plate to be worn over the chest. This research develops a method for testing and modeling the dynamic response of foam materials to be used for down-selection of materials for this application. Constitutive equations for foam materials are incorporated into a lumped parameter model of the combined armor plate and foam system. Impact testing and shock tube testing are used to measure the foam model parameters and validate the model response to a pressure wave load. The plate and foam armor model is then coupled to a model of the human thorax. With a blast pressure wave input, the armor model is evaluated based on how it affects the injury-causing mechanism of chest wall motion. Results show that to reduce chest wall motion, the foam must compress at a relatively constant stress level, which requires a sufficient foam thickness.

  20. The investigation in radiation protection of γ-rays material position meter in Guizhou Province

    International Nuclear Information System (INIS)

    Wei Fuxing

    1997-01-01

    The paper investigates the protective property of 38 γ-rays material position meters used in machine vertical kilns by 36 cement factories in Guizhou. Model FLW-II material position meter use the least radioactive source activity and the air absorption dose rate about one meter is equal to the natural background. For model FWJ-77A, the air absorption dose rate around one meter was 1.1-5.3 μGY/h and the average value is 2.1 +- 0.7 μGY/h; for Model LF-I, they are respectively 0.42-6.4 μGY/h and 2.4 +- 0.6 μGY/h. These value are lower than or near to the dose limit value which state stipulated. The biggest dose equivalent that maintenance workers accepted per year is only equal to 1/2∼1/3 of the dose limit value which state stipulated. Some management suggestions for the production, sellment and use of γ-rays material position meter were presented

  1. 10 CFR 73.25 - Performance capabilities for physical protection of strategic special nuclear material in transit.

    Science.gov (United States)

    2010-01-01

    ... strategic special nuclear material in transit. 73.25 Section 73.25 Energy NUCLEAR REGULATORY COMMISSION... Transit § 73.25 Performance capabilities for physical protection of strategic special nuclear material in transit. (a) To meet the general performance objective and requirements of § 73.20 an in-transit physical...

  2. 49 CFR 195.581 - Which pipelines must I protect against atmospheric corrosion and what coating material may I use?

    Science.gov (United States)

    2010-10-01

    ... corrosion and what coating material may I use? 195.581 Section 195.581 Transportation Other Regulations... Corrosion Control § 195.581 Which pipelines must I protect against atmospheric corrosion and what coating... atmosphere, except pipelines under paragraph (c) of this section. (b) Coating material must be suitable for...

  3. 10 CFR 73.73 - Requirement for advance notice and protection of export shipments of special nuclear material of...

    Science.gov (United States)

    2010-01-01

    ... shipments of special nuclear material of low strategic significance. 73.73 Section 73.73 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) PHYSICAL PROTECTION OF PLANTS AND MATERIALS Records and Reports § 73.73... Incident Response, using any appropriate method listed in § 73.4; (2) Assure that the notification will be...

  4. Fracture Toughness Evaluation of Space Shuttle External Tank Thermal Protection System Polyurethane Foam Insulation Materials

    Science.gov (United States)

    McGill, Preston; Wells, Doug; Morgan, Kristin

    2006-01-01

    Experimental evaluation of the basic fracture properties of Thermal Protection System (TPS) polyurethane foam insulation materials was conducted to validate the methodology used in estimating critical defect sizes in TPS applications on the Space Shuttle External Fuel Tank. The polyurethane foam found on the External Tank (ET) is manufactured by mixing liquid constituents and allowing them to react and expand upwards - a process which creates component cells that are generally elongated in the foam rise direction and gives rise to mechanical anisotropy. Similarly, the application of successive foam layers to the ET produces cohesive foam interfaces (knitlines) which may lead to local variations in mechanical properties. This study reports the fracture toughness of BX-265, NCFI 24-124, and PDL-1034 closed-cell polyurethane foam as a function of ambient and cryogenic temperatures and knitline/cellular orientation at ambient pressure.

  5. Coordination Between the HEU Transparency Program and the Material Protection, Control and Accountability Program

    International Nuclear Information System (INIS)

    Glaser, J.; Hernandez, J.; Dougherty, D.; Bieniawski, A.; Cahalane, P.; Mastal, E.

    2000-01-01

    DOE sponsored programs such as Material Protection Control and Accountability (MPC and A) and implementation of the Highly-Enriched Uranium (HEU) Transparency Program send US personnel into Russian nuclear facilities and receive Russian representatives from these programs. While there is overlap in the Russian nuclear facilities visited by these two programs, there had not been any formal mechanism to share information between them. Recently, an MPC and A/HEU Working Group was developed to facilitate the sharing of appropriate information and to address concerns expressed by Minatom and Russian facility personnel such as US visit scheduling conflicts. This paper discusses the goals of the Working Group and ways it has helped to allow the programs to work more efficiently with the Russian facilities

  6. Supporting the material control and accountancy system with physical protection system features

    International Nuclear Information System (INIS)

    Miyoshi, D.S.; Caskey, D.L.; Olson, C.E.

    1984-01-01

    Most physical security functions can be accomplished by a range of alternative features. Careful design can provide comparable levels of security regardless of which option is chosen, albeit with possible differences in cost and efficiency. However, the effectiveness and especially the cost and efficiency of the material control and accounting system may be strongly influenced by the selection of a particular design approach to physical security. In this paper, a series of examples are cited to illustrate the effects that particular physical protection design choices may have. The examples have been chosen from several systems engineering projects at facilities within the DOE nuclear community. These examples are generalized, and a series of design principles are proposed for integrating physical security with MC and A by appropriate selection of alternative features

  7. 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

  8. Research progress of VO2 thin film as laser protecting material

    Science.gov (United States)

    Liu, Zhiwei; Lu, Yuan; Hou, Dianxin

    2018-03-01

    With the development of laser technology, the battlefield threat of directional laser weapons is becoming more and more serious. The blinding and destruction caused by laser weapons on the photoelectric equipment is an important part of the current photo-electronic warfare. The research on the defense technology of directional laser weapons based on the phase transition characteristics of VO2 thin films is an important subject. The researches of VO2 thin films are summarized based on review these points: the preparation methods of VO2 thin films, phase transition mechanism, phase transition temperature regulating, interaction between VO2 thin films and laser, and the application prospect of vo2 thin film as laser protecting material. This paper has some guiding significance for further research on the VO2 thin films in the field of defense directional laser weapons.

  9. Refractory Materials for Flame Deflector Protection System Corrosion Control: Coatings Systems Literature Survey

    Science.gov (United States)

    Calle, Luz M.; Hintze, Paul E.; Parlier, Christopher R.; Sampson, Jeffrey W.; Coffman, Brekke E.; Coffman, Brekke E.; Curran, Jerome P.; Kolody, Mark R.; Whitten, Mary; Perisich, Steven; hide

    2009-01-01

    When space vehicles are launched, extreme heat, exhaust, and chemicals are produced and these form a very aggressive exposure environment at the launch complex. The facilities in the launch complex are exposed to this aggressive environment. The vehicle exhaust directly impacts the flame deflectors, making these systems very susceptible to high wear and potential failure. A project was formulated to develop or identify new materials or systems such that the wear and/or damage to the flame deflector system, as a result of the severe environmental exposure conditions during launches, can be mitigated. This report provides a survey of potential protective coatings for the refractory concrete lining on the steel base structure on the flame deflectors at Kennedy Space Center (KSC).

  10. Computerized ECT data analysis system

    International Nuclear Information System (INIS)

    Miyake, Y.; Fukui, S.; Iwahashi, Y.; Matsumoto, M.; Koyama, K.

    1988-01-01

    For the analytical method of the eddy current testing (ECT) of steam generator tubes in nuclear power plants, the authors have developed the computerized ECT data analysis system using a large-scale computer with a high-resolution color graphic display. This system can store acquired ECT data up to 15 steam generators, and ECT data can be analyzed immediately on the monitor in dialogue communication with a computer. Analyzed results of ECT data are stored and registered in the data base. This system enables an analyst to perform sorting and collecting of data under various conditions and obtain the results automatically, and also to make a plan of tube repair works. This system has completed the test run, and has been used for data analysis at the annual inspection of domestic plants. This paper describes an outline, features and examples of the computerized eddy current data analysis system for steam generator tubes in PWR nuclear power plants

  11. NEW TECHNOLOGIES FOR RESTORATION AND PROTECTION OF POWER EQUIPMENT WITH THE AID OF COMPOSITE MATERIALS

    Directory of Open Access Journals (Sweden)

    A. O. Ischenko

    2017-01-01

    Full Text Available The analysis of possible variants of reconstruction of the power equipment is fulfilled and the conclusion concerning the prospects of such work with the use of composite materials is reached. The data on the technical characteristics of composite repair materials for various purposes are presented, the results of repairs of power equipment, in particular the technology for the recovery of the boarding surfaces of the diffuser rings and protection of the pumps D1250 casings are provided. The technology of the recovery pneumatic cylinder, hydraulic cylinder rod, as well as the unique technology of restoration of working surfaces of the impeller vanes of transfer pump, that had been destroyed by corrosion in conjunction with the cavitation processes and were considered as not restorable is described. The restored impeller was in operation during a year and only thereafter it was removed for restoration. Another composite material discussed in the article – diagum – makes it possible to perform a series of repairs associated with restoration of the rubber-covered surfaces of pump casings as well as with restoration of various surfaces of the conveyor belts. Taking the excellent adhesive properties of this composite into account, restoration of worn stainless steel sieve screens to remove abrasive material was fulfilled with the aid of it. The restoration was accomplished via the use of the conveyor belt which application time had expired, that was glued to a metal sieve with diagum. The use of the composites is economically justified, because the application of them in repairs reduces, firstly, terms of restoration work and, secondly, the price of repairs. Third, equipment that was damaged beyond repair is being commissioned by the use of the mentioned composites. 

  12. New method for evaluating the kinetic constant of thermal protection materials

    International Nuclear Information System (INIS)

    Bae, Ji Yeul; Yi, Jong Ju; Park, Sul Ki; Cho, Hyung Hee; Bae, Ju Chan; Ham, Hee Cheol

    2013-01-01

    Thermal protection material (TPM) is used to protect rocket structures from extreme conditions created by the hot exhaust of the rocket. Designing TPM is an important step in the rocket design process. Considering that an increase in the system weight decreases the overall performance of a rocket, the amount of TPM is carefully determined during the design process. Therefore, the precise properties of TPM guarantee an accurate thermal analysis and the successful design of the rocket. Among the many properties of TPM, the kinetic constant and activation energy, which govern the thermochemical reaction of the TPM, are the most important. Thus, an experiment to measure the kinetic constant and activation energy is conducted as part of this research. A theoretical approach to deduce the properties from measured data is discussed, and a method to apply the theory to experimental data, termed the R 2 method, is developed. Compared to a previous method which was difficult to apply, the R 2 method reduces unclear selections of the reaction time and does not require intervention by an interpreter. The properties deduced by the R 2 method show good agreement with the other method despite the limited number of experimental results.

  13. New method for evaluating the kinetic constant of thermal protection materials

    Energy Technology Data Exchange (ETDEWEB)

    Bae, Ji Yeul; Yi, Jong Ju; Park, Sul Ki; Cho, Hyung Hee [Yonsei University, Seoul (Korea, Republic of); Bae, Ju Chan; Ham, Hee Cheol [Agency for Defense Development, Daegu (Korea, Republic of)

    2013-06-15

    Thermal protection material (TPM) is used to protect rocket structures from extreme conditions created by the hot exhaust of the rocket. Designing TPM is an important step in the rocket design process. Considering that an increase in the system weight decreases the overall performance of a rocket, the amount of TPM is carefully determined during the design process. Therefore, the precise properties of TPM guarantee an accurate thermal analysis and the successful design of the rocket. Among the many properties of TPM, the kinetic constant and activation energy, which govern the thermochemical reaction of the TPM, are the most important. Thus, an experiment to measure the kinetic constant and activation energy is conducted as part of this research. A theoretical approach to deduce the properties from measured data is discussed, and a method to apply the theory to experimental data, termed the R{sup 2} method, is developed. Compared to a previous method which was difficult to apply, the R{sup 2} method reduces unclear selections of the reaction time and does not require intervention by an interpreter. The properties deduced by the R{sup 2} method show good agreement with the other method despite the limited number of experimental results.

  14. Quantitative inspection by computerized tomography

    International Nuclear Information System (INIS)

    Lopes, R.T.; Assis, J.T. de; Jesus, E.F.O. de

    1989-01-01

    The computerized Tomography (CT) is a method of nondestructive testing, that furnish quantitative information, that permit the detection and accurate localization of defects, internal dimension measurement, and, measurement and chart of the density distribution. The CT technology is much versatile, not presenting restriction in relation to form, size or composition of the object. A tomographic system, projected and constructed in our laboratory is presented. The applications and limitation of this system, illustrated by tomographyc images, are shown. (V.R.B.)

  15. Establishing design basis threats for the physical protection of nuclear materials and facilities

    International Nuclear Information System (INIS)

    Chetvergov, S.

    2001-01-01

    In the area of nuclear energy utilization, the Republic of Kazakhstan follows the standards of international legislation and is a participant of the Nuclear Weapons Non-proliferation Treaty as a country that does not have nuclear weapons. In the framework of this treaty, Kazakhstan provides for the measures to ensure the regime of nonproliferation. The Republic signed the Agreement with the IAEA on the guarantee that was ratified by the Presidential Decree in 1995. Now the Government of the RK is considering the Convention on Physical Protection of Nuclear Materials. Kazakhstan legislation in the area of nuclear energy utilization is represented by a set of laws: the main of them is the Law of the Republic of Kazakhstan 'On the utilization of atomic energy', dated April 14, 1997. According to the Law, the issues of physical protection are regulated by interdepartmental guideline documents. Nuclear science and industry of RK include: Enterprises on uranium mining and processing; Ulba metallurgical plant, manufacturing fuel pellets of uranium dioxide for heat release assemblies of RBMK and WWR reactor types, with the enrichment on U235 1.6-4.4%; Power plant in Aktau for heat and power supply and water desalination, based on fast breeder reactor BN-350; Research reactors of National Nuclear Center: WWR-K - water-water reactor, with 10 MW power, uses highly enriched uranium (up to 36% of U-235); IVG.1M - water-water heterogeneous reactor of vessel type on thermal neutrons, maximum power is 35 MW; IGR - impulse homogeneous graphite reactor on thermal neutrons, with graphite reflector; RA - high temperature gas cooled reactor on thermal neutrons, 0.5 MW power. The establishment of design basis threats for nuclear objects in the Republic of Kazakhstan is an urgent problem because of the developing military-political situation in the region. It is necessary to specify important elements affecting the specific features of the design basis threat: military operations of

  16. Radiological protection principles concerning the safeguard, use or release of contaminated materials, buildings, areas or dumps from uranium mining. Recommendations of the Commission on Radiological Protection with explanations

    International Nuclear Information System (INIS)

    Mueller-Neumann, M.

    1992-01-01

    The volume presents the full texts of the SSK Recommendations addressing the aspects and problems involved, and which can be separately retrieved from the database: 1) Radiological protection principles concerning the release of scrap from the shut-down of uranium mining plants; 2) Radiological protection principles concerning the release for industrial use of areas contaminated from uranium mining; 3) Radiological protection principles concerning the use for forest and agricultural purposes and as public gardens (parks) and residential areas of areas contaminated from uranium mining; 4) Radiological protection principles concerning the safeguard and use of mine dumps; 5) Radiological protection principles concerning the release for further commercial or industrial use of buildings used for commercial or industrial purposes and the disposal of building debris from uranium mining and milling; 6) Radiological protection principles concerning the release for general use of reusable equipment and installations from uranium mining. The following appendices round up the material: 1) Radiation exposure from mining in Saxony and Thuringia and its evaluation (Summary of the results of consultations during the 1990 closed meeting); 2) Radiological protection principles for the limitation of the radiation exposure of the public to radon and its daughters; 3) Epidemiological studies on the health state of the inhabitants of the mining region and the miners in Saxony and Thuringia. (orig.) [de

  17. The effect of specifi c relationship between material and coating on tribological and protective features of the product

    Directory of Open Access Journals (Sweden)

    B. Sovilj

    2012-01-01

    Full Text Available Today, parts and tools are increasingly made of composite materials. Realization of specifi c connection between basic material and coating is very important. The quality of coating on products, in terms of wear and resistance to destruction, has a large impact on productivity and reliability of production processes, in particular their life. In this paper, based on experimental investigations, the effect of specific relationship between the base material and coating on tribological and protective features of the product is analyzed.

  18. Spatially distributed damage detection in CMC thermal protection materials using thin-film piezoelectric sensors

    Science.gov (United States)

    Kuhr, Samuel J.; Blackshire, James L.; Na, Jeong K.

    2009-03-01

    Thermal protection systems (TPS) of aerospace vehicles are subjected to impacts during in-flight use and vehicle refurbishment. The damage resulting from such impacts can produce localized regions that are unable to resist extreme temperatures. Therefore it is essential to have a reliable method to detect, locate, and quantify the damage occurring from such impacts. The objective of this research is to demonstrate a capability that could lead to detecting, locating and quantifying impact events for ceramic matrix composite (CMC) wrapped tile TPS via sensors embedded in the TPS material. Previous research had shown a correlation between impact energies, material damage state, and polyvinylidene fluoride (PVDF) sensor response for impact energies between 0.07 - 1.00 Joules, where impact events were located directly over the sensor positions1. In this effort, the effectiveness of a sensor array is evaluated for detecting and locating low energy impacts on a CMC wrapped TPS. The sensor array, which is adhered to the internal surface of the TPS tile, is used to detect low energy impact events that occur at different locations. The analysis includes an evaluation of signal amplitude levels, time-of-flight measurements, and signal frequency content. Multiple impacts are performed at each location to study the repeatability of each measurement.

  19. Support to the physical protection and accountancy for nuclear materials in Kazakstan

    International Nuclear Information System (INIS)

    Hashimoto, Yu.; Yoshida, M.; Akutsu, M.; Takeda, H.

    1998-01-01

    The support programs for Republic of Kazakstan have been carried out for the purpose of establishing the State System of Accounting for and Control of Nuclear Material (SSAC). These support are based on the cooperation agreement for the elimination of nuclear weapons, that reached mutual agreement between both government of Japan and the Republic of Kazakstan in March, 1994, 1994. Japan, Sweden, the United Kingdom and the United States of America have conducted the support for Kazakstan. Since there are many facilities to be supported such as fast reactors, fuel fabrication facilities and research facilities, items to be supported are coordinated and shared among the supporting countries. Japan has been carrying out the supporting tasks mainly for the fast breeder reactor facility, BN-350 and Atomic Energy Agency of Kazakstan (KAEA). PESCO Co., Ltd. is entrusted this supporting work from Technical Secretariat on Cooperation for the Elimination of Nuclear Weapons Reduced in the Former Soviet Union, and has conducted the support in the area of flow monitoring system, nuclear material accounting and control and physical protection, obtaining technical cooperation from Power Reactor and Nuclear Development Corporation (PNC)

  20. Class notes from the first international training course on the physical protection of nuclear facilities and materials

    Energy Technology Data Exchange (ETDEWEB)

    Herrington, P.B. (ed.)

    1979-05-01

    The International Training Course on Physical Protection of Nuclear Facilities and Materials was intended for representatives from the developing countries who are responsible for preparing regulations and designing and assessing physical protection systems. The first part of the course consists of lectures on the objectives, organizational characteristics, and licensing and regulations requirements of a state system of physical protection. Since the participants may have little experience in nuclear energy, background information is provided on the topics of nuclear materials, radiation hazards, reactor systems, and reactor operations. Transportation of nuclear materials is addressed and emphasis is placed on regulations. Included in these discussions are presentations by guest speakers from countries outside the United States of America who present their countries' threat to nuclear facilities. Effectiveness evaluation methodology is introduced to the participants by means of instructions which teach them how to use logic trees and the EASI (Estimate of Adversary Sequence Interruption) program. The following elements of a physical protection system are discussed: barriers, protective force, intrusion detection systems, communications, and entry-control systems. Total systems concepts of physical protection system design are emphasized throughout the course. Costs, manpower/technology trade-offs, and other practical considerations are discussed. Approximately one-third of the course is devoted to practical exercises during which the attendees participatein problem solving. A hypothetical nuclear facility is introduced, and the attendees participate in the conceptual design of a physical protection system for the facility.

  1. Class notes from the first international training course on the physical protection of nuclear facilities and materials

    International Nuclear Information System (INIS)

    Herrington, P.B.

    1979-05-01

    The International Training Course on Physical Protection of Nuclear Facilities and Materials was intended for representatives from the developing countries who are responsible for preparing regulations and designing and assessing physical protection systems. The first part of the course consists of lectures on the objectives, organizational characteristics, and licensing and regulations requirements of a state system of physical protection. Since the participants may have little experience in nuclear energy, background information is provided on the topics of nuclear materials, radiation hazards, reactor systems, and reactor operations. Transportation of nuclear materials is addressed and emphasis is placed on regulations. Included in these discussions are presentations by guest speakers from countries outside the United States of America who present their countries' threat to nuclear facilities. Effectiveness evaluation methodology is introduced to the participants by means of instructions which teach them how to use logic trees and the EASI (Estimate of Adversary Sequence Interruption) program. The following elements of a physical protection system are discussed: barriers, protective force, intrusion detection systems, communications, and entry-control systems. Total systems concepts of physical protection system design are emphasized throughout the course. Costs, manpower/technology trade-offs, and other practical considerations are discussed. Approximately one-third of the course is devoted to practical exercises during which the attendees participatein problem solving. A hypothetical nuclear facility is introduced, and the attendees participate in the conceptual design of a physical protection system for the facility

  2. Development of a ceramic material to cover walls to be applied in diagnostic radiological protection

    International Nuclear Information System (INIS)

    Frimaio, Audrew

    2006-01-01

    This study aims to formulate a ceramic composition for wall coating seeking to contribute to the optimization of diagnosis rooms' shielding. The work was based on experimental measures of X-radiation attenuation (80 and 100 kV) using ceramic coating materials containing different ceramic bases (red, white, gres, stoneware porcelain tiles, etc). Among the appraised ceramic bases, the white gres presented better attenuation properties and it was considered the most suitable material for the targets of this work. Different formulations of white gres were studied and altered in order to obtain better attenuation properties. Simulations of ceramic compositions using gres coating were made maintaining the percentages of 12-20% clay; 6-18% kaolin; 12-25% phyllite; 8-14% quartz; 1018% feldspar; 32-40% pegmatite and 6-8% talc in the composition of the necessary raw-material. The quantitative and qualitative chemical compositions of these materials were also evaluated and the most common representative elements are SiO 2 , Fe 2 O 3 , Al 2 O 3 , CaO and Ti 2 O 3 . Formulations containing Pb and Ba oxides were studied, considering that CaO can be replaced by PbO or BaO. The attenuation properties for X-radiation were investigated by computer simulations considering the incident and transmitted X-ray spectra for the different studied compositions and they were compared to the properties of the reference materials Pb, Ba and BaSO 4 (barite). The results obtained with the simulations indicated the formulated composition of gres ceramic base that presented better attenuation properties considering the X-ray energies used in diagnosis (80, 100 and 150 kV). Ceramic plates based on the formulated compositions that presented lower percentage differences related to Pb were experimentally produced and physically tested as wall coating and protecting barrier. Properties as flexion resistance module, density, load rupture, water absorption and X radiation attenuation were evaluated for

  3. Carbon fiber CVD coating by carbon nanostructured for space materials protection against atomic oxygen

    Science.gov (United States)

    Pastore, Roberto; Bueno Morles, Ramon; Micheli, Davide

    2016-07-01

    In recent years, the emphasis in space research has been shifting from space exploration to commercialization of space. In order to utilize space for commercial purposes it is necessary to understand the low earth orbit (LEO) space environment where most of the activities will be carried out. The studies on the LEO environment are mainly focused towards understanding the effect of atomic oxygen (AO) on spacecraft materials. In the first few shuttle flights, materials looked frosty because they were actually being eroded and textured: AO reacts with organic materials on spacecraft exteriors, gradually damaging them. When a spacecraft travel in LEO (where crewed vehicles and the International Space Station fly), the AO formed from the residual atmosphere can react with the spacecraft surfaces, causing damage to the vehicle. Polymers are widely used in space vehicles and systems as structural materials, thermal blankets, thermal control coatings, conformal coatings, adhesives, lubricants, etc. Exposure of polymers and composites to the space environment may result in different detrimental effects via modification of their chemical, electrical, thermal, optical and mechanical properties as well as surface erosion. The major degradation effects in polymers are due to their exposure to atomic oxygen, vacuum ultraviolet and synergistic effects, which result in different damaging effects by modification of the polymer's chemical properties. In hydrocarbon containing polymers the main AO effect is the surface erosion via chemical reactions and the release of volatile reaction products associated with the mass loss. The application of a thin protective coating to the base materials is one of the most commonly used methods of preventing AO degradation. The purpose is to provide a barrier between base material and AO environment or, in some cases, to alter AO reactions to inhibit its diffusion. The effectiveness of a coating depends on its continuity, porosity, degree of

  4. Protective or damage promoting effect of calcium carbonate layers on the surface of cement based materials in aqueous environments

    International Nuclear Information System (INIS)

    Schwotzer, M.; Scherer, T.; Gerdes, A.

    2010-01-01

    Cement based materials permanently exposed to aggressive aqueous environments are subject to chemical changes affecting their durability. However, this holds also for tap water that is considered to be not aggressive to cementitious materials, although in that case a formation of covering layers of CaCO 3 on the alkaline surfaces is commonly supposed to provide protection against reactive transport processes. Thus, investigations of the structural and chemical properties of the material/water interface were carried out in laboratory experiments and case studies to elucidate the consequences of surface reactions for the durability of cement based materials exposed to tap water. Focused Ion Beam investigations revealed that a protective effect of a CaCO 3 covering layer depends on its structural properties, which are in turn affected by the hydro-chemical conditions during crystallization. Surface precipitation of CaCO 3 can trigger further chemical degradation, if the required calcium is supplied by the pore solution of the material.

  5. US/Belarusian government-to-government material protection, control, and accounting cooperation at the Sosny Science and Technology Center

    International Nuclear Information System (INIS)

    Case, R.S. Jr.; Baumann, M.; Madsen, R.W.; Krevsum, E.; Haase, M.

    1996-01-01

    A formal program of cooperation between the US Department of Energy and the Belarusian regulatory agency Promatomnazdor (PAN) began in 1994. A visit to the Belarusian Sosny Science and Technology Center (SSTC) by representatives from the US, Sweden, Japan, and the International Atomic Energy Agency resulted in a multinational program of cooperation to enhance the existing material protection, control, and accounting systems in place at Sosny. Specific physical-protection-related recommendations included upgrades to the physical protection systems at Buildings 33 and 40 at Sosny and the security systems in the SSTC central alarm station. US experts in conjunction with the multinational team and Belarus representatives, have reviewed initial designs for physical protection upgrades at Sosny. Subsequently, the US assumed an essential role for funding and technical oversight for enhancements at the SSTC, aspects of its emergency communication systems, and the upgrade of the SSTC site access control system. This paper addresses the status of physical protection enhancements at the Sosny site

  6. Standard format and content of a licensee physical protection plan for strategic special nuclear material in transit - April 1980

    International Nuclear Information System (INIS)

    Anon.

    1981-01-01

    A predetermined plan to respond to safeguards contingency events is required to be prepared, based on personnel and other physical protection resources described in the Physical Protection Plan for strategic special nuclear material (SSNM) in transit. Specific requirements for the contingency plan are provided in Appendix C. Licensee Safeguards Contingency Plans, to 10 CFR Part 73. Regulatory Guide 5.56, Standard Format and Content of Safeguards Contingency Plans for Transportation, provides guidance for the preparation of transportation contingency plans. Licensee is reminded that all three submissions - the Physical Protection Plan, the Physical Protection Arrangements for Specific Shipments, and the Safeguards Contingency Plan - together describe the system for physical protection of each particular shipment. They should be developed and maintained to be completely consistent with each other for each shipment

  7. Effectiveness of common fish screen materials for protecting lamprey ammocoetes—Influence of sweeping velocities and decreasing flows

    Science.gov (United States)

    Mesa, Matthew G.; Liedtke, Theresa L.; Weiland, Lisa K.; Christiansen, Helena E.

    2017-12-14

    In previous tests of the effectiveness of four common fish screen materials for excluding lamprey ammocoetes, we determined that woven wire (WW) allowed substantially more entrainment than perforated plate (PP), profile bar (PB), or Intralox (IL) material. These tests were simplistic because they used small vertically-oriented screens positioned perpendicular to the flow without a bypass or a sweeping velocity (SV). In the subsequent test discussed in this report, we exposed ammocoetes to much larger (2.5-m-wide) screen panels with flows up to 10 ft3 /s, a SV component, and a simulated bypass channel. The addition of a SV modestly improved protection of lamprey ammocoetes for all materials tested. A SV of 35 cm/s with an approach velocity (AV) of 12 cm/s, was able to provide protection for fish about 5–15 mm smaller than the protection provided by an AV of 12 cm/s without a SV component. The best-performing screen panels (PP, IL, and PB) provided nearly complete protection from entrainment for fish greater than 50-mm toal length, but the larger openings in the WW material only protected fish greater than 100-mm total length. Decreasing the AV and SV by 50 percent expanded the size range of protected lampreys by about 10–15 mm for those exposed to IL and WW screens, and it decreased the protective ability of PP screens by about 10 mm. Much of the improvement for IL and WW screens under the reduced flow conditions resulted from an increase in the number of lampreys swimming away from the screen. Fish of all sizes became impinged (that is, stuck on the screen surface for more than 1 s) on the screens, with the rate of impingement highest on PP (39– 72 percent) and lowest on WW (7–22 percent). Although impingements were common, injuries were rare, and 24-h post-test survival was greater than 99 percent. Our results refined the level of protection provided by these screen materials when both an AV and SV are present and confirmed our earlier recommendation that

  8. Bill project authorizing the approval of the amendment to the convention on physical protection of nuclear material - Nr 11

    International Nuclear Information System (INIS)

    Ayrault, Jean-Marc; Fabius, Laurent

    2012-01-01

    This document contains the brief text of the bill project and the text of the amendment to the Convention on physical protection of nuclear material which has been adopted in Vienna in August 2005 to amend the Convention adopted in October 1979. This amendment introduces the following measures: extension of the scope of application of the Convention to nuclear materials used for peaceful purposes, definition of the objectives of the Convention, articulation of the Convention with other international instruments, definition of the main principles of physical protection, strengthened international cooperation, legal issues concerning extradition and legal cooperation

  9. Slovenian System for Protecting Against Radioactive Material in Scrap Metal Shipments

    Energy Technology Data Exchange (ETDEWEB)

    Stritar, A.; Cesarek, J.; Vokal Nemec, B., E-mail: andrej.stritar@gov.si [Slovenian Nuclear Safety Administration, Ljubljana (Slovenia)

    2011-07-15

    The Slovenian experience shows that the majority of detected orphan sources are associated with imports of scrap metal to Slovenia and transits of that material through Slovenia. Such orphan sources originate from past industrial activities and weak regulatory control in the countries of origin. In order to minimise the number of sources outside regulatory control several regulatory and law enforcement measures have been implemented. To prevent illicit trafficking across the border the 'First line of defence' - customs and police - are equipped with radiation detection devices. Since 2002, the Slovenian Nuclear Safety Administration (SNSA) has provided a 24-hour on-duty officer, who gives advice in case of the discovery of an orphan source. The majority of scrap metal collectors and re-cyclers are equipped with portal monitors and/or hand-held radiation detection equipment. Generally, good cooperation has been established between different organizations within Slovenia, with neighbouring countries and with some international organizations. To regulate the scrap metal activities, a new Decree on checking the radioactivity of shipments of metal scrap has been in force since 1 January 2008. This decree requires that every importer has to present a certificate of radiation measurement before any shipment of scrap metal is brought into Slovenia. Such measurements can be performed only by certified organizations. These organizations can obtain certification from the SNSA providing that they have the prescribed measuring devices, adequate training and procedures, and that their capabilities have been checked by a technical support organization. The experience after one year of application of the decree is positive. Awareness, including the adequacy of response, has increased. The paper discusses the general scheme for protection against illicit radioactive material in scrap metal shipments and the Slovenian experience in the last decade. (author)

  10. Some aspects of using Be as high heat flux protective armour material

    International Nuclear Information System (INIS)

    Gervash, A.; Mazul, I.; Yablokov, N.; Linke, J.

    2000-01-01

    The beryllium as plasma facing armour material must protect the actively cooled copper alloy heat sink of the First Wall and Divertor components from sputtering erosion, disruption and VDE transients and withstand the number of cycles under expected heat and neutron fluxes. The presented paper discusses some topical questions and presents recent results obtained in Russia in the frame of such consideration. In real operation beryllium as plasma facing component will be subjected to sequence of normal (cyclic heat fluxes) and off-normal (disruption, VDE) heat loads. Aiming to investigate the results of mentioned events the experiments with the number of Russian Be grades (DShG-200, TGP-56, TShG-56, TR-30, Condensed Be) as well as S-65C (ITER reference grade) at simulated disruption loads (∝5 MJ/m 2 ) and subsequent thermal cycling (∝5 MW/m 2 , 1000 cycles) were carried out. Experiments have revealed no macroscopic damage of the tested grades, although significant differences in crack formation and propagation were observed. The main statistics of performed experiments is presented and discussed. One of the main requirements to use Be as a candidate for plasma facing component is providing a reliable joint between Be and Cu-alloy heat sink structure. The unique Russian fast brazing process of joining beryllium to Cu-alloy that allows to survive high heat fluxes ≥10 MW/m 2 during thousand heating/cooling cycles without serious damaging in the armour material and its joint was described in previous works. The main goal of experiments presented in this paper was to study the high heat flux durability limit for joints as function of the pulse duration (i.e. investigation of creep/fatigue interaction). Authors present a description of the testing procedure and discuss the first results of mentioned experiments. (orig.)

  11. Computerized tomography of orbital lesions

    International Nuclear Information System (INIS)

    Kuroiwa, Mayumi

    1981-01-01

    Two different types of computerized tomography scanners (CT scanner), i.e. a whole-body CT scanner (GE-CT/T8800) and a cerebral CT scanner (EMI-1010), were compared in the assessment and diagnosis of various orbital lesions. The whole-body CT scanner was found to be advantageous over the cerebral CT scanner for the following reasons: (1) CT images were more informative due to thinner slices associated with smaller-sized and larger-numbered matrices; (2) less artifacts derived from motion of the head or eyeball were produced because of the shorter scanning time; (3) with a devised gantry, coronal dissections were available whenever demanded. (author)

  12. Services of radiological protection: as sizing the human and material resources

    International Nuclear Information System (INIS)

    Rueda Guerrero, M. D.; Sierra Perler, I.; Lorenzo Perez, P.

    2014-01-01

    Discussion of radiological protection in the Middle Health has formed a task force to develop a technical document recommendatory to help plan and evaluate resources radiological protection services. (Author)

  13. Synthesis and testing of a conducting polymeric composite material for lightning strike protection applications

    Science.gov (United States)

    Katunin, A.; Krukiewicz, K.; Turczyn, R.; Sul, P.; Łasica, A.; Catalanotti, G.; Bilewicz, M.

    2017-02-01

    Lightning strike protection is one of the important issues in the modern maintenance problems of aircraft. This is due to a fact that the most of exterior elements of modern aircraft is manufactured from polymeric composites which are characterized by isolating electrical properties, and thus cannot carry the giant electrical charge when the lightning strikes. This causes serious damage of an aircraft structure and necessity of repairs and tests before returning a vehicle to operation. In order to overcome this problem, usually metallic meshes are immersed in the polymeric elements. This approach is quite effective, but increases a mass of an aircraft and significantly complicates the manufacturing process. The approach proposed by the authors is based on a mixture of conducting and dielectric polymers. Numerous modeling studies which are based on percolation clustering using kinetic Monte Carlo methods, finite element modeling of electrical and mechanical properties, and preliminary experimental studies, allow achieving an optimal content of conducting particles in a dielectric matrix in order to achieve possibly the best electrical conductivity and mechanical properties, simultaneously. After manufacturing the samples with optimal content of a conducting polymer, mechanical and electrical characterization as well as high-voltage testing was performed. The application of such a material simplifies manufacturing process and ensures unique properties of aircraft structures, which allows for minimizing damage after lightning strike, as well as provide electrical bounding and grounding, interference shielding, etc. The proposed solution can minimize costs of repair, testing and certification of aircraft structures damaged by lightning strikes.

  14. A new surface catalytic model for silica-based thermal protection material for hypersonic vehicles

    Directory of Open Access Journals (Sweden)

    Li Kai

    2015-10-01

    Full Text Available Silica-based materials are widely employed in the thermal protection system for hypersonic vehicles, and the investigation of their catalytic characteristics is crucially important for accurate aerothermal heating prediction. By analyzing the disadvantages of Norman’s high and low temperature models, this paper combines the two models and proposes an eight-reaction combined surface catalytic model to describe the catalysis between oxygen and silica surface. Given proper evaluation of the parameters according to many references, the recombination coefficient obtained shows good agreement with experimental data. The catalytic mechanisms between oxygen and silica surface are then analyzed. Results show that with the increase of the wall temperature, the dominant reaction contributing to catalytic coefficient varies from Langmuir–Hinshelwood (LH recombination (TW  1350 K. The surface coverage of chemisorption areas varies evidently with the dominant reactions in the high temperature (HT range, while the surface coverage of physisorption areas varies within quite low temperature (LT range (TW < 250 K. Recommended evaluation of partial parameters is also given.

  15. Material Protection, Accounting, and Control Technologies (MPACT): Modeling and Simulation Roadmap

    Energy Technology Data Exchange (ETDEWEB)

    Cipiti, Benjamin [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Dunn, Timothy [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Durbin, Samual [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Durkee, Joe W. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); England, Jeff [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Jones, Robert [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Ketusky, Edward [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Li, Shelly [Idaho National Lab. (INL), Idaho Falls, ID (United States); Lindgren, Eric [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Meier, David [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Miller, Michael [Idaho National Lab. (INL), Idaho Falls, ID (United States); Osburn, Laura Ann [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Pereira, Candido [Argonne National Lab. (ANL), Argonne, IL (United States); Rauch, Eric Benton [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Scaglione, John [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Scherer, Carolynn P. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Sprinkle, James K. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Yoo, Tae-Sic [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2016-08-05

    The development of sustainable advanced nuclear fuel cycles is a long-term goal of the Office of Nuclear Energy’s (DOE-NE) Fuel Cycle Technologies program. The Material Protection, Accounting, and Control Technologies (MPACT) campaign is supporting research and development (R&D) of advanced instrumentation, analysis tools, and integration methodologies to meet this goal. This advanced R&D is intended to facilitate safeguards and security by design of fuel cycle facilities. The lab-scale demonstration of a virtual facility, distributed test bed, that connects the individual tools being developed at National Laboratories and university research establishments, is a key program milestone for 2020. These tools will consist of instrumentation and devices as well as computer software for modeling. To aid in framing its long-term goal, during FY16, a modeling and simulation roadmap is being developed for three major areas of investigation: (1) radiation transport and sensors, (2) process and chemical models, and (3) shock physics and assessments. For each area, current modeling approaches are described, and gaps and needs are identified.

  16. Architecture and material properties of diatom shells provide effective mechanical protection

    Science.gov (United States)

    Hamm, Christian E.; Merkel, Rudolf; Springer, Olaf; Jurkojc, Piotr; Maier, Christian; Prechtel, Kathrin; Smetacek, Victor

    2003-02-01

    Diatoms are the major contributors to phytoplankton blooms in lakes and in the sea and hence are central in aquatic ecosystems and the global carbon cycle. All free-living diatoms differ from other phytoplankton groups in having silicified cell walls in the form of two `shells' (the frustule) of manifold shape and intricate architecture whose function and role, if any, in contributing to the evolutionary success of diatoms is under debate. We explored the defence potential of the frustules as armour against predators by measuring their strength. Real and virtual loading tests (using calibrated glass microneedles and finite element analysis) were performed on centric and pennate diatom cells. Here we show that the frustules are remarkably strong by virtue of their architecture and the material properties of the diatom silica. We conclude that diatom frustules have evolved as mechanical protection for the cells because exceptional force is required to break them. The evolutionary arms race between diatoms and their specialized predators will have had considerable influence in structuring pelagic food webs and biogeochemical cycles.

  17. Thermal buffering performance of composite phase change materials applied in low-temperature protective garments

    Science.gov (United States)

    Yang, Kai; Jiao, Mingli; Yu, Yuanyuan; Zhu, Xueying; Liu, Rangtong; Cao, Jian

    2017-07-01

    Phase change material (PCM) is increasingly being applied in the manufacturing of functional thermo-regulated textiles and garments. This paper investigated the thermal buffering performance of different composite PCMs which are suitable for the application in functional low-temperature protective garments. First, according to the criteria selecting PCM for functional textiles/garments, three kinds of pure PCM were selected as samples, which were n-hexadecane, n-octadecane and n-eicosane. To get the adjustable phase change temperature range and higher phase change enthalpy, three kinds of composite PCM were prepared using the above pure PCM. To evaluate the thermal buffering performance of different composite PCM samples, the simulated low-temperature experiments were performed in the climate chamber, and the skin temperature variation curves in three different low temperature conditions were obtained. Finally composite PCM samples’ thermal buffering time, thermal buffering capacity and thermal buffering efficiency were calculated. Results show that the comprehensive thermal buffering performance of n-octadecane and n-eicosane composite PCM is the best.

  18. Risk analysis and protective measures for occupationally workers with technologically enhanced naturally occurring radioactive materials

    International Nuclear Information System (INIS)

    Hegazy, R.A.M.

    2011-01-01

    Naturally occurring radionuclides are present in many natural resources. Elevated concentrations of these radionuclides are often found in certain geological materials, namely igneous rocks and ores. Human activities that exploit these resources may lead to enhanced concentrations of radionuclides (often referred to as technologically enhanced naturally occurring radioactive material (TE-NORM). Enhanced levels of natural background radiation are encountered in many occupational industrial activities involving a large number of workers. Uncontrolled activities associated with TE-NORM can contaminate the environment and pose a risk to human health. This risk can be alleviated by the adoption of controls to identify where NORM is present; and cleaning the NORM-contaminated equipment and waste management while protecting workers. The main objective of this study is to investigate the natural radioactivity and the hazard parameters in the TE-NORM samples from different industrial activities. Also to describe the models and develop the computer codes that allow one to estimate the risk of cancer resulting from any specified dose of ionizing radiation for occupationally workers in different industrial activities. The present study deals with 50 different samples. This waste generated from petroleum fields, phosphate fertilizers samples, consumer product samples from China, ceramic and zircon samples. The radon exhalation rates calculated using solid state nuclear track detector (CR-39). The value of radon exhalation rate 58.82±5.3 x10 3 , 4.28±0.49 x10 3 and 0.306±0.025 x10 3 Bq/m 2 h for scale, sludge and sand, respectively. The value of radon exhalation rate 82.67±7.98, 62.58 ±5.7, 46.16 ±3.91 and 198.51±18.68 Bq/m 2 h for phosphate fertilizers samples, consumer product samples from China, ceramic and zircon samples, respectively. The 226 Ra activity concentrations were 301.4±771.5, 52.1±438 and 2.56±55.37 kBq/kg for scale, sludge and sand, respectively. The

  19. Computerization of operation and maintenance for nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-07-01

    This report provides a resource for computerization of activities in plant operation and maintenance. Experience gained from design and implementation of various computer systems around the world is described. The material may be useful as a guide to modification and upgrading of existing plants as well as design and engineering of new plants. It should be particularly of interest to managers and engineers who are engaged in planning, bidding, specifying or designing computer systems for operation and maintenance applications. Refs, figs and tabs.

  20. Computerization of operation and maintenance for nuclear power plants

    International Nuclear Information System (INIS)

    1995-07-01

    This report provides a resource for computerization of activities in plant operation and maintenance. Experience gained from design and implementation of various computer systems around the world is described. The material may be useful as a guide to modification and upgrading of existing plants as well as design and engineering of new plants. It should be particularly of interest to managers and engineers who are engaged in planning, bidding, specifying or designing computer systems for operation and maintenance applications. Refs, figs and tabs

  1. Preliminary assessment on the differences of nuclear terrorism convention from the convention on the physical protection of nuclear material and amendment to the convention on the physical protection of nuclear material

    International Nuclear Information System (INIS)

    Midiana Ariethia; Muhamad Ilman A A; Mas Pungky Hendrawijaya

    2011-01-01

    The threat of acts of nuclear terrorism in all its forms and manifestations create the urgent need to enhance international cooperation between countries in designing and following practical and effective measures for the prevention of acts of terrorism and to counter and punish its offenders. Several United Nations Security Council Resolutions, such as UNSCR Number 1373 (2001), and UNSCR Number 1540 (2005), and the result of Nuclear Security Summit in 2010 that encourage the member countries of IAEA to ratify nuclear conventions as soon as possible, are the reasons that the Indonesian Government planning on ratifying The International Convention for The Suppression of Acts of Nuclear Terrorism (Nuclear Terrorism Convention). Nuclear Terrorism Convention is one of the 16 (sixteen) international instruments that must be ratified by the member countries of IAEA. Of the 16 (sixteen) international instruments, 3 (three) conventions are related to nuclear; Convention on the Physical Protection of Nuclear Material, Amendment to the Convention on the Physical Protection of Nuclear Material, dan Nuclear Terrorism Convention. This paper presents the preliminary assessment on the differences of Nuclear Terrorism Convention to The Convention on The Physical Protection of Nuclear Material and Amendment to The Convention on The Physical Protection of Nuclear Material. This assessment is important due to the plan of the Indonesian Government to ratify the Nuclear Terrorism Convention. The result of this assessment could be used by BAPETEN in the ratification process of the Nuclear Terrorism Convention. The method used in this assessment is references assessment. (author)

  2. Morphological analysis of the vestibular aqueduct by computerized tomography images

    International Nuclear Information System (INIS)

    Marques, Sergio Ricardo; Smith, Ricardo Luiz; Isotani, Sadao; Alonso, Luis Garcia; Anadao, Carlos Augusto; Prates, Jose Carlos; Lederman, Henrique Manoel

    2007-01-01

    Objective: In the last two decades, advances in the computerized tomography (CT) field revise the internal and medium ear evaluation. Therefore, the aim of this study is to analyze the morphology and morphometric aspects of the vestibular aqueduct on the basis of computerized tomography images (CTI). Material and method: Computerized tomography images of vestibular aqueducts were acquired from patients (n = 110) with an age range of 1-92 years. Thereafter, from the vestibular aqueducts images a morphometric analysis was performed. Through a computerized image processing system, the vestibular aqueduct measurements comprised of its area, external opening, length and the distance from the vestibular aqueduct to the internal acoustic meatus. Results: The morphology of the vestibular aqueduct may be funnel-shaped, filiform or tubular and the respective proportions were found to be at 44%, 33% and 22% in children and 21.7%, 53.3% and 25% in adults. The morphometric data showed to be of 4.86 mm 2 of area, 2.24 mm of the external opening, 4.73 mm of length and 11.88 mm of the distance from the vestibular aqueduct to the internal acoustic meatus, in children, and in adults it was of 4.93 mm 2 , 2.09 mm, 4.44 mm, and 11.35 mm, respectively. Conclusions: Computerized tomography showed that the vestibular aqueduct presents high morphological variability. The morphometric analysis showed that the differences found between groups of children and adults or between groups of both genders were not statistically significant

  3. Computerized index for teaching files

    International Nuclear Information System (INIS)

    Bramble, J.M.

    1989-01-01

    A computerized index can be used to retrieve cases from a teaching file that have radiographic findings similar to an unknown case. The probability that a user will review cases with a correct diagnosis was estimated with use of radiographic findings of arthritis in hand radiographs of 110 cases from a teaching file. The nearest-neighbor classification algorithm was used as a computer index to 110 cases of arthritis. Each case was treated as an unknown and inputted to the computer index. The accuracy of the computer index in retrieving cases with the same diagnosis (including rheumatoid arthritis, gout, psoriatic arthritis, inflammatory osteoarthritis, and pyrophosphate arthropathy) was measured. A Bayes classifier algorithm was also tested on the same database. Results are presented. The nearest-neighbor algorithm was 83%. By comparison, the estimated accuracy of the Bayes classifier algorithm was 78%. Conclusions: A computerized index to a teaching file based on the nearest-neighbor algorithm should allow the user to review cases with the correct diagnosis of an unknown case, by entering the findings of the unknown case

  4. Workshop materials from the 2nd international training course on physical protection of nuclear facilities and materials, Module 13

    International Nuclear Information System (INIS)

    Martin, F.P.

    1980-04-01

    This course is intended for representatives of countries where nuclear power is being developed and whose responsibilities include the preparation of regulation and the design and evaluation of physical protection systems. This is the second of two volumes; the first volume is SAND-79-1090

  5. Asbestos-Containing Materials in Schools; Final Rule and Notice. Part III: Environmental Protection Agency. 40 CFR Part 763.

    Science.gov (United States)

    Federal Register, 1987

    1987-01-01

    The Environmental Protection Agency (EPA) has issued a final rule under the Toxic Substance Control Act (TSCA) to require all local education agencies (LEAs) to identify asbestos-containing materials in their school buildings and take appropriate action to control release of asbestos fibers. The LEAs are required to describe their activities in…

  6. Decree of the Czechoslovak Atomic Energy Commission concerning the security protection of nuclear installations and nuclear materials

    International Nuclear Information System (INIS)

    1989-01-01

    In compliance with the Czechoslovak State Surveillance over Nuclear Safety of Nuclear Installations Act No. 28/1984, the Decree specifies requirements for assuring security protection of nuclear installations (and their parts) and of nuclear materials with the aim to prevent their abuse for jeopardizing the environment and the health and lives of people. (P.A.)

  7. Application of methods of mathematical modeling for determining of radiation-protective characteristics of polystyrene-metal composite materials

    International Nuclear Information System (INIS)

    Klepikov, V.F.; Prokhorenko, E.M.; Lytvynenko, V.V.; Zakharchenko, A.A.; Nazhmuradov, M.A.

    2016-01-01

    Radiation safety features of polystyrene steel composite materials were found by means of mathematical modeling techniques. We determined the attenuation of the gamma quantum flux passing through a solid protective layer compared with those attenuation for the bulk protective layer. Change of fractional attenuation of the dose absorbed by 10 and 50 mm thick composites is calculated. Dependence between protective properties of composite and its blend composition was studied. Modifications of technical process of composite materials production were performed. Rotation speed of agitator system was found. It was defined that heating time of polystyrene steel mix is longer than heating time of polystyrene tungstic one. Degree of mix heating and integrity of thermic field on its surface was controlled with the help of IR radiometry methods.

  8. Computerized Classification Testing with the Rasch Model

    Science.gov (United States)

    Eggen, Theo J. H. M.

    2011-01-01

    If classification in a limited number of categories is the purpose of testing, computerized adaptive tests (CATs) with algorithms based on sequential statistical testing perform better than estimation-based CATs (e.g., Eggen & Straetmans, 2000). In these computerized classification tests (CCTs), the Sequential Probability Ratio Test (SPRT) (Wald,…

  9. Protective Behaviour of Citizens to Transport Accidents Involving Hazardous Materials: A Discrete Choice Experiment Applied to Populated Areas nearby Waterways.

    Directory of Open Access Journals (Sweden)

    Esther W de Bekker-Grob

    Full Text Available To improve the information for and preparation of citizens at risk to hazardous material transport accidents, a first important step is to determine how different characteristics of hazardous material transport accidents will influence citizens' protective behaviour. However, quantitative studies investigating citizens' protective behaviour in case of hazardous material transport accidents are scarce.A discrete choice experiment was conducted among subjects (19-64 years living in the direct vicinity of a large waterway. Scenarios were described by three transport accident characteristics: odour perception, smoke/vapour perception, and the proportion of people in the environment that were leaving at their own discretion. Subjects were asked to consider each scenario as realistic and to choose the alternative that was most appealing to them: staying, seeking shelter, or escaping. A panel error component model was used to quantify how different transport accident characteristics influenced subjects' protective behaviour.The response was 44% (881/1,994. The predicted probability that a subject would stay ranged from 1% in case of a severe looking accident till 62% in case of a mild looking accident. All three transport accident characteristics proved to influence protective behaviour. Particularly a perception of strong ammonia or mercaptan odours and visible smoke/vapour close to citizens had the strongest positive influence on escaping. In general, 'escaping' was more preferred than 'seeking shelter', although stated preference heterogeneity among subjects for these protective behaviour options was substantial. Males were less willing to seek shelter than females, whereas elderly people were more willing to escape than younger people.Various characteristics of transport accident involving hazardous materials influence subjects' protective behaviour. The preference heterogeneity shows that information needs to be targeted differently depending on

  10. Protective

    Directory of Open Access Journals (Sweden)

    Wessam M. Abdel-Wahab

    2013-10-01

    Full Text Available Many active ingredients extracted from herbal and medicinal plants are extensively studied for their beneficial effects. Antioxidant activity and free radical scavenging properties of thymoquinone (TQ have been reported. The present study evaluated the possible protective effects of TQ against the toxicity and oxidative stress of sodium fluoride (NaF in the liver of rats. Rats were divided into four groups, the first group served as the control group and was administered distilled water whereas the NaF group received NaF orally at a dose of 10 mg/kg for 4 weeks, TQ group was administered TQ orally at a dose of 10 mg/kg for 5 weeks, and the NaF-TQ group was first given TQ for 1 week and was secondly administered 10 mg/kg/day NaF in association with 10 mg/kg TQ for 4 weeks. Rats intoxicated with NaF showed a significant increase in lipid peroxidation whereas the level of reduced glutathione (GSH and the activity of superoxide dismutase (SOD, catalase (CAT, glutathione S-transferase (GST and glutathione peroxidase (GPx were reduced in hepatic tissues. The proper functioning of the liver was also disrupted as indicated by alterations in the measured liver function indices and biochemical parameters. TQ supplementation counteracted the NaF-induced hepatotoxicity probably due to its strong antioxidant activity. In conclusion, the results obtained clearly indicated the role of oxidative stress in the induction of NaF toxicity and suggested hepatoprotective effects of TQ against the toxicity of fluoride compounds.

  11. The Material Protection, Control and Accounting Sustainability Program Implementation at the Electrochemical Plant

    International Nuclear Information System (INIS)

    Sirotenko, Vladimir; Antonov, Eduard; Sirotenko, Alexei; Kukartsev, Alexander; Krivenko, Vladimir; Dabbs, Richard D.; Carroll, Michael F.; Garrett, Albert G.; Patrick, Scott W.; Ku, Esther M.

    2008-01-01

    Joint efforts by the Electrochemical Plant (ECP) in Zelenogorsk, Russia, and the United States Department of Energy National Nuclear Security Administration (US DOE/NNSA) Material Protection, Control and Accounting (MPC and A) Program to upgrade ECP security systems began in 1996. The commissioning of major MPC and A systems at ECP occurred in December 2004. Since that time, the US Project Team (USPT) and ECP personnel have focused jointly on the development and implementation of an enterprise-wide MPC and A Sustainability Program (SP) that address the seven essential MPC and A Program sustainability elements. This paper describes current operational experience at the ECP with the full implementation of the site SP utilizing an earned-value methodology. In support of this site program, ECP has established a Document Control Program (DCP) for sustainability-related documents; developed a robust master Work Breakdown Structure (WBS) that outlines all ECP MPC and A sustainability activities; and chartered an Enterprise-Wide Sustainability Working Group (ESWG) The earned value methodology uses ECP-completed (and USPT-verified) analyses to assess project performance on a quarterly basis. The MPC and A SP, presently operational through a contract between ECP and the Los Alamos National Laboratory (LANL), incorporates the seven essential MPC and A Program sustainability elements and governs all sustainability activities associated with MPC and A systems at ECP. The site SP is designed to ensure over the near term the upgraded MPC and A systems continuous operation at ECP as funding transitions from US-assisted to fully Russian supported and sustained

  12. Buildings 104 and 142 Complex Physical Protection and Material Control and Accounting Upgrades at the Mayak Production Association

    International Nuclear Information System (INIS)

    Aichele, Walter T.; Dwyer, Gregory M.; Larsen, R.; Malone, Tim

    2004-01-01

    The Federal State Unitary Enterprise Mayak Production Association (Mayak) and the U.S. Material Protection, Control and Accounting (MPC and A) United States Project Team (USPT) have worked together for a number of years as part of the U.S. national Nuclear Security Administration's (NNSA) MPC and A program to implement both Physical Protection (PP) and Material Control and Accounting (MC and A) upgrades within the Buildings 104 and 142 Complex, a long-term storage area for uranium and plutonium oxide located within Mayak's RT-1 Spent Fuel Reprocessing Plant. This paper focuses on the successes and areas for improvement in the analysis, planning, construction, implementation, and completion of a complex and labor-intensive project aimed at the refurbishment of two existing, in service, long-term special nuclear material (SNM) storage buildings within a Russian SNM production facility

  13. Physical protection of nuclear materials in transit. Quarterly progress report, April--June 1978

    International Nuclear Information System (INIS)

    Chapman, L.D.

    1978-12-01

    A computer model, SOURCE, has been developed to study the impact of convoy configuration and tactics upon personnel survival and emergency signal generation during an initial armed attack. During this quarter, several improvements were made to the SOURCE code. These improvements include (1) the capability to model an ambush in which the adversaries set up a roadblock, (2) upgraded data on aiming accuracies and human vulnerabilities, and (3) two output formats for examining the locations of the surviving guards. To support the conflict analysis task, several complementary conflict modeling efforts are undergoing parallel development. These methodologies include the SABRES computerized conflict simulation models, the AMBUSH conflict board game, and an alternative methodology being developed by Vector Research, Inc. (VRI). The SABRES I combat model can be used to study the relative value of alternative defender tactics and the relative value of different weapon systems. AMBUSH is a tactical board game which provides a hypothetical conflict between a truck convoy and an adversary group attempting a hijacking. ORINCON Corporation developed network models to be used in determining the cost implications of alternative transportation regulations. SRI International provided weapon characterization data from representative types and calibers of sporting rifles, assault rifles, machine guns, submachine guns, shotguns, and handguns. The alternative methodology for conflict modeling being developed by VRI is the engagement model, CONVOY. SAI is under contract to model the communication system for transporters of SNM

  14. Psychometrics behind Computerized Adaptive Testing.

    Science.gov (United States)

    Chang, Hua-Hua

    2015-03-01

    The paper provides a survey of 18 years' progress that my colleagues, students (both former and current) and I made in a prominent research area in Psychometrics-Computerized Adaptive Testing (CAT). We start with a historical review of the establishment of a large sample foundation for CAT. It is worth noting that the asymptotic results were derived under the framework of Martingale Theory, a very theoretical perspective of Probability Theory, which may seem unrelated to educational and psychological testing. In addition, we address a number of issues that emerged from large scale implementation and show that how theoretical works can be helpful to solve the problems. Finally, we propose that CAT technology can be very useful to support individualized instruction on a mass scale. We show that even paper and pencil based tests can be made adaptive to support classroom teaching.

  15. Chinese computerized nuclear data library

    International Nuclear Information System (INIS)

    Liang Qichang; Cai Dunjiu

    1996-01-01

    The Second Version of Chinese Evaluated Nuclear Data Library (CENDL-2) includes the complete neutron nuclear data sets of 54 important elements and isotopes used for nuclear science and engineering with the incident neutron energy from 10 -5 eV to 20 MeV, the international universal format ENDF/B-6 was adopted. Now, the Chinese Computerized nuclear data library has been developed and put into operation. That is, the users can make on-line use of the main data libraries for evaluated neutron reaction data in the world of EXFOR experimental nuclear data library on the terminal of computer via the perfect computer software system, carry out directly the nuclear engineering calculation or nuclear data evaluation, enjoy the use of the resource of our nuclear data libraries for their development of nuclear energy and nuclear technology applications

  16. Computerized evaluation of flood impact

    International Nuclear Information System (INIS)

    Gagnon, J.; Quach, T.T.; Marche, C.; Lessard, G.

    1998-01-01

    A computerized evaluation process for assessing the economic impacts of a potential dam failure is described. The DOMINO software, which was developed by Hydro-Quebec, takes into account flow data from dam break simulations of floods, the territory involved, plus the economic evaluations of the real estate and infrastructures affected. Some examples of software applications and impact evaluations are presented. The principal elements involved in estimating economic or other types of impacts induced by natural flooding or dam failure, are: (1) flow forecasting, (2) defining the contour of the involved territory, and (3) accounting for the various impacts identified in the affected zone. Owing to its wide range of functions and utilities, DOMINO has proven to be a very useful, user-friendly and portable decision-making tool. 5 refs., 6 tabs

  17. Physical protection of special nuclear material in the commercial fuel cycle. Volume I. Executive summary

    International Nuclear Information System (INIS)

    1976-04-01

    This is the summary of the work and recommendations resulting from Sandia's participation in the Special Safeguards Study, which covered three areas: protection of SNM at fixed facilities, protection of SNM while in transit, and relocation and recovery of lost SNM. The results are published in full in five other volumes. 6 tables, 4 fig

  18. Wood metal. A material of interest for the preparation of individual collimators and radiation protective means

    International Nuclear Information System (INIS)

    Schumann, E.; Keiner, P.; Klose, E.

    1978-01-01

    On the grounds of its physical properties Wood metal is suitable for the preparation of individual collimators, shields and other radiation protective means in clinical radiology. Advantages and disadvantages of these self-made protective means are discussed. Its use for constructing special shielding elements and filters applied in radiotherapy as well as for shielding syringes applied in nuclear medicine is demonstrated. (author)

  19. Patient radiation exposure in computerized tomography

    Energy Technology Data Exchange (ETDEWEB)

    Pavlov, V [Meditsinska Akademiya, Sofia (Bulgaria)

    1980-01-01

    Radiation exposure to patients undergoing axial computerized tomography as a tool of neurological X-ray diagnostics was studied. Doses thereby delivered were compared with those from routine head films at X-ray tube parameters 200 W, 70 kV, and 70 cm target-to-patient distance. Radiation exposures were analyzed with a view to improving shielding and procedural techniques. Comparisons were made using LiF TLD measurements with an Alderson phantom (standard for axial computer tomography). Skin and intracranial space doses were compared using two computers, Siretom I and Siretom 2000, for various positionings: frontal, fronto-lateral, temporal, temporo-occipital, and occipital. In addition, patient body doses with or without shielding and doses to subjects attending sick children or restless adults were examined. Achievable protection was estimated for lead shields of 0.5 mm lead equivalent. It was concluded that radiation doses delivered to neurologic patients undergoing axial computer tomography are smaller than those resulting from conventional X-ray examinations.

  20. The material control and accounting system model development in the Radiochemical plant of Siberian Chemical Combine (SChC)

    International Nuclear Information System (INIS)

    Kozyrev, A.S.; Purygin, V.Ya.; Skuratov, V.A.; Lapotkov, A.A.

    1999-01-01

    The nuclear material (NM) control and accounting computerized system is designed to automatically account NM reception, movement and storage at the Radiochemical Plant. The objective of this system development is to provide a constant surveillance over the process material movement, to improve their accountability and administrative work, to upgrade the plant protection against possible NM thefts, stealing and diversion, to rule out any casual errors of operators, to improve the timeliness and significance (reliability) of information about nuclear materials. The NM control and accounting system at the Radiochemical Plant should be based on the computerized network. It must keep track of all the material movements in each Material Balance Areas: material receipt from other plant; material local movement within the plant; material shipment to other plants; generation of required documents about NM movements and its accounting [ru

  1. Thermal protection for hypervelocity flight in earth's atmosphere by use of radiation backscattering ablating materials

    Science.gov (United States)

    Howe, John T.; Yang, Lily

    1991-01-01

    A heat-shield-material response code predicting the transient performance of a material subject to the combined convective and radiative heating associated with the hypervelocity flight is developed. The code is dynamically interactive to the heating from a transient flow field, including the effects of material ablation on flow field behavior. It accomodates finite time variable material thickness, internal material phase change, wavelength-dependent radiative properties, and temperature-dependent thermal, physical, and radiative properties. The equations of radiative transfer are solved with the material and are coupled to the transfer energy equation containing the radiative flux divergence in addition to the usual energy terms.

  2. Study of materials used for the thermal protection of the intake system for internal combustion engines

    Science.gov (United States)

    Birtok-Băneasă, C.; Raţiu, S.; Puţan, V.; Josan, A.

    2018-01-01

    The present paper focuses on calculation of thermal conductivity for a new materials developed by the authors, using the heat flux plate method. This experimental method consists in placing the sample of the new material in a calorimetric chamber and heating from underside. As the heat flux which passes through the sample material is constant and knowing the values of the temperatures for the both sides of sample, the sample material thermal conductivity is determined. Six types of different materials were tested. Based on the experimental data, the values of the thermal conductivity according to the material and the average temperature were calculated and plotted.

  3. Establishment and utilization of radiological protection programs for the transport of radioactive material; Establecimiento y utilizacion de programas de proteccion radiologica para el transporte de material radiactivo

    Energy Technology Data Exchange (ETDEWEB)

    Lopez V, J.; Capadona, N. [Autoridad Regulatoria Nuclear, Av. Del Libertador 8250 (1429) Buenos Aires, (Argentina)]. e-mail: jlvietri@sede.arn.gov.ar

    2006-07-01

    The present work has by objective to indicate rules for the establishment and the use of the Radiological Protection Programs (PPR) that are of application to the transport of radioactive materials according to that required by the Transport Regulation of the International Atomic Energy Agency (IAEA). The PPR are established and applied in systematic form for remittent, transport and addressees, to consider the measures of radiological protection and its appropriately control during the transport stages of radioactive material. In particular, in the work it is analyzed the PPR applied to the operative stage, in the one that can be considered as one of the more important documents to use since it summarizes the evaluations and the necessary controls of radiological protection. Also it is analyzed the importance that this document gets ready on the base that it converges in the the analyses, evaluations and data that have been kept in mind during the previous stages of design of bundles and production of packings, the types and quantities of involved bundles, as well as of considering the quantities of expeditions and its frequencies, the ways of transport, etc. It is included a brief description of the parts that the PPR conforms on the base of that suggested in the advanced draft of the TS-G-1.5 Guide 'Radiation Protection Programmes for Transport of Radioactive Material', of October, 2005, of the IAEA: objectives. necessity, scope, basic elements of a PPR in function of the occupational dose. assignment of functions and responsibilities for the establishment of a PPR, evaluation and dose optimization, surface contamination, segregation and other protection measures, responses in emergencies. training and administration systems for baled and transport of radioactive material. Next an example of PPR for the transport of bundles of the A Type by lorry with content of radiopharmaceuticals that are the bundles more used worldwide in the expeditions of

  4. Summary report on transportation of nuclear fuel materials in Japan : transportation infrastructure, threats identified in open literature, and physical protection regulations.

    Energy Technology Data Exchange (ETDEWEB)

    Cochran, John Russell; Ouchi, Yuichiro (Japan Atomic Energy Agency, Japan); Furaus, James Phillip; Marincel, Michelle K.

    2008-03-01

    This report summarizes the results of three detailed studies of the physical protection systems for the protection of nuclear materials transport in Japan, with an emphasis on the transportation of mixed oxide fuel materials1. The Japanese infrastructure for transporting nuclear fuel materials is addressed in the first section. The second section of this report presents a summary of baseline data from the open literature on the threats of sabotage and theft during the transport of nuclear fuel materials in Japan. The third section summarizes a review of current International Atomic Energy Agency, Japanese and United States guidelines and regulations concerning the physical protection for the transportation of nuclear fuel materials.

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

    International Nuclear Information System (INIS)

    2005-01-01

    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 6 problem sessions as follow: Environmental protection, earth sciences, protection of cultural objects; Industrial applications; applications in medicine, medical apparatus; measurement methods, simulations, experiment planning; radiation techniques; laboratories, metrology

  6. Reflecting on the ethical administration of computerized medical records

    Science.gov (United States)

    Collmann, Jeff R.

    1995-05-01

    This presentation examines the ethical issues raised by computerized image management and communication systems (IMAC), the ethical principals that should guide development of policies, procedures and practices for IMACS systems, and who should be involved in developing a hospital's approach to these issues. The ready access of computerized records creates special hazards of which hospitals must beware. Hospitals must maintain confidentiality of patient's records while making records available to authorized users as efficiently as possible. The general conditions of contemporary health care undermine protecting the confidentiality of patient record. Patients may not provide health care institutions with information about themselves under conditions of informed consent. The field of information science must design sophisticated systems of computer security that stratify access, create audit trails on data changes and system use, safeguard patient data from corruption, and protect the databases from outside invasion. Radiology professionals must both work with information science experts in their own hospitals to create institutional safeguards and include the adequacy of security measures as a criterion for evaluating PACS systems. New policies and procedures on maintaining computerized patient records must be developed that obligate all members of the health care staff, not just care givers. Patients must be informed about the existence of computerized medical records, the rules and practices that govern their dissemination and given the opportunity to give or withhold consent for their use. Departmental and hospital policies on confidentiality should be reviewed to determine if revisions are necessary to manage computer-based records. Well developed discussions of the ethical principles and administrative policies on confidentiality and informed consent and of the risks posed by computer-based patient records systems should be included in initial and continuing

  7. A preliminary study on PVDC modified composite materials of protective for tritium

    International Nuclear Information System (INIS)

    Wan Xiaoli; Dan Guiping; Li Ye; Wen Wei; Zhang Dong

    2012-01-01

    Through the experimental device, the HTO permeation performances of two kinds of PVDC modified composite materials were studied. The characteristic curves of the two composite materials were ascertained, and various other packing materials with anti-tritium permeation performance were compared. (authors)

  8. Microcomputer Network for Computerized Adaptive Testing (CAT)

    Science.gov (United States)

    1984-03-01

    PRDC TR 84-33 \\Q.�d-33- \\ MICROCOMPUTER NETWOJlt FOR COMPUTERIZED ADAPTIVE TESTING ( CAT ) Baldwin Quan Thomas A . Park Gary Sandahl John H...ACCEIIION NO NPRDC TR 84-33 4. TITLE (-d Sul>tlllo) MICROCOMP UTER NETWORK FOR COMPUTERIZED ADA PTIVE TESTING ( CAT ) 1. Q B. uan T. A . Park...adaptive testing ( CAT ) Bayesian sequential testing 20. ABSTitACT (Continuo on ro•••• aide II noco .. _, _., ld-tlly ,.,. t.loclt _._.) DO Computerized

  9. Development of High-Fidelity Material Response Modeling for Resin-Infused Woven Thermal Protection Systems

    Data.gov (United States)

    National Aeronautics and Space Administration — For future space exploration missions, it is essential for the thermal protection system (TPS) found on hypersonic vehicles or atmospheric entry probes to be...

  10. 2. National scientific conference on process engineering in environment protection. Conference materials

    International Nuclear Information System (INIS)

    1994-01-01

    The national conference on 'Process engineering in environment protection' Jachranka 1994 has been divided into three sessions. Section 1 has been devoted to flue gas purification and collects 13 papers. Section 2 on liquid purification gathered 8 presentation. Section 3 - the poster session with 12 posters on related topics. During the conference 2 lectures and 3 posters have been devoted to the application of nuclear techniques to the solution different problems connected with environment protection

  11. CRRIS: a computerized radiological risk-investigation system

    International Nuclear Information System (INIS)

    Baes, C.F. III; Miller, C.W.

    1981-01-01

    The US Environmental Protection Agency (EPA) is responsible for regulating radioactive airborne effluents in the US. A comprehensive, integrated Computerized Radiological Risk Investigation System (CRRIS) is being developed to support EPA's radiation standards development. This modular system consists primarily of five computer codes and their supporting data bases for estimating environmental transport and radiation doses and risks. Health effects are estimated on the basis of a life-table methodology developed by EPA. CRRIS is designed to provide EPA with a reasonable and flexible way of assessing the risk to man associated with radionuclide releases to the atmosphere

  12. On-line course as tools for radiation protection training in patients. A practical case in computerized tomography; El Aula Virtual como herramienta para la formacion en PR del paciente; caso practico en tomografia computarizada

    Energy Technology Data Exchange (ETDEWEB)

    Medina Campos, J.; Fernandez Tallon, J.; Busca Suau, J.; Baro Casanovas, J.

    2006-07-01

    The rise in ionizing radiation applications within the field of diagnostics, with the corresponding increase in both number and doses received by patients, requires adequate resources for education and training in radiological protection. In is quite difficult to assemble professionals at a specific place to carry out training. However, the use of Information and Communication Technologies (IT) makes it possible to carry out training. However, the use of Information and Communication Technologies (IT) makes it possible to carry out training through Internet in an effective, easy and amusing way (e-learning). An on-line course of patient radiological protection and quality control in computer tomography has been developed aimed at professionals that use these diagnostic techniques. The course has been run twice in the period 2005-2006. The course is found on an Internet-accessible Virtual Campus, which allows access to multimedia contents, communication between students and instructors and follow-up of students performance. Final evaluation is done on-line and successfully passing the course counts for 8.9 credits in the Continuous Education Programme of Spanish Health Systems. (Author)

  13. Investigation of novel composite material based on extra-heavy concrete and basalt fiber for gamma radiation protection properties

    International Nuclear Information System (INIS)

    Romanenko, Yi.M.; Nosovs'kij, A.V.; Gulyik, V.Yi.; Golyuk, M.Yi.

    2018-01-01

    The paper presents a new composite material for radiation protection based on extra-heavy concrete reinforced by basalt fiber. Basalt fiber is a new material for concrete reinforcement, which provides improved mechanical characteristics of concrete, reduces the level of microcracks and increases the durability of concrete. Within the scope of present work, the gamma-ray radiation protection properties of concrete reinforced with basalt fiber was modeled. Two types of extra-heavy concrete were used for this paper. The main gamma-ray attenuation coefficients such as mean atomic number, mean atomic mass, mean electron density, effective atomic number, effective electron density, Murty effective atomic number were analyzed with help of WinXCom software. It has been shown that the addition of basalt fiber to concrete does not impair its gamma-ray radiation shielding properties. With increasing the basalt fiber dosage in concrete, the radiation properties against gamma radiation are improved.

  14. Achievements, current status and prospects for Russian-American cooperation in nuclear material physical protection, control and accounting - 1998

    International Nuclear Information System (INIS)

    Nikiforov, N.V.

    1999-01-01

    The process of upgrading the material physical protection, control and accounting systems is an ongoing and long-term process that consists of modernization measuring equipment and methodologies, improving, data exchange and processing technologies, and improving administrative procedures. The positive results that was already achieved form a foundation upon which this collaboration may extend into other new and important areas, such as - the second and third lines of defence, which are directed toward countering illegal trafficking not only in nuclear materials, but in other hazardous substances that constitute a threat to the nuclear sites and national security of the countries [ru

  15. The project of the Spanish Nuclear Industry Forum to develop an interactive educational material on Radiological Protection

    International Nuclear Information System (INIS)

    Real, A.; Cruz, T. de la; Girona, L.; Montesinos, L.; Sanchez, P.

    2012-01-01

    The Training Department of the Spanish Nuclear Industry Forum has undertaken a new project to develop an interactive educational material on Radiological Protection. The objective was to develop an attractive, comprehensive and interactive material, to facilitate students and teachers of Elementary, Middle and High schools, to become familiar with ionising radiations. The novelly of the project, is that based on the European framework of key competencies for file long learning, which are defined as a set of knowledge, skills and altitudes that all individuals need for personal fulfilment and employment. The material presented in this paper, is based in an integrated structure of tasks, activities and exercises, which will facilitate the acquisition of as may key competencies as possible. Besides, the material also includes reference texts, links to pertinent web sites and videos. Students, through the development of a specific task (and related activities and exercises), will learn the differences between ionizing and non ionising radiation, the origin, characteristics and types of types of ionising radiation, how to detect and measure them, the potential detrimental health effects, the principles of radiation protection and the beneficial applications can have for man. The material is freely available in www.rinconeducativo.org. (Author) 4 refs.

  16. Exploring new W–B coating materials for the aqueous corrosion–wear protection of austenitic stainless steel

    Energy Technology Data Exchange (ETDEWEB)

    Mallia, B., E-mail: bertram.mallia@um.edu.mt [Department of Metallurgy and Materials Engineering, University of Malta, Msida MSD 2080 (Malta); Dearnley, P.A. [nCATS National Centre for Advanced Tribology Southampton, Engineering Sciences, University of Southampton, Southampton SO17 1BJ (United Kingdom)

    2013-12-31

    The material loss of metallic surfaces through corrosion–wear is a serious concern in many application sectors, ranging from bio-medical implants to marine, oil and gas field components to transport vehicle and nuclear reactor devices. In principle, self-passivating alloys, like stainless steels, can be protected from surface degradation caused by corrosion–wear through the application of protective thin, hard surface coatings. In this work the suitability of using W matrix coating materials supersaturated with varying levels of boron were applied to austenitic stainless steel substrates (Ortron 90) and assessed for this purpose. These materials were compared to a highly corrosion–wear resistant “datum” surface engineered material (CrN coated Ti–6Al–4V) in sliding contact tests against a chemically inert aluminium oxide ball, whilst immersed in 0.9% NaCl solution at 37 °C. The work demonstrated that all the coated materials to be very much more resistant to material loss through corrosion–wear (by nearly an order of magnitude) compared to uncoated stainless steel, and two coatings, W–13%B and W–23%B coated Ortron 90 were similarly resistant as CrN coated Ti–6Al–4V. Three fundamental types of corrosion–wear were discovered that represented differing levels of passive film durability. The total material loss rate (TMLR) during corrosion–wear testing showed linear proportionality with the change in open circuit potential δ{sub OCP} which obeyed the governing equation: TMLR = m δ{sub OCP} + C. - Highlights: • Magnetron sputtered W–(B) coatings displayed a crystalline to amorphous transition. • W–(B) coatings displayed excellent corrosion–wear resistance under OCP conditions. • Three kinds of corrosion–wear behaviour were determined in this study. • A linear correlation between total material loss and change in OCP was discovered. • Static CV tests were not useful for predicting dynamic corrosion–wear behaviour.

  17. Influence of supplementary cementitious materials on the properties of concrete for secondary protection barrier in radioactive waste repositories

    Czech Academy of Sciences Publication Activity Database

    Koťátková, J.; Čáchová, M.; Bezdička, Petr; Vejmelková, E.; Konvalinka, P.; Zemanová, L.; Černý, R.

    2018-01-01

    Roč. 760, SI (2018), s. 96-101 ISSN 1662-9795. [Special Concrete and Composites 2017 /14./. Lísek, 10.10.2017-11.10.2017] R&D Projects: GA ČR(CZ) GA17-11635S Institutional support: RVO:61388980 Keywords : Basic physical properties * Mechanical properties * Repository * Secondary protection barrier * Supplementary cementitious materials * Thermal properties Subject RIV: CA - Inorganic Chemistry OBOR OECD: Inorganic and nuclear chemistry

  18. Department of Energy Nuclear Material Protection, Control, and Accounting Program at the Mangyshlak Atomic Energy Complex, Aktau, Republic of Kazakhstan

    International Nuclear Information System (INIS)

    Case, R.; Berry, R.B.; Eras, A.

    1998-01-01

    As part of the Cooperative Threat Reduction Nuclear Material Protection, Control, and Accounting (MPC and A) Program, the US Department of Energy and Mangyshlak Atomic Energy Complex (MAEC), Aktau, Republic of Kazakstan have cooperated to enhance existing MAEC MPC and A features at the BN-350 liquid-metal fast-breeder reactor. This paper describes the methodology of the enhancement activities and provides representative examples of the MPC and A augmentation implemented at the MAEC

  19. The OENORM S 5200 'Radioactivity in building materials' as a tool for radiation protection of the general population

    International Nuclear Information System (INIS)

    Kunsch, B.

    1989-04-01

    This report comprises two papers, one which is announced in the title, i.e. B. Kunsch, F. Steger, E. Tschirf: The OENORM S 5200 'Radioactivity in building materials' as a tool for radiation protection of the general population; and in addition a paper by F. Steger, H. Stadtmann, P. Kindl, L. Breitenhuber: Radon in dwellings: investigations and measurements. The two papers are treated separately. (qui)

  20. The Physical Protection of Nuclear Material and Nuclear Facilities; Proteccion Fisica De Los Materiales Y Las Instalaciones Nucleares

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-06-15

    Physical protection against the theft or unauthorized diversion of nuclear materials and against the sabotage of nuclear facilities by individuals or groups has long been a matter of national and international concern. Although responsibility for establishing and operating a comprehensive physical protection system for nuclear materials and facilities within a State rests entirely with the Government of that State, it is not a matter of indifference to other States whether and to what extent that responsibility is fulfilled. Physical protection has therefore become a matter of international concern and co-operation. The need for international co-operation becomes evident in situations where the effectiveness of physical protection in one State depends on the taking by other States also of adequate measures to deter or defeat hostile actions against nuclear facilities and nuclear materials, particularly when such materials are transported across national frontiers [Spanish] La proteccion fisica contra el robo o la desviacion no autorizada de materiales nucleares y contra el sabotaje de las instalaciones nucleares por parte de individuos o grupos es motivo de preocupacion nacional e internacional desde hace mucho tiempo. Aunque la obligacion de crear y hacer funcionar un sistema completo de proteccion fisica de las instalaciones y materiales nucleares en el territorio de un Estado determinado incumbe exclusivamente al Gobierno de dicho Estado, el que esa obligacion se cumpla o no, y si se cumple, en que medida o hasta que punto, son cosas que no dejan indiferentes a los demas Estados. Por ello, la proteccion fisica se ha convertido en motivo de interes y cooperacion internacional. La necesidad de la cooperacion internacional se hace evidente en los casos en que la eficacia de la proteccion fisica en el territorio de un Estado depende de que otros Estados tomen tambien medidas apropiadas para evitar o hacer fracasar los actos hostiles dirigidos contra instalaciones y

  1. 20th International Training Course (ITC-20) on the physical protection of nuclear facilities and materials evaluation report.

    Energy Technology Data Exchange (ETDEWEB)

    Ramirez, Amanda Ann

    2008-09-01

    The goal of this evaluation report is to provide the information necessary to improve the effectiveness of the ITC provided to the International Atomic Energy Agency Member States. This report examines ITC-20 training content, delivery methods, scheduling, and logistics. Ultimately, this report evaluates whether the course provides the knowledge and skills necessary to meet the participants needs in the protection of nuclear materials and facilities.

  2. Research of Acoustic Properties of Materials with the Purpose of Their Use at Design of Special Noise Protective Clothes for Oil and Gas Industry

    Science.gov (United States)

    Drofa, E. A.; Lipilina, E. Yu

    2018-01-01

    The article is devoted to the substantiation of the choice of a rational package of materials, which has the greatest noise-protective properties when designing special clothes with reference to the oil and gas industry. Studies were conducted to assess the factors that have the most significant effect on the noise-protective properties of clothing. Conclusions are made about the possibility of using the developed technique for studying the noise-protective properties of materials in selecting rational packages of materials for the production of special clothes with high noise-protective properties.

  3. Naturally occurring radioactive materials in construction integrating radiation protection in Reuse

    CERN Document Server

    Schroeyers, Wouter

    2017-01-01

    Naturally Occurring Radioactive Materials in Construction (COST Action NORM4Building) discusses the depletion of energy resources and raw materials and its huge impact not only on the building market, but also in the development of new synthetic building materials, whereby the reuse of various (waste) residue streams becomes a necessity. It is based on the outcome of COST Action TU 1301, where scientists, regulators, and representatives from industry have come together to present new findings, sharing knowledge, experiences, and technologies to stimulate research on the reuse of residues containing enhanced concentrates of natural radionuclides (NORM) in tailor-made building materials. Chapters address legislative issues, measurement, and assessment of building materials, physical and chemical aspects, from raw materials, to residues with enhanced concentrations of natural radionuclides (NORM), processes, building products containing NORM, and end-of-life and reuse requirements. Presents a holistic app...

  4. A computerized legal information management system | Ohiagu ...

    African Journals Online (AJOL)

    A computerized legal information management system. ... process through the filling system using the survey research methodology. ... A framework for the design and implementation of a legal information management system was presented.

  5. Computerizing marine biota: a rational approach

    Digital Repository Service at National Institute of Oceanography (India)

    Chavan, V.S.; Chandramohan, D.; Parulekar, A.H.

    Data on marine biota while being extensive are also patchy and scattered; thus making retrieval and dissemination of information time consuming. This emphasise the need for computerizing information on marine biota with the objective to collate...

  6. Human Reliability Analysis For Computerized Procedures

    International Nuclear Information System (INIS)

    Boring, Ronald L.; Gertman, David I.; Le Blanc, Katya

    2011-01-01

    This paper provides a characterization of human reliability analysis (HRA) issues for computerized procedures in nuclear power plant control rooms. It is beyond the scope of this paper to propose a new HRA approach or to recommend specific methods or refinements to those methods. Rather, this paper provides a review of HRA as applied to traditional paper-based procedures, followed by a discussion of what specific factors should additionally be considered in HRAs for computerized procedures. Performance shaping factors and failure modes unique to computerized procedures are highlighted. Since there is no definitive guide to HRA for paper-based procedures, this paper also serves to clarify the existing guidance on paper-based procedures before delving into the unique aspects of computerized procedures.

  7. Computerized Interpretation of Dynamic Breast MRI

    National Research Council Canada - National Science Library

    Chen, Weijie; Giger, Maryellen Lissak

    2005-01-01

    ... and prognosis of breast cancer. The research involves investigation of automatic methods for image artifacts correction, tumor segmentation, and extraction of computerized features that help distinguish between benign and malignant lesions...

  8. Act No. 80-572 on protection and control of nuclear materials

    International Nuclear Information System (INIS)

    1980-01-01

    This Act lays down that the import, export, possession, transfer, use and transport of nuclear materials defined by the Act are subject to licensing and control under conditions to be determined by Decree. The purpose of this control is to avoid loss, theft or diversion of such materials. Any person who obtains fraudulently nuclear material referred to in the Act or who carries out activities involving such material without the required licence shall be subject to severe penalties. Finally, it is provided that the Government shall report to Parliament each year on operation of the provisions of this Act. (NEA) [fr

  9. Electrostatic discharge attenuation test for the characterization of ESD protective materials

    International Nuclear Information System (INIS)

    Paasi, Jaakko; Viheriaekoski, Toni; Sutela, Lassi; Tamminen, Pasi K

    2008-01-01

    New experimental method has been developed to evaluate materials, tools, equipment and packaging used in the electronics production environment under Charged Device Model (CDM) type of electrostatic discharge (ESD) transients. The method is intended to characterize the ability of the material or object to attenuate ESD energy and peak discharge current when a charged device is discharged into the material under test. The test is supplementary for the standard quasi-static measurements of ESD control programs in the cases where standard measurements do not give sufficient information due to voltage non-linearity, complexity or shape of the material or object under test.

  10. Decree-Law No. 375/90 of 10 November 1990 designating the competent national authority for the physical protection of nuclear material

    International Nuclear Information System (INIS)

    1990-01-01

    This Decree-Law designates, in accordance with the Convention on the Physical Protection of Nuclear Material, the Protection and Nuclear Safety Bureau (GPSN) of the Ministry of the Environment and Natural Resources as the national competent authority in relation to physical protection matters. Accordingly, the import, manufacture, possession, purchase, sale or transfer of nuclear material, as well as its transport, are subject to prior authorisation by the GPSN [fr

  11. Computerized provider order entry systems.

    Science.gov (United States)

    2001-01-01

    Computerized provider order entry (CPOE) systems are designed to replace a hospital's paper-based ordering system. They allow users to electronically write the full range of orders, maintain an online medication administration record, and review changes made to an order by successive personnel. They also offer safety alerts that are triggered when an unsafe order (such as for a duplicate drug therapy) is entered, as well as clinical decision support to guide caregivers to less expensive alternatives or to choices that better fit established hospital protocols. CPOE systems can, when correctly configured, markedly increase efficiency and improve patient safety and patient care. However, facilities need to recognize that currently available CPOE systems require a tremendous amount of time and effort to be spent in customization before their safety and clinical support features can be effectively implemented. What's more, even after they've been customized, the systems may still allow certain unsafe orders to be entered. Thus, CPOE systems are not currently a quick or easy remedy for medical errors. ECRI's Evaluation of CPOE systems--conducted in collaboration with the Institute for Safe Medication Practices (ISMP)--discusses these and other related issues. It also examines and compares CPOE systems from three suppliers: Eclipsys Corp., IDX Systems Corp., and Siemens Medical Solutions Health Services Corp. Our testing focuses primarily on the systems' interfacing capabilities, patient safeguards, and ease of use.

  12. Computerized automated remote inspection system

    International Nuclear Information System (INIS)

    The automated inspection system utilizes a computer to control the location of the ultrasonic transducer, the actual inspection process, the display of the data, and the storage of the data on IBM magnetic tape. This automated inspection equipment provides two major advantages. First, it provides a cost savings, because of the reduced inspection time, made possible by the automation of the data acquisition, processing, and storage equipment. This reduced inspection time is also made possible by a computerized data evaluation aid which speeds data interpretation. In addition, the computer control of the transducer location drive allows the exact duplication of a previously located position or flaw. The second major advantage is that the use of automated inspection equipment also allows a higher-quality inspection, because of the automated data acquisition, processing, and storage. This storage of data, in accurate digital form on IBM magnetic tape, for example, facilitates retrieval for comparison with previous inspection data. The equipment provides a multiplicity of scan data which will provide statistical information on any questionable volume or flaw. An automatic alarm for location of all reportable flaws reduces the probability of operator error. This system has the ability to present data on a cathode ray tube as numerical information, a three-dimensional picture, or ''hard-copy'' sheet. One important advantage of this system is the ability to store large amounts of data in compact magnetic tape reels

  13. International measures needed to protect metal recycling facilities from radioactive materials

    International Nuclear Information System (INIS)

    Mattia, M.; Wiener, R.

    1999-01-01

    In almost every major city and region of every country, there is a recycling facility that is designed to process or consume scrap metal. These same countries will probably have widespread applications of radioactive materials and radiation generating equipment. This material and equipment will have metal as a primary component of its housing or instrumentation. It is this metal that will cause these sources of radioactivity, when lost, stolen or mishandled, to be taken to a metal recycling facility to be sold for the value of the metal. This is the problem that has faced scrap recycling facilities for many years. The recycling industry has spent millions of dollars for installation of radiation monitors and training in identification of radioactive material. It has expended millions more for the disposal of radioactive material that has mistakenly entered these facilities. Action must be taken to prevent this material from entering the conventional recycling process. There are more than 2,300 known incidents of radioactive material found in recycled metal scrap. Worldwide, more than 50 smeltings of radioactive sources have been confirmed. Seven fatal accidents involving uncontrolled radioactive material have also been documented. Hazardous exposures to radioactive material have plagued not just the workers at metal recycling facilities. The families of these workers, including their children, have been exposed to potentially harmful levels of radioactivity. The threat from this material does not stop there. Radioactive material that is not caught at recycling facilities can be melted and the radioactivity has been found in construction materials used to build homes, as well as shovels, fencing material, and furniture offered for sale to the general public. The time has come for the international community to address the issue of the uncontrolled sources of radioactive material. The following are the key points that must be addressed. (i) Identification of sources

  14. Surface Catalytic Efficiency of Advanced Carbon Carbon Candidate Thermal Protection Materials for SSTO Vehicles

    Science.gov (United States)

    Stewart, David A.

    1996-01-01

    The catalytic efficiency (atom recombination coefficients) for advanced ceramic thermal protection systems was calculated using arc-jet data. Coefficients for both oxygen and nitrogen atom recombination on the surfaces of these systems were obtained to temperatures of 1650 K. Optical and chemical stability of the candidate systems to the high energy hypersonic flow was also demonstrated during these tests.

  15. Chapter No.5. Nuclear materials and physical protection of nuclear installations

    International Nuclear Information System (INIS)

    2002-01-01

    The State System of Accounting for and Control of Nuclear Material (SSAC) is based on requirements resulting from the Safeguards Agreement between the Government of the Slovak Republic and the IAEA. UJD performs this activity according to the 'Atomic Act' and relevant decree. The purpose of the SSAC is also to prevent unauthorised use of nuclear materials, to detect loses of nuclear materials and provide information that could lead to the recovery of missing material. The main part of nuclear materials under jurisdiction of the Slovak Republic is located at NPP Jaslovske Bohunice, NPP Mochovce and at interim storage in Jaslovske Bohunice. Even though that there are located more then 99% of nuclear materials in these nuclear facilities, there are not any significant problems with their accountancy and control due to very simply identification of accountancy units - fuel assemblies, and due to stability of legal subjects responsible for operation and for keeping of information continuity, which is necessary for fulfilling requirements of the Agreement. The nuclear material located outside nuclear facilities is a special category. There are 81 such subjects of different types and orientations on the territory of the Slovak Republic. These subjects use mainly depleted uranium as a shielding and small quantity of natural uranium, low enrichment uranium and thorium for experimental purposes and education. Frequent changes of these subjects, their transformations into the other subjects, extinction and very high fluctuation of employees causes loss of information about nuclear materials and creates problems with fulfilling requirements resulting from the Agreement. In 2001, the UJD carried out 51 inspections of nuclear materials, of which 31 inspections were performed at nuclear installations in co-operation with the IAEA inspectors. No discrepancies concerning the management of nuclear materials were found out during inspections and safeguards goals in year 2001 were

  16. Flexible barrier materials for protection against electromagnetic fields and their characterization

    Science.gov (United States)

    Jaroszewski, Maciej

    2015-10-01

    Composite materials for electromagnetic shielding can be manufactured as textiles using conductive yarns and textiles with conductivity obtained by various finishing processes on textile surfaces. The EM shielding effectiveness of fabrics are improved by lowering its conductivity using different methods and materials. An alternative is the usage of new light shielding materials in the form of metallized nonwoven fabrics or textiles. Their advantages are: a general availability on the market, a low price, good mechanical properties (strength, elasticity) and resistance to the environmental conditions. The composite anisotropic materials with a sandwich structure constituting of materials with different spatial orientations of fibers allow one to achieve relatively high and constant values of the shielding effectiveness which, together with the materials' mechanical properties, leads to a wide range of applicability in various disciplines of modern technology. This article is devoted to innovative flexible materials shielding electromagnetic field. The results of the PEM shielding effectiveness obtained for the polypropylene (PP) nonwoven fabrics metallized by pulsed magnetron sputtering are presented.

  17. Safety protection suggestion of naturally occurring radioactive materials in the oil and gas industry

    International Nuclear Information System (INIS)

    Zhou Xiaojian; Zhou Qifu; Wang Xiaotao; Xu Zhongyang; Song Peifeng

    2014-01-01

    It's not enough concern about the naturally occurring radioactive materials (NORM) of oil and gas industry in China. NORM with radium and radon mainly exist in the scale, sludge and production water, and they tend to deposit on the pipe wall, wellhead equipment and so on. These materials are a threat to the health of workers, so it is very important to have the safe disposal of them. This paper introduces the radioactive hazards and puts for-ward the safe disposal measures so as to provide the reference for the safe disposal of radioactive materials. Some management and technical advices are presented too. (authors)

  18. Trial operation of material protection, control, and accountability systems at two active nuclear material handling sites within the All-Russian Institute of Experimental Physics (VNIIEF)

    International Nuclear Information System (INIS)

    Skripka, G.; Vatulin, V.; Yuferev, V.

    1997-01-01

    This paper discusses Russian Federal Nuclear Center (RFNC)-VNIIEF activities in the area of nuclear material protection, control, and accounting (MPC and A) procedures enhancement. The goal of such activities is the development of an automated systems for MPC and A at two of the active VNIIEF research sites: a research (reactor) site and a nuclear material production facility. The activities for MPC and A system enhancement at both sites are performed in the framework of a VNIIEF-Los Alamos National Laboratory contract with participation from Sandia National Laboratories, Lawrence Livermore National Laboratory, Brookhaven National Laboratory, Oak Ridge National Laboratory, Pacific Northwest National Laboratory, and PANTEX Plant in accordance with Russian programs supported by MinAtom. The American specialists took part in searching for possible improvement of technical solutions, ordering equipment, and delivering and testing the equipment that was provided by the Americans

  19. Status of U.S. programs for material protection, control ampersand accounting assistance to Ukraine and Kazakstan

    International Nuclear Information System (INIS)

    Roche, C.T.; Zinneman, T.E.; Rudolph, R.R.

    1995-01-01

    The United States is one of several donor states providing technical assistance to the Newly Independent States (NIS) of the Former Soviet Union (FSU) for improving their systems for control of nuclear materials. Ukraine and Kazakstan have significant nuclear energy programs. Both countries have committed to nonproliferation of nuclear weapons. They have signed the NPT and have safeguards agreements with the U.S. concerning development of state systems of control, accounting and physical protection of nuclear materials. As directed by the DOE - International Safeguards Division (now the DOE - Russia/NIS Nuclear Materials Security Task Force), technical specialists from several national laboratories, including Argonne, Los Alamos, Oak Ridge, Pacific Northwest and Sandia, as well as representatives of other U.S. Government organizations, such as the NRC, DOD/DNA and the New Brunswick Laboratory, are interacting with government regulatory and facility personnel of Ukraine and Kazakstan. Argonne has program coordination responsibilities for both countries. In support of agreements between the U.S. and Ukraine and the U.S. and Kazakstan, the DOE is responsible for providing technical assistance and training to aid in the evaluation, design, development, and implementation of nuclear material safeguards. This assistance includes: (1) information systems for tracking and reporting the location of nuclear materials, (2) application of nuclear measurement techniques for verifying inventories, (3) material control and accounting (MC ampersand A) systems, and (4) physical protection (PP) systems. Site survey teams, including both MC ampersand A and PP experts from several national labs, have visited Ukraine and Kazakstan. This paper summarizes activities to date and future plans

  20. Glass-ceramic coating material for the CO2 laser based sintering of thin films as caries and erosion protection.

    Science.gov (United States)

    Bilandžić, Marin Dean; Wollgarten, Susanne; Stollenwerk, Jochen; Poprawe, Reinhart; Esteves-Oliveira, Marcella; Fischer, Horst

    2017-09-01

    The established method of fissure-sealing using polymeric coating materials exhibits limitations on the long-term. Here, we present a novel technique with the potential to protect susceptible teeth against caries and erosion. We hypothesized that a tailored glass-ceramic material could be sprayed onto enamel-like substrates to create superior adhesion properties after sintering by a CO 2 laser beam. A powdered dental glass-ceramic material from the system SiO 2 -Na 2 O-K 2 O-CaO-Al 2 O 3 -MgO was adjusted with individual properties suitable for a spray coating process. The material was characterized using X-ray fluorescence analysis (XRF), heating microscopy, dilatometry, scanning electron microscopy (SEM), grain size analysis, biaxial flexural strength measurements, fourier transform infrared spectroscopy (FTIR), and gas pycnometry. Three different groups of samples (each n=10) where prepared: Group A, powder pressed glass-ceramic coating material; Group B, sintered hydroxyapatite specimens; and Group C, enamel specimens (prepared from bovine teeth). Group B and C where spray coated with glass-ceramic powder. All specimens were heat treated using a CO 2 laser beam process. Cross-sections of the laser-sintered specimens were analyzed using laser scanning microscopy (LSM), energy dispersive X-ray analysis (EDX), and SEM. The developed glass-ceramic material (grain size d50=13.1mm, coefficient of thermal expansion (CTE)=13.310 -6 /K) could be spray coated on all tested substrates (mean thickness=160μm). FTIR analysis confirmed an absorption of the laser energy up to 95%. The powdered glass-ceramic material was successfully densely sintered in all sample groups. The coating interface investigation by SEM and EDX proved atomic diffusion and adhesion of the glass-ceramic material to hydroxyapatite and to dental enamel. A glass-ceramic material with suitable absorption properties was successfully sprayed and laser-sintered in thin films on hydroxyapatite as well as on

  1. Next Generation , Lightweight, Durable Boot Materials to Provide Active & Passive Thermal Protection, Phase I

    Data.gov (United States)

    National Aeronautics and Space Administration — The objective of this NASA Phase I SBIR program is to leverage lightweight, durable materials developed by NanoSonic for use within extra vehicular activity (EVA)...

  2. EPR and Optical Characterization of Photorefractive Materials Used in Agile Laser Protection

    National Research Council Canada - National Science Library

    Halliburton, Larry

    2003-01-01

    .... The specific materials investigated were LiNbO3 and LiTaO3. The experimental techniques used to characterize these crystals were optical absorption, thermoluminescence, and electron paramagnetic resonance (EPR...

  3. Protocol to treat people with wounds contaminated with radioactive material standpoint of radiological protection

    International Nuclear Information System (INIS)

    Lopes, Amanda Gomes; Tauhata, Luiz; Reis, Arlene Alves; Cruz, Paulo Alberto Lima da; Bertelli Neto, Luiz

    2015-01-01

    People who work in research laboratories, radioisotope production center or nuclear artifacts, nuclear medicine center, or allocated in the vicinity of nuclear facilities that suffered accidents or bombardment, may be subject to wound with radioactive material should have special treatment and follow a protocol of care. If insoluble, much of the material will be retained at the wound site and the treatment is based on human anatomical structure and need to be evaluated the deposition, retention, and release for dosimetric purpose. The incorporation of soluble material may enter in the blood stream, distributed through the body and be deposited in organs, causing committed dose of ionizing radiation, before being excreted. The behavior and the assessment of radiation exposure mechanism are described with the use of biokinetic models. Upon the occurrence of these events, the first aid care of these people should follow a well-established procedure according to the scenario, the degree of severity of each case and type of radioactive material involved. This paper seeks to establish a protocol for first care of people with wounds containing radioactive material as part of the preparation for their care in specialized medical center. Measurements were made with radionuclides, characteristic of each occurrence scenario, appropriate detectors for each situation, with the performance expected for each type or model for the depth of location, activity and committed dose rates involved, using tissue-equivalent material. Moreover, the estimated the activity and internal dose were made using the conversion factor obtained with AIDE software for radionuclide of interest. (author)

  4. Protocol to treat people with wounds contaminated with radioactive material standpoint of radiological protection

    Energy Technology Data Exchange (ETDEWEB)

    Lopes, Amanda Gomes; Tauhata, Luiz; Reis, Arlene Alves; Cruz, Paulo Alberto Lima da, E-mail: amandglird@gmail.com, E-mail: tauhata@ird.gov.br, E-mail: prof.arlenealves@gmail.com, E-mail: palcruz@ird.gov.br [Instituto de Radioprotecao e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil); Bertelli Neto, Luiz, E-mail: lbertelli@lanl.gov [Los Alamos National Laboratory, Health Physics Measurements, Radiation Protection, Los Alamos, NM (United States)

    2015-07-01

    People who work in research laboratories, radioisotope production center or nuclear artifacts, nuclear medicine center, or allocated in the vicinity of nuclear facilities that suffered accidents or bombardment, may be subject to wound with radioactive material should have special treatment and follow a protocol of care. If insoluble, much of the material will be retained at the wound site and the treatment is based on human anatomical structure and need to be evaluated the deposition, retention, and release for dosimetric purpose. The incorporation of soluble material may enter in the blood stream, distributed through the body and be deposited in organs, causing committed dose of ionizing radiation, before being excreted. The behavior and the assessment of radiation exposure mechanism are described with the use of biokinetic models. Upon the occurrence of these events, the first aid care of these people should follow a well-established procedure according to the scenario, the degree of severity of each case and type of radioactive material involved. This paper seeks to establish a protocol for first care of people with wounds containing radioactive material as part of the preparation for their care in specialized medical center. Measurements were made with radionuclides, characteristic of each occurrence scenario, appropriate detectors for each situation, with the performance expected for each type or model for the depth of location, activity and committed dose rates involved, using tissue-equivalent material. Moreover, the estimated the activity and internal dose were made using the conversion factor obtained with AIDE software for radionuclide of interest. (author)

  5. Computerized Adaptive Personality Testing: A Review and Illustration With the MMPI-2 Computerized Adaptive Version.

    Science.gov (United States)

    Forbey, Johnathan D.; Ben-Porath, Yossef S.

    2007-01-01

    Computerized adaptive testing in personality assessment can improve efficiency by significantly reducing the number of items administered to answer an assessment question. Two approaches have been explored for adaptive testing in computerized personality assessment: item response theory and the countdown method. In this article, the authors…

  6. Efficiency of raw materials. Relief of the economy, environmental protection; Rohstoffeffizienz. Wirtschaft entlasten, Umwelt schonen

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-11-15

    In the contribution under consideration, the Federal Statistical Office (Wiesbaden, Federal Republic of Germany) and the Federal Environmental Agency (Dessau-Rosslau, Federal Republic of Germany) present actual data and analyses from environmentally economic total computations. In Germany, the use of raw materials became more efficient. Thus, 580 tons of raw materials per million Euro of gross domestic product were needed in the year 2008, while still 680 tons of raw materials were needed in the year 2000. The economical handling of natural resources relieves the environment and enables economic chances for individual companies and national economy. The lowering of environmental effects is to be in the focus of withdrawal and use of raw materials. This requires a stronger reduction of the consumption of raw materials. Savings potentials and an increased efficiency must be aspired in the short and medium term. The politics must create suitable incentives and framework conditions. The contribution under consideration presents new activities and strategies in order to achieve these targets.

  7. Plasma processing techniques for deposition of carbonic thin protective coatings on structural nuclear materials

    International Nuclear Information System (INIS)

    Andrei, V.; Oncioiu, G.; Coaca, E.; Rusu, O.; Lungu, C.

    2009-01-01

    Full text of publication follows: The production of nano-structured surface films with controlled properties is crucial for the development of materials necessary for the Advanced Systems for Nuclear Energy. Since the surface of materials is the zone through which materials interact with the environment, the surface science and surface engineering techniques plays an essential role in the understanding and control of the processes involved. Complex surface structures were developed on stainless steels used as structural nuclear materials: austenitic stainless steels based on Fe, austenitic steels with high content of Cr, ferrites resistant to corrosion, by various Plasma Processing methods which include: - Plasma Electrolytic (PE) treatments: the steel substrates were modified by nitriding and nitro-carburizing plasma diffusion treatments; - carbonic films deposition in Thermionic Vacuum Arc Plasma. The results of the characterization of surface structures obtained in various experimental conditions for improvement of the properties (corrosion resistance, hardness, wear properties) are reported: the processes and structures were characterized by correlation of the results of the complementary techniques: XPS, 'depth profiling', SEM, XRD, EIS. An overall description of the processes involved in the surface properties improvement, and some consideration about the new materials development for energy technologies are presented

  8. Ensuring preservation of nuclear materials at RT plant storage facilities by upgrading physical protection, containment (TID) and TV surveillance measures

    International Nuclear Information System (INIS)

    Savin, A.A.

    1999-01-01

    The upgrading of nuclear material (NM) physical protection system of storage facilities for plutonium dioxide has been carried out in the frame of contract between Sandia National Laboratories and PA Mayak. The implementation of this project is of great importance for ensuring the preservation of NM in storage. The project envisages a complex approach to the solution of the task: the use of engineered fences, detection means, observation devices, access and control thereof for the personnel; the organization of security force in such way that to give a possibility to take adequate and purposeful actions towards possible adversaries. The design includes upgrading the system for physical protection through the introduction of modern, efficient engineering devices for security, integrated system for access control and security, the system for TV surveillance [ru

  9. Computerized tomography used in non-destructive testing of welded pipes

    Energy Technology Data Exchange (ETDEWEB)

    Iovea, M; Rizescu, C; Georgescu, G; Marinescu, A; Chitescu, P; Sava, T; Neagu, M; Avram, D [Institute of Research and Design for Electrical Engineering, ICPE - Electrostatica Splaiul Unirii 313, Sect. 3, R-74204 Bucharest (Romania)

    1997-12-31

    High quality standards in operation of National Power System is ensured by the use of high performance techniques and systems for Non-Destructive Testing (NDT). In recent years a number of new developments of the non-conventional technologies in the field of NDT have been achieved. In our laboratory there have been developed two computerized technologies using {gamma}-ray computed tomography and ultrasonic imaging methods. The standard techniques for imaging from projection data is computerized tomography. The industrial computerized tomography methods consist in the measurement of thin X - or {gamma}-ray beam attenuation when passing through some selected surface of the tested object, along several directions, so that by means of an adequate mathematical algorithm, a map of linear attenuation coefficients for the scanned surface is obtained. In fact, this map gives the density of materials occurring in the surface plane. Computerized tomography equipment, in various constructive versions, are intended for the following applications: (1) NDT in those fields requiring strict control of product quality, as for instance the nuclear energy, military industry, aeronautics, transportation fields, etc., (2) research in field of materials technology, machine engineering, metallurgy, welding, etc. This paper presents the applications of Computerized Tomography in NDT, by showing the results obtained on welded pipes, as well as the facilities offered by this method. In the final part, the paper presents the concept of a mobile tomography system for industrial pipes testing. (author). 2 figs., 7 refs.

  10. Computerized tomography used in non-destructive testing of welded pipes

    International Nuclear Information System (INIS)

    Iovea, M.; Rizescu, C.; Georgescu, G.; Marinescu, A.; Chitescu, P.; Sava, T.; Neagu, M.; Avram, D.

    1996-01-01

    High quality standards in operation of National Power System is ensured by the use of high performance techniques and systems for Non-Destructive Testing (NDT). In recent years a number of new developments of the non-conventional technologies in the field of NDT have been achieved. In our laboratory there have been developed two computerized technologies using γ-ray computed tomography and ultrasonic imaging methods. The standard techniques for imaging from projection data is computerized tomography. The industrial computerized tomography methods consist in the measurement of thin X - or γ-ray beam attenuation when passing through some selected surface of the tested object, along several directions, so that by means of an adequate mathematical algorithm, a map of linear attenuation coefficients for the scanned surface is obtained. In fact, this map gives the density of materials occurring in the surface plane. Computerized tomography equipment, in various constructive versions, are intended for the following applications: 1) NDT in those fields requiring strict control of product quality, as for instance the nuclear energy, military industry, aeronautics, transportation fields, etc., 2) research in field of materials technology, machine engineering, metallurgy, welding, etc. This paper presents the applications of Computerized Tomography in NDT, by showing the results obtained on welded pipes, as well as the facilities offered by this method. In the final part, the paper presents the concept of a mobile tomography system for industrial pipes testing. (author). 2 figs., 7 refs

  11. Physical protection

    International Nuclear Information System (INIS)

    Myers, D.A.

    1989-01-01

    Physical protection is defined and its function in relation to other functions of a State System of Accounting for and Control of Nuclear Materials is described. The need for a uniform minimum international standard for physical protection as well as the need for international cooperation in physical protection is emphasized. The IAEA's INFCIRC/225/Rev. 1 (Annex 1) is reviewed. The Convention on the Physical Protection of Nuclear Material (Annex 2) is discussed. Photographs show examples of typical physical protection technology (Annex 3)

  12. Introduction to Part 3 - Pollution and protection of the seas: radioactive materials, heavy metals and oil

    International Nuclear Information System (INIS)

    Kinne, O.

    1984-01-01

    In the introduction to Vol 3. Pt 5. of Marine Ecology, the essentials of ocean management and pollution control are discussed. Human activities reducing the quality of life in the marine environment and causing negative effects on human health, resources and marine ecosystems must be controlled. In particular there must be international cooperation and control in the disposal of radioactive wastes, oils and pesticides and the discharge of organic chemicals. Long-term ecological research, monitoring and legislation are necessary to ensure the maximum degree of ecosystem protection. (U.K.)

  13. Evaluation of brain scintigraphy and computerized tomography

    International Nuclear Information System (INIS)

    Cavailloles, F.; Dairou, R.; Desbleds, M.T.; Benoit, C.; Larmande, P.; Bok, B.; Alperovitch, A.

    1983-01-01

    In order to assess the clinical usefulness of brain computerized tomography and radionuclide scan, a prospective study was performed on a series of 554 patients. The detection rate was assessed as well as the identification rate of lesions. In addition, the usefulness of both tests was appreciated subjectively by two neurologists reviewing the patients' files. Both give reasonably similar results: computerized tomography is superior to radionuclide scan in the diagnosis of tumors and intracerebral hematomas, the radionuclide scan being slightly superior in the diagnosis of purely ischemic CVA and subdural hematomas. The superiority which was subjectively conceded to computerized tomography was greater than that objectively demonstrated. However, clinical usefulness of computerized tomography was judged important in only 50% of the cases. Moreover, to request both computerized tomography and radionuclide scan appeared as having no interest in 83% of the cases. In that series, the diagnostic hypotheses were in agreement with the final diagnosis in 88% of the cases. Bias encountered in this type of studies are discussed [fr

  14. Protection and thermal management of thermoelectric generator system using phase change materials: An experimental investigation

    DEFF Research Database (Denmark)

    Ahmadi Atouei, Saeed; Rezaniakolaei, Alireza; Ranjbar, A.A.

    2018-01-01

    In most thermoelectric systems the thermal boundary conditions are transient, and thermal manage-ment of the system is critical to improve electrical performance of the system. In this study, effect of using phase change materials (PCM) to control the hot and cold side temperatures...

  15. Malicious release of radioactive materials in urban area. Exposure of the public and emergency staff, protective measures

    International Nuclear Information System (INIS)

    Koch, Wolfgang; Lange, Florentin

    2016-01-01

    The preparedness for hypothetical radiological scenarios is part of the tasks for governmental authorities, safety and emergency organizations and the staff in case of the incident. The EURATOM guideline for radiation protection has to be implemented into national laws. According to the guidelines it is required that emergency planning has to be prepared for hypothetical radiological scenarios including terroristic or other maliciously motivated attacks using radioactive materials. The study includes assumptions on the released respirable radioactivity, restriction of the hazardous area, wind induced re-suspension of radioactive dusts and inhalation exposure, and mitigation measures.

  16. Solution of environmental protection problems and complex utilization of raw materials during mining and processing of uranium ores

    International Nuclear Information System (INIS)

    Litvinenko, V.G.; Savva, P.P.

    1993-01-01

    Consideration is given to the complex of measures taken in Priargunsky industrial mine-chemical association and directed to environment protection, complex utilization of raw materials during mining and processing of uranium ores. These measures include: 1) reduction of toxic chemical agent effluents into atmosphere due to introduction of new methods and gas cleaning systems; 2) rational use of water resources owing to application of circulating water supply systems, waste waters treatment and effective control of the state of water consumption by industrial enterprises; 3) utilization of gangue and industrial solid wastes

  17. Synthesis and analysis of Mo-Si-B based coatings for high temperature oxidation protection of ceramic materials

    Science.gov (United States)

    Ritt, Patrick J.

    The use of Ni-based superalloys in turbine engines has all but been exhausted, with operating temperatures nearing the melting point of these materials. The use of ceramics in turbine engines, particularly ceramic matrix composites such as SiC/C and SiC/SiC, is of interest due to their low density and attractive mechanical properties at elevated temperatures. The same materials are also in consideration for leading edges on hypersonic vehicles. However, SiC-based composites degrade in high temperature environments with low partial pressures of oxygen due to active oxidation, as well as high temperature environments containing water or sand. The need for a protective external coating for SiC-based composites in service is obvious. To date, no coating investigated for SiC/C or SiC/SiC has been proven to be resistant to oxidation and corrosion at intermediate and high temperatures, as well as in environments deficient in oxygen. The Mo-Si-B coating shows great promise in this area, having been proven resistant to attack from oxidation at extreme temperatures, from water vapor and from calcia-magnesia-aluminosilicate (CMAS). The adaptation of the Mo-Si-B coating for ceramic materials is presented in detail here. Evaluation of the coating under a range of oxidation conditions as well as simulated re-entry conditions confirms the efficacy of the Mo-Si-B based coating as protection from catastrophic failure. The key to the oxidation and corrosion resistance is a robust external aluminoborosilica glass layer that forms and flows quickly to cover the substrate, even under the extreme simulated re-entry conditions. Suppression of active oxidation of SiC, which may occur during atmospheric re-entry and hypersonic flight trajectories, has also been examined. In order to adapt the Mo-Si-B based coating to low partial pressures of oxygen and elevated temperatures, controlled amounts of Al were added to the Mo-Si-B based coating. The resulting coating decreased the inward

  18. Bill project authorizing the approval of the amendment to the Convention on the physical protection of nuclear materials

    International Nuclear Information System (INIS)

    Juppe, Alain; Fillon, Francois

    2011-01-01

    This document deals with the amendment to the Convention on the Physical Protection of Nuclear Materials which has been adopted in July 2005. This amendment notably extended the Convention's scope, objectives, relation with other international instruments and content (regarding cooperation, sanctions, and so on). After the text of this amendment, this document contains the bill project which reports an impact study (estimated economic, financial, environmental, and legal consequences of the amendment implementation), comments the penal and criminal cooperation defined in the Convention. A table indicates the impact of the amendment's articles on the French law

  19. The Strategic Technologies for Automation and Robotics (STEAR) program: Protection of materials in the space environment subprogram

    Science.gov (United States)

    Schmidt, Lorne R.; Francoeur, J.; Aguero, Alina; Wertheimer, Michael R.; Klemberg-Sapieha, J. E.; Martinu, L.; Blezius, J. W.; Oliver, M.; Singh, A.

    1995-01-01

    Three projects are currently underway for the development of new coatings for the protection of materials in the space environment. These coatings are based on vacuum deposition technologies. The projects will go as far as the proof-of-concept stage when the commercial potential for the technology will be demonstrated on pilot-scale fabrication facilities in 1996. These projects are part of a subprogram to develop supporting technologies for automation and robotics technologies being developed under the Canadian Space Agency's STEAR Program, part of the Canadian Space Station Program.

  20. CdTe/TiO{sub 2} nanocomposite material for photogenerated cathodic protection of 304 stainless steel

    Energy Technology Data Exchange (ETDEWEB)

    Wang, Xiu-tong, E-mail: xiutongwang@gmail.com [Institutes of Oceanology, Chinese Academy of Sciences, Qingdao 266071 China (China); Wei, Qin-yi, E-mail: weiqiny200@163.com [Institutes of Oceanology, Chinese Academy of Sciences, Qingdao 266071 China (China); University of Chinese Academy of Sciences, 19 (Jia) Yuquan Road, Beijing 100049 (China); Zhang, Liang, E-mail: zzll20081988@126.com [CNOOC Information Technology co., Ltd. Beijing Branch, Beijing 100029 China (China); Sun, Hao-fen, E-mail: fyqfyx@163.com [School of Environmental and Municipal Engineering Qingdao, Qingdao Technological University, Qingdao 266033 China (China); Li, Hong, E-mail: lhqdio1987@163.com [Institutes of Oceanology, Chinese Academy of Sciences, Qingdao 266071 China (China); Zhang, Qiao-xia, E-mail: qiaoxiazhang1989@163.com [Institutes of Oceanology, Chinese Academy of Sciences, Qingdao 266071 China (China)

    2016-06-15

    Graphical abstract: - Highlights: • The photoelectric properties of TiO{sub 2} could greatly improve by doping with CdTe. • The cathodic protection property of the CdTe/TiO{sub 2} was superior to that of pure TiO{sub 2}. • The protective action of the CdTe/TiO{sub 2} for 304SS could be maintained in the dark. - Abstract: TiO{sub 2} nanotubes were fabricated by the anodization method, and CdTe was deposited on them via electrochemical deposition method. The optimal performance of the CdTe/TiO{sub 2} composites was achieved via changing the acidity of the electrolyte. Scanning electron microscopy, energy dispersive spectroscopy and X-ray diffraction were used to investigate the surface morphology, elemental analysis and phase characteristics of the composite materials. Some electrochemical tests, such as open-circuit potential, current variation versus time were carried out to investigate the photogenerated cathodic protection of 304 stainless steel by CdTe/TiO{sub 2}. The results indicated that the cathodic protection performance of the CdTe/TiO{sub 2} composite was superior to that of pure TiO{sub 2} in the wavelength of visible light. The CdTe/TiO{sub 2} composite exhibited optimal photogenerated cathodic protection properties under visible light for the corrosion potential of 304 stainless steel shifted negatively to −850 mV when the concentration of HCl in the deposition electrolyte was 1 mol/L.

  1. Computerized occlusal analysis in bruxism

    Directory of Open Access Journals (Sweden)

    Lazić Vojkan

    2006-01-01

    Full Text Available Introduction. Sleep bruxism as nocturnal parafunction, also known as tooth grinding, is the most common parasomnia (sleep disorder. Most tooth grinding occurs during rapid eye movement - REM sleep. Sleep bruxism is an oral habit characterized by rhythmic activity of the masticatory muscles (m. masseter that causes forced contact between dental surfaces during sleep. Sleep bruxism has been associated with craniomandibular disorders including temporomandibular joint discomfort, pulpalgia, premature loss of teeth due to excessive attrition and mobility, headache, muscle ache, sleep interruption of an individual and problems with removable and fixed denture. Basically, two groups of etiological factors can be distinguished, viz., peripheral (occlusal factors and central (pathophysiological and psychological factors. The role of occlusion (occlusal discrepancies as the causative factor is not enough mentioned in relation to bruxism. Objective. The main objective of this paper was to evaluate the connection between occlusal factors and nocturnal parafunctional activities (occlusal disharmonies and bruxism. Method. Two groups were formed- experimental of 15 persons with signs and symptoms of nocturnal parafunctional activity of mandible (mean age 26.6 years and control of 42 persons with no signs and symptoms of bruxism (mean age 26.3 yrs.. The computerized occlusal analyses were performed using the T-Scan II system (Tekscan, Boston, USA. 2D occlusograms were analyzed showing the occlusal force, the center of the occlusal force with the trajectory and the number of antagonistic tooth contacts. Results. Statistically significant difference of force distribution was found between the left and the right side of the arch (L%-R% (t=2.773; p<0.02 in the group with bruxism. The difference of the centre of occlusal force - COF trajectory between the experimental and control group was not significant, but the trajectory of COF was longer in the group of

  2. Formal Verification of Computerized Procedure with Colored Petri Nets

    International Nuclear Information System (INIS)

    Kim, Yun Goo; Shin, Yeong Cheol

    2008-01-01

    Computerized Procedure System (CPS) supports nuclear power plant operators in performing operating procedures which are instructions to guide in monitoring, decision making and controlling nuclear power plants. Computerized Procedure (CP) should be loaded to CPS. Due to its execution characteristic, computerized procedure acts like a software in CPS. For example, procedure flows are determined by operator evaluation and computerized procedure logic which are pre-defined. So the verification of Computerized Procedure logic and execution flow is needed before computerized procedures are installed in the system. Formal verification methods are proposed and the modeling of operating procedures with Coloured Petri Nets(CP-nets) is presented

  3. Comments by a peer review panel on the computerized radiological risk investigation system (CRRIS)

    International Nuclear Information System (INIS)

    Baker, D.A.

    1988-08-01

    This document represents the comprehensive review by experts of the documents describing the models, computer programs, and data bases making up the Computerized Radiological Risk Investigation System (CRRIS). The CRRIS methodology has been produced for the US Environmental Protection Agency's (EPA) Office of Radiation Programs (ORP) by the Health and Safety Research Division of Oak Ridge National Laboratory (ORNL) to assess the significance of releases of radioactive material from facilities handling such materials. The comments covered a wide range of aspects of the CRRIS models. Special review topics covered were uncertainty, validation, verification, and health effects. The reports making up the CRRIS documentation were reviewed in detail. The following are some of the more frequent comments about the methodology. This is a very comprehensive work, but too complex and hard to use. Too little explanation of some of the assumptions taken such as variance from standard ICRP organ weighting factors. Overly complex model for soil to root transfer and interception fraction. Gaussian plume model was used, when more state-of-art models are available. 35 refs

  4. Comments by a peer review panel on the computerized radiological risk investigation system (CRRIS)

    Energy Technology Data Exchange (ETDEWEB)

    Baker, D.A. (ed.)

    1988-08-01

    This document represents the comprehensive review by experts of the documents describing the models, computer programs, and data bases making up the Computerized Radiological Risk Investigation System (CRRIS). The CRRIS methodology has been produced for the US Environmental Protection Agency's (EPA) Office of Radiation Programs (ORP) by the Health and Safety Research Division of Oak Ridge National Laboratory (ORNL) to assess the significance of releases of radioactive material from facilities handling such materials. The comments covered a wide range of aspects of the CRRIS models. Special review topics covered were uncertainty, validation, verification, and health effects. The reports making up the CRRIS documentation were reviewed in detail. The following are some of the more frequent comments about the methodology. This is a very comprehensive work, but too complex and hard to use. Too little explanation of some of the assumptions taken such as variance from standard ICRP organ weighting factors. Overly complex model for soil to root transfer and interception fraction. Gaussian plume model was used, when more state-of-art models are available. 35 refs.

  5. The strengthening of international regime of protection of the nuclear materials and other radioactive sources

    International Nuclear Information System (INIS)

    Shiganbayev, E.

    2001-01-01

    Full text: The widening of export streams satisfies the interest of any state, but at the same time the interests of individual countries and the whole international community requires the limitation of export of goods and technologies which are potentially dangerous. The decision of this problem, finding of the optimal balance between the devotion of the principles of free trade and the necessity of limiting the danger export is one of the main tasks of the national system of security of the Republic of Kazakhstan. Kazakhstan is a country with a policy of nonproliferation. This important element of the policy of the country, directed to maintenance and strengthening of the international security, becomes the priority trend in the foreign policy of Kazakhstan. The international community decides this problem under the Comprehensive Nuclear Test Ban Treaty (CTBT), Treaty on the Non-Proliferation of Nuclear Weapons (NPT), and the Convention on the Prohibition of the Development Production and Stockpiling of Bacteriological (Biological) and Toxin Weapons and on the Destruction, Convention on the Prohibition of the Development, Production, Stockpiling and Use of Chemical Weapons and Their Destruction. At present there are four international regimes in control with the aim of nonproliferation of the weapons of mass destruction (WMD): The group of the nuclear supplies which deals with the questions of delivery of special nuclear materials and technologies, and also nuclear materials and double function technologies; Australian group works in the sphere of control for materials and technologies of chemical and biological weapons; The regime of the control of rocket technologies functioning with the aim to prevent the proliferation of rockets as means of delivery of weapon of mass destruction; Wassenaar agreement, regime of export control for usual armament, goods and double function technologies. Kazakhstan does not have nuclear weapons and participants in the Agreement

  6. The prospect of using the chitin-melanin-glukancontaining materials in measures of radiating protection

    International Nuclear Information System (INIS)

    Senyuk, O.F.; Myshkovskij, N.M.; Ivchenko, V.G.; Kovalev, V.A.; Gorovoj, L.F.; Kosyakov, V.N.; Kurchenko, V.P.; Sushinskaya, N.V.; Gavrilenko, N.V.

    2004-01-01

    An installation for testing the efficiency of Petryanov fabrics in conditions of the maximal humidity is created. It was shown in research, that chitin-melanin-glukan-containing materials (ChMGM) from higher bazidial fungi has high sorptive ability in relation to isotopes of strontium, uranium, transuranic elements, in particular to americium, and also salts of heavy metals (copper, silver, lead, chromium). Main part of metal ions are quickly absorbed by these materials. The technique of processing them by ChMGM is developed with the purpose to estimate amplification the detaining ability of these filters. High concentration of salts of alkaline and alkaline-earth metals do not essentially influence the absorption level of ChMGM heavy metals and transuranic elements

  7. Development of Highly Repellent Silica Particles for Protection of Hemp Shiv Used as Insulation Materials.

    Science.gov (United States)

    Bourebrab, Marion A; Durand, Géraldine G; Taylor, Alan

    2017-12-21

    New bio-materials have recently gained interest for use in insulation panels in walls, but wider adoption by the building industry is hindered by their intrinsic properties. The fact that such materials are mainly composed of cellulose makes them combustible, and their hydrophilic surface presents a high water uptake, which would lead to faster biodegradation. A hydrophobic treatment with silica particles was successfully synthesised via Stöber process, characterised, and deposited on hemp shiv. The surface of hemp shiv coated several times with 45 and 120 nm particles were uniformly covered, as well as extensively water repellent. Those samples could withstand in humidity chamber without loss of their hydrophobic property and no sign of mould growth after 72 h of exposure.

  8. Development of Highly Repellent Silica Particles for Protection of Hemp Shiv Used as Insulation Materials

    Directory of Open Access Journals (Sweden)

    Marion A. Bourebrab

    2017-12-01

    Full Text Available New bio-materials have recently gained interest for use in insulation panels in walls, but wider adoption by the building industry is hindered by their intrinsic properties. The fact that such materials are mainly composed of cellulose makes them combustible, and their hydrophilic surface presents a high water uptake, which would lead to faster biodegradation. A hydrophobic treatment with silica particles was successfully synthesised via Stöber process, characterised, and deposited on hemp shiv. The surface of hemp shiv coated several times with 45 and 120 nm particles were uniformly covered, as well as extensively water repellent. Those samples could withstand in humidity chamber without loss of their hydrophobic property and no sign of mould growth after 72 h of exposure.

  9. Assessing the integrity of local area network materials accountability systems against insider threats

    International Nuclear Information System (INIS)

    Jones, E.; Sicherman, A.

    1996-07-01

    DOE facilities rely increasingly on computerized systems to manage nuclear materials accountability data and to protect against diversion of nuclear materials or other malevolent acts (e.g., hoax due to falsified data) by insider threats. Aspects of modern computerized material accountability (MA) systems including powerful personal computers and applications on networks, mixed security environments, and more users with increased knowledge, skills and abilities help heighten the concern about insider threats to the integrity of the system. In this paper, we describe a methodology for assessing MA applications to help decision makers identify ways of and compare options for preventing or mitigating possible additional risks from the insider threat. We illustrate insights from applying the methodology to local area network materials accountability systems

  10. Privacy and Property? Multi-level Strategies for Protecting Personal Interests in Genetic Material

    OpenAIRE

    Laurie, Graeme

    2003-01-01

    The paper builds on earlier medico-legal work by Laurie on privacy in relation to genetic material. In this chapter, the author discusses not only Laurie's views as 'pro-privacy' but the limitations of privacy, particularly once information, genetic or otherwise, enters a public sphere. The article draws on cases and laws in the UK, continental Europe, and the US, to provide a comparative view in suggesting an alternative approach to privacy.

  11. Computerized tomography in orthopaedics and traumatology

    International Nuclear Information System (INIS)

    Boettger, E.; Heckl, R.; Rehabilitations-Krankenhaus Langensteinbach, Karlsbad

    1981-01-01

    Computerized tomography in traumatology is the selected method for the indications mentioned, so that angiographic investigations are only necessary in exceptional cases. Computerized tomography is also better than other methods when diagnozing soft part tumours, however, angiography is still indicated preoperatively for individual cases. CT is only good as additional help to conventional diagnostics with bone tumours. The differential diagnosis cysts-tumour is possible using contrast medium injections. The frequently large soft part share of tumours is recognizable with osteolytic tumours so that a better irradiation and operation planning can be effected. Diseases in the spinal canal can only be assessed with reservation using modern equipment. Lumbar dislocations of the disk can mostly not be sufficiently determined. Perivertebral abscesses can be certainly detected using computerized tomography. This is particularly so for abscesses prior to calcification. (orig.) [de

  12. The German radiation protection infrastructure with emphasis on the safety of radiation sources and radioactive material

    International Nuclear Information System (INIS)

    Czarwinski, R.; Weimer, G.

    2001-01-01

    Through federalism, Germany has a complicated but well functioning regulatory infrastructure for the safety and security of radiation sources based on a clear legal system. The main features of this infrastructure include the legal framework, the authorization and control systems and the responsibilities of different regulatory authorities, which this paper will describe. In connection with the legal framework, the provisions to control the import/export of radiation sources are briefly discussed and some information is given about the registries of sources. Protection and response measures related to unusual events concerning radiation sources, including orphan sources, will be cited. Also, the education and training of different target groups and punitive actions are touched upon in the paper. Conclusions will be drawn for future national and international actions. (author)

  13. Study of filterable materials and protection instruments by the use of radioactive aerosols

    International Nuclear Information System (INIS)

    Billard; Chevalier; Pradel

    1960-01-01

    Many filtration problems can be studied by means of radioactive aerosols. For the investigations described in this paper we have chosen the solid disintegration products of radon, the radioactive gas formed from radium, because of the facilities of generation and measurement it offers. Radon and its daughters are in fact always present in the atmosphere in sufficient concentration for certain tests. In order to improve the sensitivity of the measurements, radon from uranium ore can be used. The technique of measuring by counting α particles is rapid and easy to employ. We have thus been able to define a test for filterable substances, and to check filtering installation and individual protection instruments. (author) [fr

  14. The Ural Electrochemical Integrated Plant Sustainability Program of Nuclear Material Protection, Control and Accounting System Upgrades

    International Nuclear Information System (INIS)

    Vakhonin, Alexander; Yuldashev, Rashid; Dabbs, Richard D.; Carroll, Michael F.; Garrett, Albert G.; Patrick, Scott W.; Ku, Eshter M.

    2009-01-01

    UEIP has been working on a comprehensive sustainability program that includes establishing a site sustainability working group, information gathering, planning, organizing, developing schedule and estimated costs, trhough joint UEIP-US DOE/NNSA National Laboratory sustainability contracts. Considerable efforts have been necessary in the sustainability planning, monitoring, and control of the scope of work using tools such as Microsoft Excel, Microsoft Project and SAP R/3. While information interchanges within the sustainability program provides adequate US assurances that US funds are well spent through its quarterly reporting methodology, proper information security and protection measures are taken throughout the process. Decommissioning of outdated equipment has also become part of determining sustainability requirements and processes. The site's sustainability program has facilitated the development of a transition plan toward eventual full Russian funding of sustaining nuclear security upgrades.

  15. Circular from January 26, 2004, taken for the enforcement of the by-law from January 26, 2004, relative to the national defense secrecy protection in the domain of nuclear materials protection and control; Circulaire du 26 janvier 2004 prise pour l'application de l'arrete du 26 janvier 2004 relatif a la protection du secret de la defense nationale dans le domaine de la protection et du controle des matieres nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-01-15

    The by-law of January 26, 2004 gives a regulatory foundation to the classification of sensible informations relative to the security and physical protection of nuclear materials. This circular recalls, in this framework, the conditions of implementation of the regulation relative to the protection of national defense secrecies in the domain of the protection of nuclear facilities and materials. (J.S.)

  16. Computerized simulation of the mechanical behavior of wood-filled shock absorbers of radioactive materials transport casks; Rechnerische Simulation des mechanischen Verhaltens von holzgefuellten Stossdaempfern von Transportbehaeltern fuer radioaktive Stoffe

    Energy Technology Data Exchange (ETDEWEB)

    Neumann, Martin; Wille, Frank [Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin (Germany)

    2011-07-01

    In Germany the mechanical component inspection of transport containers for radioactive materials is performed by BAM (Bundesanstalt fuer Materialforschung und -pruefung) under consideration of national and international standards and guidelines. Experimental and calculative (analytical and numerical) techniques combined with material and/or component testing are the basis of assessment concepts according the state of the art. The authors describe the experiences of BAM concerning assessment and description of the mechanical behavior of shock absorbing components, including modeling strategies, material models, drop tests and experiment-calculation comparison. Energy absorbing components are used to reduce the impact forces at the container in case of a transport accident. In Germany wood filled thin-walled constructions are used. The deformation behavior of the wood is a main part of the calculative simulation procedures in comparison with experimental tests.

  17. Refractory Materials for Flame Deflector Protection System Corrosion Control: Refractory Ceramics Literature Survey

    Science.gov (United States)

    Calle, Luz Marina; Hintze, Paul E.; Parlier, Christopher R.; Curran, Jerome P.; Kolody, Mark; Perusich, Stephen; Whitten, Mary C.; Trejo, David; Zidek, Jason; Sampson, Jeffrey W.; hide

    2009-01-01

    Ceramics can be defmed as a material consisting of hard brittle properties produced from inorganic and nonmetallic minerals made by firing at high temperatures. These materials are compounds between metallic and nonmetallic elements and are either totally ionic, or predominately ionic but having some covalent character. This definition allows for a large range of materials, not all applicable to refractory applications. As this report is focused on potential ceramic materials for high temperature, aggressive exposure applications, the ceramics reviewed as part of this report will focus on refractory ceramics specifically designed and used for these applications. Ceramic materials consist of a wide variety of products. Callister (2000) 1 characterized ceramic materials into six classifications: glasses, clay products, refractories, cements, abrasives, and advanced ceramics. Figure 1 shows this classification system. This review will focus mainly on refractory ceramics and cements as in general, the other classifications are neither applicable nor economical for use in large structures such as the flame trench. Although much work has been done in advanced ceramics over the past decade or so, these materials are likely cost prohibitive and would have to be fabricated off-site, transported to the NASA facilities, and installed, which make these even less feasible. Although the authors reviewed the literature on advanced ceramic refractories 2 center dot 3 center dot 4 center dot 5 center dot 6 center dot 7 center dot 8 center dot 9 center dot 10 center dot 11 center dot 12 after the review it was concluded that these materials should not be ' the focus of this report. A review is in progress on materials and systems for prefabricated refractory ceramic panels, but this review is focusing more on typical refractory materials for prefabricated systems, which could make the system more economically feasible. Refractory ceramics are used for a wide variety of applications

  18. Computerized management of plant intervention tasks

    International Nuclear Information System (INIS)

    Remacle, J.; Quoidbach, G.

    1993-01-01

    The concept of 'computerized management' of plant intervention tasks was developed by TRACTEBEL in 1983 for the Belgian power plants of ELECTRABEL. The main objective of the 'Computerized Management of Plant Intervention Tasks' is to help the staff of a nuclear or a conventional power plant in planning, organizing, and carrying out any (preventive or corrective) maintenance task. It consists of a group of interconnected functional modules acting on a unique and homogeneous data base. A short description of 3 modules is given, i.e., the 'User' Module, the 'Equipment' Module and the 'Periodic Procedure' Module. (Z.S.)

  19. Computerized tomography in the diagnosis of hyperparathyroidism

    International Nuclear Information System (INIS)

    Sobota, J.; Girl, J.; Sotornik, I.; Kocandrle, V.

    1990-01-01

    Long-term experience in the application of computerized tomography to the diagnosis of hyperparathyroidism is summarized. Based on a large number of examinations (164) of parathyroid glands associated with the possibility of verification and comparison with the results of ultrasonography and other imaging methods, the potential of computerized tomography in the diagnosis of hyperparathyroidism and its advantages and limitations are summarized. It is concluded that owing to its high diagnostic precision, this technique can be regarded reliable in detecting enlarged parathyroid glands. (author). 11 figs., 1 tab., 19 refs

  20. Status report on US-Russian laboratory-to-laboratory cooperation in nuclear materials protection, control and accounting

    International Nuclear Information System (INIS)

    Mullen, M.

    1996-01-01

    In April 1994, a new program of cooperation on nuclear materials protection, control, and accounting (MPC and A) was initiated between (1) the US Department of Energy and its laboratories and (2) nuclear institutes and enterprises of the Russian Federation. The program is called the Laboratory-to-Laboratory Nuclear Materials Protection, Control, and Accounting Program (Lab-to-Lab MPC and A Program); it is one of several, complementary US-Russian MPC and A programs. The purpose of the Lab-to-Lab MPC and A Program is to accelerate progress toward a goal that is vital to the national security interests of both countries: reducing the risk of nuclear weapons proliferation by strengthening MPC and A systems. In its first two years, the program has made significant progress and has expanded to include many additional Russian participants. It has also fostered a spirit of mutual understanding, partnership, and respect between US and Russian nuclear specialists, which has paved the way for advances in other MPC and A and nuclear security cooperative efforts. This paper reviews the current status of the program. In addition to summarizing the background and objectives of the program, the paper describes highlights of recent work and outlines future directions for Lab-to-Lab MPC and A cooperation

  1. Transport properties of carboxylated nitrile butadiene rubber (XNBR)-nanoclay composites; a promising material for protective gloves in occupational exposures.

    Science.gov (United States)

    Mirzaei Aliabadi, Mostafa; Naderi, Ghasem; Shahtaheri, Seyed Jamaleddin; Forushani, Abbas Rahimi; Mohammadfam, Iraj; Jahangiri, Mehdi

    2014-02-28

    This study was conducted in response to one of the research needs of National Institute for Occupational Safety and Health (NIOSH), i.e. the application of nanomaterials and nanotechnology in the field of occupational safety and health. In order to fill this important knowledge gap, the equilibrium solubility and diffusion of carbon tetrachloride and ethyl acetate through carboxylated nitrile butadiene rubber (XNBR)-clay nanocomposite, as a promising new material for chemical protective gloves (or barrier against the transport of organic solvent contaminant), were examined by swelling procedure. Near Fickian diffusion was observed for XNBR based nanocomposites containing different amounts of nanoclay. Decontamination potential is a key factor in development of a new material for reusable chemical protective gloves applications, specifically for routine or highly toxic exposures. A thermal decontamination regime for nanocomposite was developed for the first time. Then, successive cycles of exposure/decontamination for nanocomposite were performed to the maximum 10 cycles for the first time. This result confirms that the two selected solvents cannot deteriorate the rubber-nanoclay interaction and, therefore, such gloves can be reusable after decontamination.

  2. US/Russian cooperative efforts in nuclear material protection, control, and accounting at the Siberian Chemical Combine

    International Nuclear Information System (INIS)

    Goloskokov, I.; Yarygin, A.; Petrushev, V.; Morgado, R.E.

    1998-01-01

    The Siberian Chemical Combine (SKhK) is the largest multifunction nuclear production facility in the Russian nuclear complex. Until recently, it produced and processed special nuclear material for the Russian Defense Ministry. SKhK and its US partners in the Department of Energy (DOE) US/Russian Materials Protection, Control, and Accountability (MPC and A) Program are nearing completion of the initial MPC and A upgrades at the six SKhK plant sites that were begun three years ago. Comprehensive enhancements to the physical protection and access control systems are progressing on a site-wide basis while a comprehensive MC and A system is being implemented at the Radiochemical Plant site. SKhK now produces thermal and electrical power, enriches uranium for commercial reactor fuel, reprocesses irradiated fuel, converts high-enriched uranium metal into high-enriched oxide for blending into reactor-grade, low-enriched uranium, and manufactures civilian products. The authors review the progress to date and outline plans for continuing the work in 1999

  3. Graphite intercalated polyaniline composite with superior anticorrosive and hydrophobic properties, as protective coating material on steel surfaces

    Energy Technology Data Exchange (ETDEWEB)

    Rathnayake, R.M.N.M. [National Institute of Fundamental Studies, Kandy (Sri Lanka); Graduate School of Engineering, Toyota Technological Institute, 2-12-1 Hisakata, Tempaku, Nagoya 468-8511 (Japan); Mantilaka, M.M.M.G.P.G. [Sri Lanka Institute of Nanotechnology, Nanotechnology and Science Park, Mahenwatte, Pitipana, Homagama (Sri Lanka); Hara, Masanori; Huang, Hsin-Hui [Graduate School of Engineering, Toyota Technological Institute, 2-12-1 Hisakata, Tempaku, Nagoya 468-8511 (Japan); Wijayasinghe, H.W.M.A.C., E-mail: athula@ifs.ac.lk [National Institute of Fundamental Studies, Kandy (Sri Lanka); Yoshimura, Masamichi [Graduate School of Engineering, Toyota Technological Institute, 2-12-1 Hisakata, Tempaku, Nagoya 468-8511 (Japan); Pitawala, H.M.T.G.A. [Department of Geology, University of Peradeniya, Peradeniya (Sri Lanka)

    2017-07-15

    Highlights: • In this paper, it has been utilized a novel method to prepare a new composite material of PANI/NPG graphite composite, using NPG vein graphite variety. • It is found that the composite works as an anti-corrosive coating on steel surfaces. Further, the prepared composite shows good hydrophobic ability, which is very useful in preventing corrosion on metal surfaces. • The prepared PANI/NPG composite material shows a significantly high corrosion resistance compared to alkyd resin/PANI coatings or alkyd resin coatings, on steel surfaces. - Abstract: Solid polymer composite systems are widely being used for potential technological applications in secondary energy sources and electrochromic devices. In this study, we synthesized and characterized a composite material composed of polyaniline (PANI) and natural needle platy (NPG) vein graphite. Fourier transform infrared spectroscopy (FTIR), X-ray diffraction (XRD), cyclic voltammetry (CV), scanning electron microscopy (SEM), X-ray photoelectron spectroscopy (XPS), micro-Raman analysis, thermogravimetric and differential thermal analysis (TGA/DTA), transmission electron microscopy (TEM) were used to study the structural and electrochemical properties of the prepared PANI/NPG graphite composite. XPS, FTIR, and micro-Raman analysis confirmed the existence of relevant functional groups and bonding in the prepared PANI/NPG composite material. The composite shows a very low corrosion rate, approximately 29 μm per year, and high hydrophobicity on steel surfaces, which helps to prevent the corrosion due to O{sub 2} penetration towards the metal surface. It indicates that the composite can be used as a high potential surface coating material to anticorrosion. The specific capacitance of PANI/NPG composite is 833.3 F g{sup −1}, which is higher than that of PANI. This synergistic electrical performance result proves the prepared PANI/NPG graphite composite as a suitable protective coating material for steel

  4. The study of excited oxygen molecule gas species production and quenching on thermal protection system materials

    Science.gov (United States)

    Nordine, Paul C.; Fujimoto, Gordon T.; Greene, Frank T.

    1987-01-01

    The detection of excited oxygen and ozone molecules formed by surface catalyzed oxygen atom recombination and reaction was investigated by laser induced fluorescence (LIF), molecular beam mass spectrometric (MBMS), and field ionization (FI) techniques. The experiment used partially dissociated oxygen flows from a microwave discharge at pressures in the range from 60 to 400 Pa or from an inductively coupled RF discharge at atmospheric pressure. The catalyst materials investigated were nickel and the reaction cured glass coating used for Space Shuttle reusable surface insulation tiles. Nonradiative loss processes for the laser excited states makes LIF detection of O2 difficult such that formation of excited oxygen molecules could not be detected in the flow from the microwave discharge or in the gaseous products of atom loss on nickel. MBMS experiments showed that ozone was a product of heterogeneous O atom loss on nickel and tile surfaces at low temperatures and that ozone is lost on these materials at elevated temperatures. FI was separately investigated as a method by which excited oxygen molecules may be conveniently detected. Partial O2 dissociation decreases the current produced by FI of the gas.

  5. SRB thermal protection systems materials test results in an arc-heated nitrogen environment

    Science.gov (United States)

    Wojciechowski, C. J.

    1979-01-01

    The external surface of the Solid Rocket Booster (SRB) will experience imposed thermal and shear environments due to aerodynamic heating and radiation heating during launch, staging and reentry. This report is concerned with the performance of the various TPS materials during the staging maneuver. During staging, the wash from the Space Shuttle Main Engine (SSME) exhust plumes impose severe, short duration, thermal environments on the SRB. Five different SRB TPS materials were tested in the 1 MW Arc Plasma Generator (APG) facility. The maximum simulated heating rate obtained in the APG facility was 248 Btu/sq ft./sec, however, the test duration was such that the total heat was more than simulated. Similarly, some local high shear stress levels of 0.04 psia were not simulated. Most of the SSME plume impingement area on the SRB experiences shear stress levels of 0.02 psia and lower. The shear stress levels on the test specimens were between 0.021 and 0.008 psia. The SSME plume stagnation conditions were also simulated.

  6. Attenuation characteristics of materials used in radiation protection as radiation shielding

    International Nuclear Information System (INIS)

    Almeida Junior, Airton T.; Araujo, F.G.S.; Nogueira, M.S.; Santos, M.A.P.

    2013-01-01

    Crystal glass has been widely used as shielding material in gamma radiation sources as well as x-ray generating equipment to replace the plumbiferous glass, in order to minimize exposure to individuals. In this work, ten plates of crystal glass, with dimensions of 20cm x 20cm and range of thicknesses from 0.5 to 2.0 cm, and barite concrete were irradiated with potential constants of 60kV, 80kV, 110kV, 150kV and gamma radiation of 60 Co. The curves of attenuation and of transmission were obtained for crystal glass, barite plaster and barite concrete (mGy/mA.min) at 1 meter as a function of thickness.Crystal glass has been widely used as shielding material in gamma radiation sources as well as x-ray generating equipment to replace the plumbiferous glass, in order to minimize exposure to individuals. In this work, ten plates of crystal glass, with dimensions of 20cm x 20cm and range of thicknesses from 0.5 to 2.0 cm, and barite concrete were irradiated with potential constants of 60kV, 80kV, 110kV, 150kV and gamma radiation of 60 Co. The curves of attenuation and of transmission were obtained for crystal glass, barite plaster and barite concrete (mGy/mA.min) at 1 meter as a function of thickness. (author)

  7. The computerized reactor period measurement system for China fast burst reactor-II

    International Nuclear Information System (INIS)

    Zhao Wuwen; Jiang Zhiguo

    1996-01-01

    The article simply introduces the hardware, principle, and software of the computerized reactor period measurement system for China Fast Burst Reactor-II (CFBR-II). It also gives the relation between fission yield and pre-reactivity of CFBR-II reactor system of bared reactor with decoupled-component and system of bared reactor with multiple light-material. The computerized measurement system makes the reactor period measurement into automatical and intelligent and also improves the speed and precision of period data on-line process

  8. The Japanese Nuclear Energy Encyclopedia edited and computerized to promote public acceptance

    International Nuclear Information System (INIS)

    Shimooke, T.; Kobayashi, K.; Suzuki, Y.; Kobayashi, S.

    1992-01-01

    Editing the Japanese Nuclear Energy Encyclopedia has been in progress since 1989. It will be completed in 1993. The book is intended to provide raw material for the public to have his own judgement on nuclear energy. It is also useful as a 'text book' for specialists who lecture on the nuclear energy including the social effects at public seminars and meetings. Computerization of the book is also being made simultaneously. The trial use of the partly completed book has been started by some 150 of the nominated lectures through the country from August 1992. The computerized book has been well received so far by these lectures. (J.P.N.)

  9. Proposal of programming standards for a computerized protection system

    International Nuclear Information System (INIS)

    Ehrenberger, W.; Voges, U.

    1975-05-01

    In process computer systems with high safety and reliability requirements, correctness of the software has to be proved. During the development of a program specific guidelines should be met in order to facilitate the verification of its correctness. This paper is a collection of relevant proposals. (orig.) [de

  10. Contribution of computerization to alarm processing: A French safety view

    Energy Technology Data Exchange (ETDEWEB)

    Cette, W [CEA Centre d` Etudes de Fontenay-aux-Roses, 92 (France). Inst. de Protection et de Surete Nucleaire

    1997-09-01

    Following the TMI accident and according to the requirement of the French safety authority, very important studies were performed by the French utility, Electricite de France (EDF), and assessed by the Institute for Nuclear Safety and Protection (IPSN) on reactor operation in conventional control rooms, particularly on alarm processing. These studies dealt with the man-machine interface, as well as design and exploitation requirements, presentation and management of alarm signals, and associated operating documents. The conclusions of these studies have led to improvements in French conventional control rooms. The current state of these control rooms and links between alarm sets and operating documents will be shortly presented in the first part of the paper. More recently, the computerized means implemented in the PWR 1400 MWe control rooms (N4) profoundly modified reactor operation. In particular, major advances concern alarm processing in comparison with conventional control rooms. The N4 plants provide a more rigorous approach in processing and presentation of alarms than in the past. Indeed, EDF wanted to have less alarms switched on during plant upsets and to make them more characteristic of a specific situation of the process. For example, computerization makes it easier to validate or inhibit alarms according to the situation, to allow the operator to manage alarm presentation and to propose on-line alarm sheets to the operator etc. This approach in comparison with conventional control rooms, and the IPSN assessment will be presented in the second part of this paper. (author).

  11. Contribution of computerization to alarm processing: A French safety view

    International Nuclear Information System (INIS)

    Cette, W.

    1997-01-01

    Following the TMI accident and according to the requirement of the French safety authority, very important studies were performed by the French utility, Electricite de France (EDF), and assessed by the Institute for Nuclear Safety and Protection (IPSN) on reactor operation in conventional control rooms, particularly on alarm processing. These studies dealt with the man-machine interface, as well as design and exploitation requirements, presentation and management of alarm signals, and associated operating documents. The conclusions of these studies have led to improvements in French conventional control rooms. The current state of these control rooms and links between alarm sets and operating documents will be shortly presented in the first part of the paper. More recently, the computerized means implemented in the PWR 1400 MWe control rooms (N4) profoundly modified reactor operation. In particular, major advances concern alarm processing in comparison with conventional control rooms. The N4 plants provide a more rigorous approach in processing and presentation of alarms than in the past. Indeed, EDF wanted to have less alarms switched on during plant upsets and to make them more characteristic of a specific situation of the process. For example, computerization makes it easier to validate or inhibit alarms according to the situation, to allow the operator to manage alarm presentation and to propose on-line alarm sheets to the operator etc. This approach in comparison with conventional control rooms, and the IPSN assessment will be presented in the second part of this paper. (author)

  12. Transfer of radioactive materials in the fuel cycle. Transportation systems, transportation volume and radiation protection

    International Nuclear Information System (INIS)

    Schwarz, G.

    1997-01-01

    No other aspect of the carriage of hazardous goods has been provoking such long-lived concern in the general public and in the press during the last few years as the transport of spent nuclear fuels and high-level radioactive wastes to the storage facility at Gorleben. One reason for this controversy, besides clear-cut opposition in principal against such transfer activities, is the fact that there is an information gap, so that large parts of the population are not well informed about the relevant legal safety requirements and obligations governing such transports. The article therefore tries to fill this gap, presenting information on the number and necessity of transports of radioactive materials in the nuclear fuel cycle, the relevant scenarios, the transportation systems and packing and shielding requirements, as well as information on the radiological classification and hazardousness of waste forms. (Orig.) [de

  13. CORROSION AND SURFACE PROTECTION IN MACHINE MATERIALS FRICTION HAVE DIFFERENT SURFACE PAIRS EXPERIMENTAL INVESTIGATION OF FACTORS

    Directory of Open Access Journals (Sweden)

    Senai YALCINKAYA

    2017-05-01

    Full Text Available Friction force, normal force, linear change. The normal force varies with the loads on the friction object. In order to determine the friction force and the friction coefficient, the friction object and the friction speed are used. The experimental work was carried out in three stages. In the first stage, the effect of normal force on the friction force was studied. In the second step, the friction force of the friction surface area is influenced. The effect of the change of the shear rate in step 3 on the friction force was investigated. At the last stage, the experimental study of the effect of the material selection on the friction force was made and it was seen that the aluminum / brass surface pair had the smallest friction coefficient as a result of the opening. The greatest coefficient of friction is found in the pair of glass / felt objects.

  14. Bacillus thuringiensis in caterpillars and associated materials collected from protected tropical forests in northwestern Costa Rica.

    Science.gov (United States)

    Rodríguez-Sánchez, César; Sittenfeld, Ana; Janzen, Daniel H; Espinoza, Ana M

    2006-06-01

    Bacillus thuringiensis (Bt) synthesizes crystalline inclusions that are toxic to caterpillars (Lepidoptera) and other orders of invertebrates. Materials associated with 37 caterpillars from 16 species, collected while feeding on 15 different species of host plants in dry, cloud and rain forests located in the Area de Conservación Guanacaste in northwestern Costa Rica, were examined for the presence of Bt. From a total of 101 derived samples, 25 Bt isolates were cultured: 56% from host plant leaves, 8% from caterpillar guts and 36% from caterpillar fecal pellets. Bt was isolated from at least one sample in 38% of the systems constituted by the food plant, gut and fecal pellets corresponding to a single caterpillar. Four different morphologies of crystalline inclusions were observed, with bipyramidal and irregular crystal morphologies being the most prevalent.

  15. An activated barrier for protection of special nuclear materials in vital areas

    International Nuclear Information System (INIS)

    Timm, R.E.; Miranda, J.E.

    1984-01-01

    The Argonne National Laboratory and Sandia National Laboratory have recently installed an activated barrier, the Access Denial System (ADS) for the upgrade of safeguards of special nuclear materials. The technology of this system was developed in the late 70's by Sandia National Laboratory-Albuquerque. The installation was the first for the Department of Energy. Subsequently, two additional installations have been completed. The Access Denial System, combined with physical restraints, provide the system delay. The principal advantages of the activated barrier are: (1) it provides an order of magnitude improvement in delay over that of a fixed barrier, (2) it can be added to existing vital areas with a minimum of renovations, (3) existing operations are minimally impacted, and (4) health and safety risks are virtually nonexistent. Hardening of the vital areas using the ADS was accomplished in a costeffective manner

  16. Activated barrier for protection of special nuclear materials in vital areas

    International Nuclear Information System (INIS)

    Timm, R.E.; Miranda, J.E.; Reigle, D.L.; Valente, A.D.

    1984-01-01

    The Argonne National Laboratory and Sandia National Laboratory have recently installed an activated barrier, the Access Denial System (ADS) for the upgrade of safeguards of special nuclear materials. The technology of this system was developed in the late 70's by Sandia National Laboratory-Albuquerque. The installation was the first for the Department of Energy. Subsequently, two additional installations have been completed. The Access Denial System, combined with physical restraints, provide the system delay. The principal advantages of the activated barrier are: (1) it provides an order of magnitude improvement in delay over that of a fixed barrier, (2) it can be added to existing vital areas with a minimum of renovations, (3) existing operations are minimally impacted, and (4) health and safety risks are virtually nonexistent. Hardening of the vital areas using the ADS was accomplished in a cost-effective manner. 3 references, 1 figure, 1 table

  17. The industrial computerized tomography applied to the rock analysis

    International Nuclear Information System (INIS)

    Tetzner, Guaraciaba de Campos

    2008-01-01

    This work is a study of the possibilities of the technical applications of Computerized Tomography (CT) by using a device developed in the Radiation Technology Center (CTR), Institute for Energy and Nuclear Research (IPEN-CNEN/SP). The equipment consists of a gamma radiation source ( 60 Co), a scintillation detector of sodium iodide doped with thallium (NaI (Tl)), a mechanical system to move the object (rotation and translation) and a computer system. This operating system has been designed and developed by the CTR-IPEN-CNEN/SP team using national resources and technology. The first validation test of the equipment was carried out using a cylindrical sample of polypropylene (phantom) with two cylindrical cavities (holes) of 5 x 25 cm (diameter and length). In these tests, the holes were filled with materials of different density (air, oil and metal), whose attenuation coefficients are well known. The goal of this first test was to assess the response quality of the equipment. The present report is a study comparing computerized tomography equipment CTR-IPEN-CNEN/SP which uses a source of gamma radiation ( 60 Co) and other equipment provided by the Department of Geosciences in the University of Texas (CTUT), which uses an X-ray source (450 kV and 3.2 mA). As a result, the images obtained and the comprehensive study of the usefulness of the equipment developed here strengthened the proposition that the development of industrial computerized tomography is an important step toward consolidating the national technology. (author)

  18. Robinson's Computerized Strabismus Model Comes of Age

    NARCIS (Netherlands)

    H.J. Simonsz (Huib); H. Spekreijse (Henk)

    1996-01-01

    textabstractIn this article we review our further development of D.A. Robinson's computerized strabismus model. First, an extensive literature study has been carried out to get more accurate data on the anatomy of the average eye and the eye muscles, and about how these vary with age and with

  19. Computerized Italian criticality guide, description and validation

    International Nuclear Information System (INIS)

    Carotenuto, M.; Landeyro, P.A.

    1988-10-01

    Our group is developing an 'expert system' for collecting engineering know-how on back-end nuclear plant design. An expert system is the most suitable software tool for our problem. During the analysis, the design process was divided into different branches. At each branch of the design process the Expert System relates a computerized design procedure. Any design procedure is composed of a set of design methods, together with their condition of application and reliability limits. In the framework of this expert system, the nuclear criticality safety analysis procedure was developed, in the form of a computerized criticality guide, attempting to reproduce the designer's normal 'reasoning' process. The criticality guide is composed of two parts: A computerized text, including theory, a description of the accidents occurred in the past and a description of the italian design experience; An interactive computer aided calculation module, containing a graphical facility for critical parameter curves. In the present report are presented the criticality guide (computerized Italian Criticality Guide) and its validation test. (author)

  20. Computerized management information systems and organizational structures

    Science.gov (United States)

    Zannetos, Z. S.; Sertel, M. R.

    1970-01-01

    The computerized management of information systems and organizational structures is discussed. The subjects presented are: (1) critical factors favoring centralization and decentralization of organizations, (2) classification of organizations by relative structure, (3) attempts to measure change in organization structure, and (4) impact of information technology developments on organizational structure changes.

  1. Some procedures for computerized ability testing

    NARCIS (Netherlands)

    van der Linden, Willem J.; Zwarts, Michel A.

    1989-01-01

    For computerized test systems to be operational, the use of item response theory is a prerequisite. As opposed to classical test theory, in item response models the abilities of the examinees and the properties of the items are parameterized separately. Hence, when measuring the abilities of

  2. Implementation of a Computerized Maintenance Management System

    Science.gov (United States)

    Shen, Yong-Hong; Askari, Bruce

    1994-01-01

    A primer Computerized Maintenance Management System (CMMS) has been established for NASA Ames pressure component certification program. The CMMS takes full advantage of the latest computer technology and SQL relational database to perform periodic services for vital pressure components. The Ames certification program is briefly described and the aspects of the CMMS implementation are discussed as they are related to the certification objectives.

  3. Computerizing Maintenance Management Improves School Processes.

    Science.gov (United States)

    Conroy, Pat

    2002-01-01

    Describes how a Computerized Maintenance Management System (CMMS), a centralized maintenance operations database that facilitates work order procedures and staff directives, can help individual school campuses and school districts to manage maintenance. Presents the benefits of CMMS and things to consider in CMMS selection. (EV)

  4. The limited angle problem in computerized tomography

    International Nuclear Information System (INIS)

    Louis, A.K.

    1984-01-01

    Fast reconstruction formulae in X-ray computerized tomography demand the directions, in which the measurements are taken, to be equally distributed over the whole circle. In many applications data can only be provided in a restricted range. Here the intrinsic difficulties are studied by giving a singular value decomposition of the Radon transform in a restricted range. Practical limitations are deduced. (orig.)

  5. Ethics and the Computerization of Pharmacy.

    Science.gov (United States)

    McCarthy, Robert L.; Perrolle, Judith A.

    1991-01-01

    The current and potential impact of computerization on pharmacy practice is discussed, focusing on ethical dilemmas in the pharmacist-patient relationship, confidentiality of records, and the role of artificial intelligence in decision making about drug therapy. Case studies for use by teachers of pharmaceutical ethics are provided. (Author/MSE)

  6. Individual Differences in Computerized Adaptive Testing.

    Science.gov (United States)

    Kim, JinGyu

    Research on the major computerized adaptive testing (CAT) strategies is reviewed, and some findings are reported that examine effects of examinee demographic and psychological characteristics on CAT strategies. In fixed branching strategies, all examinees respond to a common routing test, the score of which is used to assign examinees to a…

  7. Computerized management support for swine breeding farms

    NARCIS (Netherlands)

    Huirne, R.B.M.

    1990-01-01

    1. INTRODUCTION

    The investigations described in this thesis have been directed towards computerized management support for swine breeding farms, focused on sow productivity and profitability. The study is composed of three basic parts: (1) basic description and

  8. Computerized three-dimensional normal atlas

    International Nuclear Information System (INIS)

    Mano, Isamu; Suto, Yasuzo; Suzuki, Masataka; Iio, Masahiro.

    1990-01-01

    This paper presents our ongoing project in which normal human anatomy and its quantitative data are systematically arranged in a computer. The final product, the Computerized Three-Dimensional Normal Atlas, will be able to supply tomographic images in any direction, 3-D images, and coded information on organs, e.g., anatomical names, CT numbers, and T 1 and T 2 values. (author)

  9. The Computerized Reference Department: Buying the Future.

    Science.gov (United States)

    Kriz, Harry M.; Kok, Victoria T.

    1985-01-01

    Basis for systematic computerization of academic research library's reference, collection development, and collection management functions emphasizes productivity enhancement for librarians and support staff. Use of microcomputer and university's mainframe computer to develop applications of database management systems, electronic spreadsheets,…

  10. Computerized system for measuring cerebral metabolism

    International Nuclear Information System (INIS)

    McGlone, J.S.; Hibbard, L.S.; Hawkins, R.A.; Kasturi, R.

    1987-01-01

    A computerized stereotactic measurement system for evaluating rat brain metabolism was developed to utilize the large amount of data generated by quantitative autoradiography. Conventional methods of measurement only analyze a small percent of these data because these methods are limited by instrument design and the subjectiveness of the investigator. However, a computerized system allows digital images to be analyzed by placing data at their appropriate three-dimensional stereotactic coordinates. The system automatically registers experimental data to a standard three-dimensional image using alignment, scaling, and matching operations. Metabolic activity in different neuronal structures is then measured by generating digital masks and superimposing them on to experimental data. Several experimental data sets were evaluated and it was noticed that the structures measured by the computerized system, had in general, lower metabolic activity than manual measurements had indicated. This was expected because the computerized system measured the structure over its volume while the manual readings were taken from the most active metabolic area of a particular structure

  11. How will computerization revolutionize managed care?

    Science.gov (United States)

    Trabin, T

    1994-01-01

    Computerization of behavioral health care information systems is revolutionizing how payors, managed care companies, and providers exchange information. In this article, an imaginary scenario is depicted of how patient data will be accessed and communicated to facilitate care management of behavioral health care services in the near future.

  12. Computerized Italian criticality guide, description and validation

    Energy Technology Data Exchange (ETDEWEB)

    Carotenuto, M; Landeyro, P A [ENEA - Dipartimento Ciclo del Combustibile, Centro Ricerche Energia, Casaccia (Italy)

    1988-10-15

    Our group is developing an 'expert system' for collecting engineering know-how on back-end nuclear plant design. An expert system is the most suitable software tool for our problem. During the analysis, the design process was divided into different branches. At each branch of the design process the Expert System relates a computerized design procedure. Any design procedure is composed of a set of design methods, together with their condition of application and reliability limits. In the framework of this expert system, the nuclear criticality safety analysis procedure was developed, in the form of a computerized criticality guide, attempting to reproduce the designer's normal 'reasoning' process. The criticality guide is composed of two parts: A computerized text, including theory, a description of the accidents occurred in the past and a description of the italian design experience; An interactive computer aided calculation module, containing a graphical facility for critical parameter curves. In the present report are presented the criticality guide (computerized Italian Criticality Guide) and its validation test. (author)

  13. Geometrical efficiency in computerized tomography: generalized model

    International Nuclear Information System (INIS)

    Costa, P.R.; Robilotta, C.C.

    1992-01-01

    A simplified model for producing sensitivity and exposure profiles in computerized tomographic system was recently developed allowing the forecast of profiles behaviour in the rotation center of the system. The generalization of this model for some point of the image plane was described, and the geometrical efficiency could be evaluated. (C.G.C.)

  14. Bacterial Biofilm Characterization and Microscopic Evaluation of the Antibacterial Properties of a Photocatalytic Coating Protecting Building Material

    Directory of Open Access Journals (Sweden)

    Thomas Verdier

    2018-03-01

    Full Text Available Use of photocatalytic paint-like coatings may be a way to protect building materials from microbial colonization. Numerous studies have shown the antimicrobial efficiency of TiO 2 photocatalysis on various microorganisms. However, few have focused on easy-to-apply solutions and on photocatalysis under low irradiance. This paper focuses on (a the antibacterial properties of a semi-transparent coating formulated using TiO 2 particles and (b the microscopic investigations of bacterial biofilm development on TiO 2 -coated building materials under accelerated growth conditions. Results showed significant antibacterial activity after few hours of testing. The efficiency seemed limited by the confinement of the TiO 2 particles inside the coating binder. However, a pre-irradiation with UV light can improve efficiency. In addition, a significant effect against the formation of a bacterial biofilm was also observed. The epifluorescence approach, in which fluorescence is produced by reflect rather than transmitted light, could be applied in further studies of microbial growth on coatings and building materials.

  15. Compensation of the Persistent Current Multipoles in the LHC Dipoles by making the Coil Protection Sheet from Soft Magnetic Material

    CERN Document Server

    Völlinger, C

    2000-01-01

    This note presents a scheme for compensating the persistent current multipole errors of the LHC dipoles by making the coil protection sheets from soft magnetic material of 0.5 mm thickness. The material properties assumed in this study are those of iron sheets with a very low content of impurities (99.99% pure Fe). The non-linearities in the upramp cycle on the b3 multipole component can be reduced by the factor of four (while decreasing the b5 variation by the factor of two. Using sheets of slightly different thicknesses offers a tuning possibility for the series magnet coils and can compensate deviations arising from cables of different suppliers. The calculation method is based on a semi-analytical hysteresis model for hard superconductors and an M(B) - iteration using the method of coupled boundary elements - finite elements (BEM - FEM). It is now possible to compute persistent current multipole errors of geometries with arbitrarily shaped iron yokes and thin layers of soft magnetic material such as tunin...

  16. Computerized reactor monitor and control for research reactors

    International Nuclear Information System (INIS)

    Buerger, L.; Vegh, E.

    1981-09-01

    The computerized process control system developed in the Central Research Institute for Physics, Budapest, Hungary, is described together with its special applications at research reactors. The nuclear power of the Hungarian research reactor is controlled by this computerized system, too, while in Lybia many interesting reactor-hpysical calculations are built into the computerized monitor system. (author)

  17. 39 CFR 501.15 - Computerized Meter Resetting System.

    Science.gov (United States)

    2010-07-01

    ... 39 Postal Service 1 2010-07-01 2010-07-01 false Computerized Meter Resetting System. 501.15... AND DISTRIBUTE POSTAGE EVIDENCING SYSTEMS § 501.15 Computerized Meter Resetting System. (a) Description. The Computerized Meter Resetting System (CMRS) permits customers to reset their postage meters at...

  18. Bacillus thuringiensis in caterpillars and associated materials collected from protected tropical forests in northwestern Costa Rica

    Directory of Open Access Journals (Sweden)

    César Rodríguez-Sánchez

    2006-06-01

    Full Text Available Bacillus thuringiensis (Bt synthesizes crystalline inclusions that are toxic to caterpillars (Lepidoptera and other orders of invertebrates. Materials associated with 37 caterpillars from 16 species, collected while feeding on 15 different species of host plants in dry, cloud and rain forests located in the Área de Conservación Guanacaste in northwestern Costa Rica, were examined for the presence of Bt. From a total of 101 derived samples, 25 Bt isolates were cultured: 56% from host plant leaves, 8% from caterpillar guts and 36% from caterpillar fecal pellets. Bt was isolated from at least one sample in 38% of the systems constituted by the food plant, gut and fecal pellets corresponding to a single caterpillar. Four different morphologies of crystalline inclusions were observed, with bipyramidal and irregular crystal morphologies being the most prevalent. Rev. Biol. Trop. 54(2: 265-271. Epub 2006 Jun 01.Bacillus thuringiensis (Bt sintetiza inclusiones cristalinas que resultan tóxicas para algunas larvas de lepidópteros y otros órdenes de invertebrados. Su presencia fue examinada en materiales asociados a 37 orugas de mariposas de 16 especies, las cuales fueron colectadas mientras se alimentaban en 15 especies diferentes de plantas hospederas en bosques secos, nubosos y húmedos localizados dentro del Área de Conservación Guanacaste (ACG en el noroeste de Costa Rica. A partir de un total de 101 muestras se obtuvo 25 aislamientos de Bt: 56% a partir de material foliar de las plantas hospederas, 8% a partir del contenido intestinal de las larvas y 36% a partir de sus excrementos. Esta bacteria fue cultivada a partir de al menos uno de los 3 diferentes tipos de muestra asociados a una oruga particular (planta hospedera, intestino, excremento en 38% de los casos posibles. En la colección de aislamientos obtenida se observaron cuatro morfologías de inclusiones cristalinas, siendo aquellas bipiramidales e irregulares las más prevalentes.

  19. Development of a ceramic material to cover walls to be applied in diagnostic radiological protection; Desenvolvimento de um material ceramico para utilizacao em protecao radiologica diagnostica

    Energy Technology Data Exchange (ETDEWEB)

    Frimaio, Audrew

    2006-07-01

    This study aims to formulate a ceramic composition for wall coating seeking to contribute to the optimization of diagnosis rooms' shielding. The work was based on experimental measures of X-radiation attenuation (80 and 100 kV) using ceramic coating materials containing different ceramic bases (red, white, gres, stoneware porcelain tiles, etc). Among the appraised ceramic bases, the white gres presented better attenuation properties and it was considered the most suitable material for the targets of this work. Different formulations of white gres were studied and altered in order to obtain better attenuation properties. Simulations of ceramic compositions using gres coating were made maintaining the percentages of 12-20% clay; 6-18% kaolin; 12-25% phyllite; 8-14% quartz; 1018% feldspar; 32-40% pegmatite and 6-8% talc in the composition of the necessary raw-material. The quantitative and qualitative chemical compositions of these materials were also evaluated and the most common representative elements are SiO{sub 2}, Fe{sub 2}O{sub 3}, Al{sub 2}O{sub 3}, CaO and Ti{sub 2}O{sub 3}. Formulations containing Pb and Ba oxides were studied, considering that CaO can be replaced by PbO or BaO. The attenuation properties for X-radiation were investigated by computer simulations considering the incident and transmitted X-ray spectra for the different studied compositions and they were compared to the properties of the reference materials Pb, Ba and BaSO{sub 4} (barite). The results obtained with the simulations indicated the formulated composition of gres ceramic base that presented better attenuation properties considering the X-ray energies used in diagnosis (80, 100 and 150 kV). Ceramic plates based on the formulated compositions that presented lower percentage differences related to Pb were experimentally produced and physically tested as wall coating and protecting barrier. Properties as flexion resistance module, density, load rupture, water absorption and X

  20. Current Challenges in Radiation Protection in Medicine

    International Nuclear Information System (INIS)

    KASE, K.R.

    2008-01-01

    Radiation protection professionals in medical facilities and practices are being challenged by new imaging technologies that use x-rays or radioactive materials. These include faster computerized tomography (CT) scanners, new interventional techniques that use extended fluoroscopy time, increased use of positron emission tomography (PET), and digital imaging techniques. More frequently these technologies are being fused into a single procedure, such as combined CT and PET scanning. Radiation Protection professionals are challenged to (1) be aware of developing technologies and clinical techniques, (2) analyze the potential radiation risks to patients and staff, (3) initiate necessary radiation safety training for medical staff, and (4) be involved in planning, dose measurement and optimization of the procedure to achieve appropriate dose control and ALARA